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Sample records for desequilibres radioactifs 238u-230th-226ra

  1. 238U-230Th-226Ra radioactive disequilibria in the products from 1707 eruption of Fuji volcano, Japan

    International Nuclear Information System (INIS)

    Kurihara, Yuichi; Takahashi, Masaomi; Sato, Jun

    2008-01-01

    Time scale of magmatic processes in the 1707 eruptive activity of Fuji volcano, Japan, was estimated by the 238 U- 230 Th- 226 Ra disequilibria observed in the 1707 volcanic products. The activity ratios of 226 Ra/ 230 Th in the products were larger than unity, being enriched in 226 Ra relative to 230 Th. The decay-corrected 226 Ra/ 230 Th activity ratio to the time of the eruption versus 238 U/ 230 Th activity ratio diagram for the 1707 volcanic products showed a positive correlation, suggesting that the 238 U/ 230 Th- 226 Ra disequilibria occurred during the magma genesis of Fuji volcano. The 230 Th- 226 Ra disequilibria in the 1707 volcanic products suggested that the time scale from the magma genesis to the eruption, including the melting of the mantle wedge, magma storage and magmatic differentiation from basalt to andesite, was less than 8000 years. (author)

  2. 238U-230Th-226Ra systematics applied to the active oceanic volcanism. Constraints on the duration and processes of magmas formation

    International Nuclear Information System (INIS)

    Claude-Ivana, Ch.

    1997-02-01

    The development of a new precise analytical technique for measuring radioactive disequilibria by TIMS has enabled to put constraints on both the extend and time scale of incompatible element fractionation during magma formation in oceanic islands. Three different settings have been studied: the Grande Comore volcanoes (Comores archipelago), Tenerife and Lanzarote volcanism (Canary islands) and four islands within the Azores: Sao Miguel, Terceira, Pico and Faial islands. The Comores and Canaries archipelagoes are both lying on an old thick oceanic lithosphere. The detailed case in Grande Comore shows evidence for a process of interaction of the Comore plume with the underlying lithosphere. In the Canaries, the lithosphere also contributes to lava formation either during the differentiation (in Tenerife) or during mantle melting (in Lanzarote). Within the Azores, U-series measurements reveal large geochemical and isotopic variations between the different islands that we interpret as reflecting heterogeneities in the Azore plume. In particular, the U-Th fractionation in Sao Miguel volcanics is though to result from melting of an hydrous sediment-bearing mantle. The magma transit times have been found to be very short (1000 yr) in all the basaltic series. This very rapid migration of the melts is an evidence for the absence of large magma chamber and for processes of fracturing during melt transports. However, this model does not apply in the case of the very evolved volcanic series in Tenerife island (Canaries) where transit times of c.a. 100000 yr indicate the presence of a large magmatic reservoir. (author)

  3. Transfer of 238U, 230Th, 226Ra, and 210Pb from soils to tree and shrub species in a Mediterranean area

    International Nuclear Information System (INIS)

    Blanco Rodriguez, P.; Vera Tome, F.; Lozano, J.C.; Perez Fernandez, M.A.

    2010-01-01

    The soil-to-plant transfer factors of natural uranium isotopes ( 238 U and 234 U), 230 Th, 226 Ra, and 210 Pb were studied in a disused uranium mine located in the Extremadura region in the south-west of Spain. The plant samples included trees (Quercus ilex, Quercus suber, and Eucalyptus cameldulensis) and one shrub (Cytisus multiflorus). All of them are characteristic of Mediterranean environments. The activity concentrations in leaves and fruit were determined for the tree species at different stages of growth. For the shrub, the total above-ground fraction was considered in three seasons. For old leaves and fruit, the highest activity concentrations were found in Eucalyptus cameldulensis for all the radionuclides studied, except in the case of 230 Th that presented similar activity concentrations in all of the tree species studied. In every case, the transfer to fruit was less than the transfer to leaves. In the shrub, the results depended on the season of sampling, with the highest value obtained in spring and the lowest in autumn. Important correlations were obtained for 238 U and 226 Ra between the activity ratio in soils with that in leaves or fruit.

  4. U-series radioactive disequilibria 238U-230Th-226Ra: discussions on sources and processes responsible for volcanism of the Andean cordillera and on the deglaciation in Iceland

    International Nuclear Information System (INIS)

    Chmeleff, J.

    2005-10-01

    Thanks to precise analyses of uranium series radioactive disequilibria, permitted by improvements of mass spectrometry data acquisition and optimization of chemistry, two questions were tackled and answers about the periods of glaciation in Iceland and the petrogenesis of Andean lavas were proposed. Two methods were used to date lava flows from the Reykjanes peninsula and the island of Heimaey, in Iceland, directly linked to the periods of deglaciation or reheating around the last ice age. An original method based on the use of segregation veins present in the lava flows has been developed. Thanks to the formation of this particular geological object this methods permits to be freed from xeno-crystals when using the internal isochron method in the 238 U- 230 Th system. Using this method some constraints are brought both on the quaternary geology of the area of Reykjavik and on the age of the end of the Wurm glaciation on Heirnaey. In parallel, due to the homogeneity of the historical and Holocene lavas of the Reykjanes peninsula, regarding the ( 230 Th/ 232 Th) and Th/U ratios, it is possible to derive the ( 230 Th/ 232 Th) ratio in time to determine the age of lava flows installed during the ice age. Thus we confirmed that the magnetic excursion recorded in the Skalamaelifell lava flow is most probably the same one as that of Laschamp-Olby and that at this time (approximately 48.000 years) the Reykjanes peninsula was entirely covered with a glacier. Thanks to this method the extent of the glacier was also constrained by dating of a picritic shield around 22.000 years, thus the peninsula has to be free of any ice cap despite the fact that glaciation is the most intense around this time.Then Andean arc magmas petrogenesis was constrained in time and space. Almost systematic excesses of 226 Ra compared to 230 Th in lavas of austral, southern and northern volcanic zones of the Andes (AVZ, SVZ and NVZ) constrain the ascending time from the source to the surface after their formation which is necessarily fast (less than 8.000 years to preserve these disequilibria). We show that eruptive activity and excesses of 238 U (and to a lesser extent 226 Ra) compared to 230 Th are linked. This observation suggests that the most active volcanoes (Villarrica and Llairna for the SVZ) are those whose source is enriched in fluids, coming from the subducted plate and sediments which cover it, during partial melting of the mantle wedge and that radioactive disequilibria tell us about the geodynamic context on a regional scale. Finally a more precise study of particular volcanoes (Nevado de Longavi (SVZ) and Guagua Pichincha (NVZ)), suggests that-uranium series disequilibria record the evolution of a volcano in time. Thus the complex history of Nevado de Longavi and the particular signals of this volcano can be translated in term of variation of partial melting degree of the source, fractional crystallization or crustal contamination. In the case of Guagua Pichincha volcano, the adakitic source of the volcanic activity could be discussed thanks to the study of 238 U and 226 Ra excesses compared to 230 Th and a model of adakites formation by partial melting of an hydrated mantle wedge followed by fractional crystallization of garnet at high pressure will be proposed. (author)

  5. Dating methods based on the radioactive disequilibrium (1961); Methodes de chronologie par le desequilibre radioactif (1961)

    Energy Technology Data Exchange (ETDEWEB)

    Coquema, C; Coulomb, R; Goldsztein, M; Schiltz, J C [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1961-07-01

    The existence in the uranium families of two long-life descendants: ionium (half-life 80000 years) and protactinium (half-life 32000 years), together with the differences in geochemical behaviour of the various natural radio-elements, particularly thorium, make it possible to envisage several models of geological time-scales covering-periods from 0 to 500000 years The theory of two of the most important models i s developed and methods are described for making radiochemical measurements on the various nuclides which are essential for resolving these models (U{sup 238}, Th{sup 234}, Th{sup 230}, Ra{sup 226}, Pa{sup 231}, Th{sup 232}, Th{sup 228}, Po{sup 210}) An example of dating is given in the case of a secondary mineralisation on a weathered portion of a deposit in the Limouzat (Forez). Samples of autunite and chalcolite taken at different levels of the mine were calculated to be between 30000 and 240000 years old. (authors) [French] L'existence dans les familles de l'uranium de deux descendants a vie longue: ionium (periode 80000 ans) et protactinium (periode 32000 ans), ainsi que les differences tie comportement geochimique des divers radioelements naturels, en particulier du thorium, permettent d'envisager plusieurs modeles d'echelles geochronologiques couvrant un domaine allant de 0 a 500000 ans. Nous developpons la theorie de deux de ces modeles les plus importants, et decrivons les methodes de dosage radiochimiques des divers nucleides dont la connaissance est necessaire a la resolution des modeles ({sup 238}U, {sup 234}Th, {sup 230}Th, {sup 226}Ra, {sup 231}Pa, {sup 232}Th, {sup 228}Th, {sup 210}Po). On donne un exemple de chronologie d'une mineralisation secondaire sur la partie alteree du gisement du Liznouzat (Forez). Des echantillons d'autunite et de chalcolite pris a differents niveaux de la mine ont pu etre dates de 30000 a 240000 ans. (auteurs)

  6. Report on intercomparison IAEA/AG-B-1 of radionuclide measurements in marine algae sample

    International Nuclear Information System (INIS)

    1985-09-01

    This report includes results of the intercomparison exercise organized to enable analysts involved in measurements to check the analytical performance of their measuring methods on homogeneous seaweed material and also to establish reference values for radionuclides 40 K, 54 Mn, 58 Co, 60 Co, 65 Zn, 134 Cs, 137 Cs, 90 Sr, 99 Tc, 238 Pu, 239+240 Pu, 241 Am, 238 U, 230 Th, 226 Ra, 210 Pb, 210 Po, 232 Th, 228 Ra and 228 Th for the advantage of all those who need well-characterized standard material for calibration purposes. The sample of the brown alga Fucus vesiculosus from the coastal area of the Southwest Baltic near the Swedish nuclear plant at Barseback was made available for intercalibration in 47 laboratories in 26 countries. The results were obtained by gamma spectrometry, alpha spectrometry and beta counting

  7. Electronic sorting of radioactive ores; Triage electronique des minerais radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Sandier, J.

    1958-01-15

    Electronic sorting of radioactive ores consists in passing the rock lumps, after sieving, one by one in front of radioactivity detectors; these detectors command electromechanical systems which class the ores according to their radioactivity level. This note sets on the state of progress of the work going on at the D.R.E.M.: use of scintillometers for γ-ray detection, with circuits carrying magnetic memories to improve their operation; results of laboratory and semi-industrial tests on several deposits; description of the material, data on the first factory project; notes on the financial returns of the process. A description is also given of the electronic sorting material used skip by skip for a first rough classification of the ores according to their content, as they leave the shaft. (author) [French] Le triage electronique des minerais radioactifs consiste a faire passer, apres criblage, les cailloux un par un devant des detecteurs de radioactivite; ces detecteurs commandent des systemes electromecaniques qui classent les minerais selon leur niveau de radioactivite. La note expose l'etat d'avancement des travaux en cours a la D.R.E.M: utilisation des scintillometres pour la detection des rayonnements γ, de circuits comportant des memoires magnetiques pour ameliorer le fonctionnement; resultats d'essais de laboratoire et semi-industriels sur plusieurs gisements; description du materiel, donnees sur le premier projet d'usine; notes sur la rentabilite du procede. Est egalement decrit le materiel de triage electronique skip par skip utilise pour une premiere classification grossiere des minerais selon leurs teneurs, des la sortie des puits. (auteur)

  8. Radioecological investigations of uranium mill tailings systems. Progress report, September 1, 1979-September 30, 1980

    International Nuclear Information System (INIS)

    Whicker, F.W.

    1980-01-01

    The initial 13 months of this program have been devoted to staffing, development of a radiochemistry capability, development of a mill tailings reclamation study, studies on hydraulic properties of soils, initiation of plant uptake studies, preparation for metabolic studies with deer and antelope, and sample collections. Through the addition of new personnel and equipment, we are rapidly developing analytical capabilities for 238 U, 230 Th, 226 Ra, 210 Pb and 210 Po in matrices such as soil, water, plant material, and animal tissues. A 4 acre study site was developed in cooperation with the Pathfinder Mines Corp. at the Shirley Basin Uranium Mine in Wyoming. The study site is designed for investigations on the influence of various kinds and thicknesses of mill tailings soil covers on the integrity of reclaimed tailings and inherent radionuclides. Studies on the hydraulic properties of various soil materials were conducted and data analysis is in progress. Plots and procedures for conducting plant uptake studies on uranium and progeny were established and long-term investigations have been initiated. A colony of tame mule deer and pronghorn antelope has been developed for studies on the uptake and retention of 210 Pb and 210 Po. Numerous collections of soil, vegetation and water from the Shirley Basin Uranium Mine environs were conducted and radiochemical assay is in progress

  9. Radioecological investigations of uranium mill tailings systems: Final report for the period September 1, 1979 through April 30, 1987

    International Nuclear Information System (INIS)

    Whicker, F.W.; Ibrahim, S.A.

    1987-01-01

    This document is the final report on studies of the integrity and transport of uranium and radioactive progeny in active and reclaimed uranium mill tailings. The overall program was designed to provide basic information on the radioecology of 238 U, 230 Th, 226 Ra, 210 Pb and 210 Po, responses of plants and animals to the landscape disruptions associated with uranium production, and guidance for impact analysis, mitigation and regulation of the uranium industry. The studies reported were conducted at the Shirley Basin Uranium Mine, which is operated by the Pathfinder Mines Corporation. The mine/mill operation, located in southeastern Wyoming, is typical in terms of the ore body, mill process, and ecological setting of many uranium production centers in the western United States. The research was motivated originally by the general lack of knowledge on the transport of uranium and its radioactive daughter products through the environment, particularly through food chains in the immediate environs of uranium production operations. The work was also motivated by the relatively high contribution of uranium mining and milling to the radiation exposure of the general population from the nuclear fuel cycle

  10. Experiment of decontamination of radioactive liquid by a biological method; Experience de decontamination de liquides radioactifs far voie biologique

    Energy Technology Data Exchange (ETDEWEB)

    Wormser, G.

    1962-07-01

    The author reports experiments of treatment of radioactive liquid effluents by percolation on a bacterial bed like the one used for the treatment of sewer wastewaters. He also reports results obtained in other countries in terms of reduction of effluent radioactivity for various radioactive ions. The installation is described and results are presented in terms of variation of contamination of an effluent with respect to its recycling on a bacterial bed [French] Dans le monde entier, on se preoccupe des moyens de decontamination pour des liquides radioactifs. Les experiences de l'auteur ont confirme qu'un lit bacterien neuf peut donner de bons resultats: il est a noter que ce procede biologique se montre selectif a l'egard des divers ions radioactifs. (auteur)

  11. The conditioning of radioactive waste by bitumen; Conditionnement des dechets radioactifs par le bitume

    Energy Technology Data Exchange (ETDEWEB)

    Rodier, J; Scheidhauer, J; Malabre, M [Commissariat a l' Energie Atomique, Chusclan (France). Centre de Production de Plutonium de Marcoule

    1961-07-01

    The separation of radioactive sludge and waste by bitumen is studied. Results are given concerning various trials carried out on the lixiviation of the final product by water as a function of the pH, of the time, and of the composition. The conditions for carrying out this process of coating the waste are controlled from a radioactive point of view. (author) [French] L'isolement de boues radioactives et de dechets par le bitume est etudie. Les resultats de divers essais portant sur la lixiviation par l'eau du produit fini en fonction du pH, du temps et de la composition sont exposes. Les conditions de realisation de l'enrobage sont controlees au point de vue du risque radioactif. (auteur)

  12. Safety apparatus for serious radioactive accidents (1962); Materiel d'intervention en cas d'accident radioactif grave (1962)

    Energy Technology Data Exchange (ETDEWEB)

    Estournel, R; Rodier, J [Commissariat a l' Energie Atomique, Centre de Production de Plutonium, Marcoule (France). Centre d' Etudes Nucleaires

    1962-07-01

    In the case of a serious radioactive accident, radioactive dust and gases may be released into the atmosphere. It is therefore necessary to be able to evaluate rapidly the importance of the risk to the surrounding population, and to be able to ensure, even in the event of an evacuation of the Centre, the continuation of the radioactivity analyses and the decontamination of the personnel. For this, the Anti-radiation Protection Service at Marcoule has organised mobile detection teams and designed a mobile laboratory and a mobile shower-unit. After describing the duty of the mobile teams, the report gives a description of the apparatus which would be used at the Marcoule Centre in the case of a serious radioactive accident. The method of using this apparatus is given. (authors) [French] Lors d'un accident radioactif grave, des poussieres et des gaz radioactifs peuvent etre relaches dans l'atmosphere. II est alors indispensable d'evaluer rapidement l'importance du risque couru par les populations environnantes, et de pouvoir assurer, meme dans le cas de l'evacuation du Centre, la poursuite des analyses radioactives et la decontamination du personnel. Pour cela, le Service de Protection contre les Radiations du Centre de Marcoule a mis sur pied des equipes mobiles de detection et realise une semi-remorque laboratoire ainsi qu'une semi-remorque douches. Apres avoir defini la mission des equipes mobiles, le rapport donne la description du materiel d'intervention qui serait mis en oeuvre par le Centre de Marcoule dans le cas d'un accident radioactif grave. Il precis le mode d'utilisation de ce materiel. (auteurs)

  13. Analytical chemistry equipment for radioactive products; Installation de chimie analytique pour produits radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Douis, M; Guillon, A; Laurent, H; Sauvagnac, R [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1959-07-01

    The report deals with a shielded enclosure, hermetic, for analytical examination and handling of radioactive products. Remote handling for the following is provided: pipette absorption - weighing - centrifuging - desiccation - volumetric - pH measurement - potentiometric - colorimetric - polarographic. The above list is not restrictive: the enclosure is designed for the rapid installation of other equipment. Powerfully ventilated and screened to 400 m-curies long life fission product levels by 5 cm of lead, the enclosure is fully safe to the stated level. (author) [French] La presente communication decrit une enceinte etanche et blindee permettant un travail et un controle analytique sur des produits radioactifs. Les techniques suivantes sont adaptees pour une manipulation a distance: pipettage, pesees, centrifugation, dessiccation, volumetrie, mesure de pH, potentiometrie, colorimetrie, polarographie. Cette liste n'est pas limitative. La conception de l'installation permet la mise en place rapide d'autres appareils. Protegee par 5 cm de plomb et fortement ventilee, elle donne toute securite de manipulation jusqu'a un niveau d'activite 400 mcuries en produits de fission a vie longue. (auteur)

  14. Treatment and final conditioning of solid radioactive wastes; Traitement et conditionnement definitif des dechets radioactifs solides

    Energy Technology Data Exchange (ETDEWEB)

    Cerre, J [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1960-07-01

    The storage of solid radioactive wastes on a site is so cumbersome and dangerous that we have developed a method of treatment and conditioning by means of which the volume of waste is considerably reduced and very long-lasting shielding can be provided. This paper describes the techniques adopted at Saclay, where the wastes are sheared, compressed and enveloped in concrete of variable thickness. The main part of the report is devoted to a description of the corresponding remote handling installation. (author) [French] L'encombrement et le danger que presentent sur un site le stockage de dechets radioactifs solides nous ont amenes a etudier un mode de traitement et de conditionnement permettant une sensible reduction du volume des dechets et une protection de tres longue duree. La presente communication expose les techniques adoptees a Saclay ou les dechets sont cisailles, comprimes et enrobes dans du beton d'epaisseur variable. La description de l'installation telecommandee correspondante fait l'objet principal de cette communication. (auteur)

  15. Timescales of magma ascent and degassing and the role of crustal assimilation at Merapi volcano (2006-2010), Indonesia: Constraints from uranium-series and radiogenic isotopic compositions

    Science.gov (United States)

    Handley, H. K.; Reagan, M.; Gertisser, R.; Preece, K.; Berlo, K.; McGee, L. E.; Barclay, J.; Herd, R.

    2018-02-01

    We present new 238U-230Th-226Ra-210Pb-210Po, 87Sr/86Sr and 143Nd/144Nd isotopic data of whole-rock samples and plagioclase separates from volcanic deposits of the 2006 and 2010 eruptions at Merapi volcano, Java, Indonesia. These data are combined with available eruption monitoring, petrographic, mineralogical and Pb isotopic data to assess current theories on the cause of a recent transition from effusive dome-building (2006) to explosive (2010) activity at the volcano, as well as to further investigate the petrogenetic components involved in magma genesis and evolution. Despite the significant difference in eruption style, the 2006 and 2010 volcanic rocks show no significant difference in (238U/232Th), (230Th/232Th) and (226Ra/230Th) activity ratios, with all samples displaying U and Ra excesses. The 226Ra and 210Pb excesses observed in plagioclase separates from the 2006 and 2010 eruptions indicate that a proportion of the plagioclase grew within the decades preceding eruption. The 2006 and 2010 samples were depleted in 210Po relative to 210Pb ((210Po/210Pb)i monitoring parameters, 210Po ingrowth calculations suggest that initial intrusion into the shallow magma plumbing system occurred several weeks to a few months prior to the initial 2010 eruption. The 2006 and 2010 samples show a wide range in (210Pb/226Ra) activity ratio within a single eruption at Merapi and are largely characterised by 210Pb deficits ((210Pb/226Ra) monitoring data, previous petrological studies (mineral, microlite and melt inclusion work) and maximum calculated timescale estimates using Fe-Mg compositional gradients in clinopyroxene, that also suggest more rapid movement of relatively undegassed magma in 2010 relative to 2006.

  16. Storing and evacuation of solid radioactive waste (1960); Stockage et evacuation des dechets radioactifs solides (1960)

    Energy Technology Data Exchange (ETDEWEB)

    Pomarola, J [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1960-07-01

    The object of this paper is to present the plans under consideration for the final destination of solid radioactive wastes. 1) It is first of all necessary to provide in each centre an organised temporary storage dump. Several types of temporary dumps are suitable and can coexist in the same area; on the ground, in buildings; in basements. 2) Definitive storage. To accomplish a definitive storage arrangement it is necessary, as a function of the activity and the conditioning of the wastes, to define: - the site and the means of transport considered both inside and outside nuclear centres. The solution adopted depends on the above imperatives, and plans for definitive storage on the ground, under ground and in the sea are examined successively. Economic considerations play a large part in the decision reached. (author) [French] La presente communication a pour objet les solutions envisagees pour une destination finale des dechets radioactifs solide. 1) Il est tout d'abord necessaire de prevoir, dans chaque centre, un stockage provisoire organise. Plusieurs types de stockage previsoire peuvent convenir et coexister sur une meme aire; stockage sur le sol; stockage en batiment; stockage en sous-sol. 2) Stockage definitif. La realisation d'un stockage definitif rend necessaire, en fonction de l'activite et du conditionnement des dechets, la definition: - du site et des modes de transports envisages a l'interieur et a l'exterieur des Centres Nucleaires. Le choix des solutions decoule des imperatifs ci-dessus et on examine successivement le stockage definitif, - sur le sol; dans le sous-sol; en mer. Les considerations d'ordre economique constituent un facteur important dans le choix de la solution. (auteur)

  17. The treatment of effluents; Ameliorations apportees aux traitements des residus radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Wormser, G; Rodier, J; Robien, E de; Fernandez, N [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

    1964-07-01

    resins are used in the sodium form; the regeneration is carried out using a sodium salt solution which, after decontamination by coprecipitation is used again. With this process it is possible to use a smaller volume of sludge. 2 - The use of a natural evaporator. This process uses atmospheric air which is not saturated with water vapour and which is at a normal temperature, in order to extract water from the aqueous effluents. (authors) [French] Depuis plusieurs annees, le Commissariat a l'Eneregie Atomique Francais s'est penche avec interet sur les problemes poses par les effluents radioactifs. Les hautes activites n'ayant pas encore recu de solution definitive, nous nous bornerons a traiter, dans cette communication, que des realisations et des recherches relatives aux effluents faiblement et moyennement actifs. Dans le domaine des realisations, diverses stations de traitement ont ete construites en France; nous en ferons une breve enumeration, tout en faisant ressortir les nouveautes les plus importantes. C'est ainsi que nous presenterons plus specialement les dernieres stations de traitement mises en oeuvre (Grenoble, Fontenay-aux-Roses, Cadarache). De I'ensemble de ces realisations nouvelles, nous traiterons d'une maniere un peu plus approfondie, les trois sujets suivants: 1 - Atelier de conditionnement par bitumage des boues provenant de la concentration des radio-nucleides. 2 - Atelier de traitement des dechets solides radioactifs et combustibles par incineration. 3 - Ensemble de concentration effluents liquides radioactifs par evaporation. Dans le domaine de la recherche, de nombreuses voies ont ete abordees; nous en ferons I'inventaire. Il s'agit, dans la plupart des cas, de la concentration des radio-nucleides en vue d'un stockage pratique et peu onereux, concentration associee a une decontamination efficace, et Ie meilleur marche possible, des liquides aqueux, en vue de leur rejet. Pour l'amelioration des traitements aboutissant a la concentration des radio

  18. The treatment and conditioning of solid radioactive waste (1962); Le traitement et le conditionnement des dechets radioactifs solides (1982)

    Energy Technology Data Exchange (ETDEWEB)

    Cerre, P; Mestre, E [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1962-07-01

    Previous studies, the results of which have been confirmed by experiments, have led us to build a semi-industrial plant for the treatment and coating of solid radioactive waste. This report details the means at our disposal in a pilot plant which, apart from being used for tests, was also routine-operated. It is thus possible to give also an appreciation of its operation in this report. (authors) [French] Les etudes anterieures, dont les resultats ont ete confirmes par des essais, nous ont conduits a realiser une installation semi-industrielle de traitement et d'enrobage des dechets radioactifs solides. Le rapport a pour but de preciser les moyens mis a notre disposition dans une unite pilote qui, outre son role de banc d'essai, a pu etre exploitee en routine. C'est donc aussi un bilan de son exploitation qui est presente. (auteurs)

  19. Experimental study of contamination by inhalation of radioactive iodine aerosols. Biological balance; Etude experimentale de la contamination par inhalation d'aerosols d'iode radioactif bilan biologique

    Energy Technology Data Exchange (ETDEWEB)

    Marble, G [Commissariat a l' Energie Atomique, 92 - Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1968-07-01

    Several articles have been published concerning research into contamination produced by inhalation of radioactive iodine aerosols in monkeys. Results dealing with the biological balance of this contamination are presented and discussed in this report. (author) [French] L'etude experimentale de la contamination par inhalation d'aerosols d'iode radioactif effectuee chez le singe a fait l'objet de plusieurs publications. Les resultats concernant le bilan biologique de cette contamination sont presentes et discutes dans ce rapport. (auteur)

  20. Study of radio-active ions in the atmosphere; Etude des ions radioactifs de l'atmosphere

    Energy Technology Data Exchange (ETDEWEB)

    Renoux, A [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1965-01-01

    A comparative study is made of active, deposits of radon and thoron in suspension in the atmosphere by means of {alpha} radiation counting, using ZELENY tubes, scattering equipment, filter papers or membranes. It has been possible to show the existence of small and large ions which are negative and positive, as well as of neutral radio-active nuclei; their properties are studied. A theoretical interpretation of the results is presented. The average content of radon (using the Ra A concentration) and of Th B in the air has been determined. The radioactive equilibrium between radon and its daughter products in atmospheric air are examined. The techniques developed for active radon and thoron deposits are applied to the study of artificial radio-activity, the analyses being carried out by means of {gamma} spectrometry. (author) [French] On effectue une etude comparative entre les depots actifs du radon et du thoron en suspension dont l'atmosphere a l'aide de comptages de rayonnement {alpha}, en utilisant des tubes de ZELENY, une batterie de diffusion, des papiers filtres ou des membranes. On met ainsi en evidence la presence de petits et gros ions negatifs et positifs, ainsi que celle de noyaux neutres radioactifs, et on etudie leurs proprietes. Une Interpretation theorique des resultats obtenus est developpee. On determine la teneur moyenne de l'air en radon (a partir de la concentration en Ra A) et en Th B. L'equilibre radioactif entre le radon et ses descendants, dans l'air atmospherique, est examine. Les Techniques mises au point pour les depots actifs du radon et du thoron sont appliquees a l'etude de la radioactivite artificielle, les depouillements s'effectuant par spectrometrie {gamma}. (auteur)

  1. From chemical mapping to pressure temperature deformation micro-cartography: mineralogical evolution and mass transport in thermo-mechanic disequilibrium systems: application to meta-pelites and confinement nuclear waste materials; De l'imagerie chimique a la micro-cartographie Pression-Temperature-Deformation: evolution mineralogique et transport de matiere dans des systemes en desequilibre thermomecanique. Applications aux metapelites et aux materiaux de stockage de dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Andrade, V. de

    2006-03-15

    The mineralogical composition of metamorphic rocks or industrial materials evolves when they are submitted to thermomechanical disequilibria, i.e. a spatial or temporal pressure and temperature evolution, or chemical disequilibria as variations in redox conditions, pH... For example, during low temperature metamorphic processes, rocks re-equilibrate only partially, and thus record locally thermodynamic equilibria increasing so the spatial chemical heterogeneities. Understanding the P-T evolution of such systems and deciphering modalities of their mineralogical transformation imply to recognize and characterize the size of these local 'paleo-equilibria', and so to have a spatial chemical information at least in 2 dimensions. In order to get this information, microprobe X-ray fluorescence maps have been used. Computer codes have been developed with Matlab to quantify these maps in view of thermo-barometric estimations. In this way, P-T maps of mineral crystallisation were produced using the multi-equilibria thermodynamic technique. Applications on two meta-pelites from the Sambagawa blue-schist belt (Japan) and from the Caledonian eclogitic zone in Spitsbergen, show that quantitative chemical maps are a powerful tool to retrieve the metamorphic history of rocks. From these chemical maps have been derived maps of P-T-time-redox-deformation that allow to characterize P-T conditions of minerals formation, and so, the P-T path of the sample, the oxidation state of iron in the chlorite phase. As a result, we underline the relation between deformation and crystallisation, and propose a relative chronology of minerals crystallisation and deformations. The Fe{sup 3+} content map in chlorite calculated by thermodynamic has also been validated by a {mu}-XANES mapping at the iron K-edge measured at the ESRF (ID24) using an innovative method. Another application relates to an experimental study of clay materials, main components of an analogical model of a nuclear waste storage site. Chemical maps allowed to characterize the 2D mineralogical evolution of clays toward iron rich end-members. They have also been used as input data in a 2D finite element numerical model aiming to estimate the iron diffusion coefficient in clays at low temperatures, important parameter to model the destabilization of nuclear waste storage sites in the course of time. (author)

  2. Tracing of natural radionuclides mobility in deep sedimentary environment using radioactive ({sup 234}U/{sup 238}U) disequilibria: application to the Mesozoic formations of the Eastern part of the Paris Basin; Tracage de la mobilite des radionucleides naturels en milieu sedimentaire profond a l'aide des desequilibres radioactifs ({sup 234}U/{sup 238}U): application aux formations mesozoiques de l'est du Bassin de Paris

    Energy Technology Data Exchange (ETDEWEB)

    Deschamps, P

    2003-11-01

    This thesis forms part of the geological investigations undertaken by the French agency for nuclear waste management, ANDRA, around the Meuse/Haute-Marne Underground Research Laboratory (URL) located in the Eastern part of the Paris Basin in order to evaluate the feasibility of high-level radioactive waste repository in deep argilite formations. The aim of the study is to examine the radionuclide migration in the deep Callovo-Oxfordian target argilite layer and its surrounding low- permeability Bathonian and Oxfordian limestone formations in order to assess the long term confining capacities of the sedimentary series. This study is based on measurement of radioactive disequilibria within U-series by Multiple- Collector Inductively Coupled Plasma Mass Spectrometry (MC-ICP-MS). The high precision and accuracy achieved allowed to demonstrate the {sup 234}U/{sup 238}U radioactive equilibrium in the Callovo-Oxfordian argilites. This result shows the uranium immobility in the target formation and provides a strong evidence for the current chemical stability and closure of the system for uranium and most probably for the other actinides. This is a fundamental result with respect to the problematic of disposal of high level radioactive waste in deep geological formation since it provides a in situ indication of the confining capacities of the clayey target formation in the current settings. Conversely, ({sup 234}U/{sup 238}U) disequilibria are systematically observed within zones, located in the surrounding carbonate formations, that are characterized by pressure dissolution structures (stylolites or dissolution seams). These disequilibria provide evidence for a discrete uranium relocation during the last two million years in the vicinity of stylolitic structures. This is a surprising result since it is generally supposed that these deep, low permeability, compact formations behave as closed system at the time scale of the U-series. (author)

  3. Tracing of natural radionuclides mobility in deep sedimentary environment using radioactive ({sup 234}U/{sup 238}U) disequilibria: application to the Mesozoic formations of the Eastern part of the Paris Basin; Tracage de la mobilite des radionucleides naturels en milieu sedimentaire profond a l'aide des desequilibres radioactifs ({sup 234}U/{sup 238}U): application aux formations mesozoiques de l'est du Bassin de Paris

    Energy Technology Data Exchange (ETDEWEB)

    Deschamps, P

    2003-11-01

    This thesis forms part of the geological investigations undertaken by the French agency for nuclear waste management, ANDRA, around the Meuse/Haute-Marne Underground Research Laboratory (URL) located in the Eastern part of the Paris Basin in order to evaluate the feasibility of high-level radioactive waste repository in deep argilite formations. The aim of the study is to examine the radionuclide migration in the deep Callovo-Oxfordian target argilite layer and its surrounding low- permeability Bathonian and Oxfordian limestone formations in order to assess the long term confining capacities of the sedimentary series. This study is based on measurement of radioactive disequilibria within U-series by Multiple- Collector Inductively Coupled Plasma Mass Spectrometry (MC-ICP-MS). The high precision and accuracy achieved allowed to demonstrate the {sup 234}U/{sup 238}U radioactive equilibrium in the Callovo-Oxfordian argilites. This result shows the uranium immobility in the target formation and provides a strong evidence for the current chemical stability and closure of the system for uranium and most probably for the other actinides. This is a fundamental result with respect to the problematic of disposal of high level radioactive waste in deep geological formation since it provides a in situ indication of the confining capacities of the clayey target formation in the current settings. Conversely, ({sup 234}U/{sup 238}U) disequilibria are systematically observed within zones, located in the surrounding carbonate formations, that are characterized by pressure dissolution structures (stylolites or dissolution seams). These disequilibria provide evidence for a discrete uranium relocation during the last two million years in the vicinity of stylolitic structures. This is a surprising result since it is generally supposed that these deep, low permeability, compact formations behave as closed system at the time scale of the U-series. (author)

  4. Radioactive equilibrium of uranium-bearing ores in some problems of applied geology; Les equilibres radioactifs des menerais uraniferes dans quelques problemes de geologie appliquee

    Energy Technology Data Exchange (ETDEWEB)

    Coulomb, R; Girard, Ph; Goldsztein, M [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1964-07-01

    The state of equilibrium between several nuclides in radioactive relationship is determined with accuracy by the fundamental equations of radioactivity. It can be measured physically and expressed in suitable and internationally adopted units; Equilibrium - disequilibrium of uranium-bearing ores is a fairly complex phenomenon but the problem can be much simplified by well-chosen approximations in various practical field cases. The results of radiometric and radiochemical measurements lead to the interpretation of geochemical anomalies and may be used in the qualitative and quantitative estimation of uranium bearing deposits. (authors) [French] L'etat d'equilibre entre plusieurs radioelements en filiation se definit avec precision par les equations fondamentales de la radioactivite et peut etre determine par des mesures physiques dans des systemes d'unites commodes et internationalement adoptes. Le probleme general equilibre-desequilibre des minerais uraniferes est relativement complexe, mais peut se simplifier largement par des approximations judicieuses dans de nombreux cas particuliers rencontres concretement sur le terrain. Les resultats des mesures radiometriques et radiochimiques permettent l'interpretation des anomalies geochimiques et peuvent servir a l'estimation qualitative et quantitative des gisements de minerais uraniferes. (auteurs)

  5. Cadarache LOR (liquides organiques radioactifs) treatment by a solidification process using NOCHAR polymers

    International Nuclear Information System (INIS)

    Vaudey, Claire-Emilie; Renou, Sebastien; Kelley, Dennis; Cochaud, Chantal; Serrano, Roger

    2013-01-01

    In France, two options can be considered to handle the Very Low Level Waste (VLLW) and the Low Level Waste (LLW). The first one is the incineration at CENTRACO facility and the second one is the disposal at ANDRA sites. The waste acceptance in these two channels is dependent upon the adequacy between the waste characteristics (physical chemistry and radiological) and the channel specifications. If the waste characteristics and the channel specifications (presence of significant quantities of halogens, complexing agents, organic components... or/and high activity limits) are incompatible, an alternative solution have to be identify. It consists of a waste pre-treatment process. For Cadarache LOR (Liquides Organiques Radioactifs) waste streams, two radioactive scintillation cocktails have to be treated. They are composed of a mix of organic liquids and water: for the first one, 19 % of organic compounds (xylene, mesitylene, diphenyloxazole, TBP...) and 86.9 % of water, and for the second one, 23 % of organic compounds (TBP...) and 77 % of water. They contain halogens (chlorine and fluorine), complexants agents (nitrate, sulphate, oxalate and formate) and have got αβγ spectra with mass activities equal to some 100 Bq/g. Therefore, tritium is also present. As a consequence, in order for storage acceptance at the ANDRA site, it is necessary to pre-treat the waste. An adequate solution seems to be a solidification process using NOCHAR polymers. Indeed, NOCHAR polymers correspond to an important variety of products applied to the treatment of radioactive aqueous and organic liquids (solvent, oil, solvent/oil mixing ...) and sludge through a mechanical and chemical solidification process. For Cadarache LOR, N910 and N960 respectively dedicated to the organic and aqueous liquids solidification are considered. With the N910, the organic waste solidification occurs in two steps. As the organic liquid travels moves through the polymer strands, the strands swell and

  6. NOCHAR Polymers: An Aqueous and Organic Liquid Solidification Process for Cadarache LOR (Liquides Organiques Radioactifs) - 13195

    International Nuclear Information System (INIS)

    Vaudey, Claire-Emilie; Renou, Sebastien; Porco, Julien; Kelley, Dennis; Cochaud, Chantal; Serrano, Roger

    2013-01-01

    To handle the Very Low Level Waste (VLLW) and the Low Level Waste (LLW) in France, two options can be considered: the incineration at CENTRACO facility and the disposal facility on ANDRA sites. The waste acceptance in these radwaste routes is dependent upon the adequacy between the waste characteristics (physical chemistry and radiological) and the radwaste route specifications. If the waste characteristics are incompatible with the radwaste route specifications (presence of significant quantities of chlorine, fluorine, organic component etc or/and high activity limits), it is necessary to find an alternative solution that consists of a waste pre-treatment process. In the context of the problematic Cadarache LOR (Liquides Organiques Radioactifs) waste streams, two radioactive scintillation cocktails have to be treated. The first one is composed of organic liquids at 13.1 % (diphenyloxazol, mesitylene, TBP, xylene) and water at 86.9 %. The second one is composed of TBP at 8.6 % and water at 91.4 %. They contain chlorine, fluorine and sulphate and have got alpha/beta/gamma spectra with mass activities equal to some kBq.g -1 . Therefore, tritium is present and creates the second problematic waste stream. As a consequence, in order for disposal acceptance at the ANDRA site, it is necessary to pre-treat the waste. The NOCHAR polymers as an aqueous and organic liquid solidification process seem to be an adequate solution. Indeed, these polymers constitute an important variety of products applied to the treatment of radioactive aqueous and organic liquids (solvent, oil, solvent/oil mixing etc) and sludge through a mechanical and chemical solidification process. For Cadarache LOR, N910 and N960 respectively dedicated to the organic and aqueous liquids solidification are considered. With the N910, the organic waste solidification occurs in two steps. As the organic liquid travels moves through the polymer strands, the strands swell and immobilise the liquid. Then as the

  7. A new class of medicament: radioactivity isotopes (1962); Une nouvelle classe de medicaments: les isotopes radioactifs (1962)

    Energy Technology Data Exchange (ETDEWEB)

    Cohen, Y. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1962-07-01

    Very many radioelement are used in medicine, either for diagnosis or as therapeutics. The development of medicine has entailed an increase in the number of application of radioactive isotopes. Firstly used in the form of simple inorganic molecules for diagnosis or as anticancer therapeutics, radioelements are now used for labelling organic molecules, allowing functional specific studies of any kind of nature. Their production is made difficult by their radio-active properties. Their pharmaceutical properties, determined by tests and controls, depend either from radiochemistry and from medicine. The author reminds, in this report, the methods for the preparation and analysis, and set out the medical application. (author) [French] De tres nombreux radioelements trouvent une application en medecine humaine, soit dans le diagnostic, soit en therapeutique. L'evolution de la medecine entraine un accroissement du champ d'application des isotopes radioactifs. D'abord utilises sous forme de molecules minerales simples, pour les diagnostics ou des therapeutiques anticancereuses, les radioelements sont maintenant introduits dans des molecules organiques qui permettent des etudes fonctionnelles specifiques de toute nature. Leur fabrication est compliquee par leurs proprietes radioactives. Leurs caracteristiques pharmaceutiques determinees par des essais et controles, sont liees d'une part a la radiochimie, d'autre part a la medecine. L'auteur rappelle, dans cet expose, les methodes de preparation et d'analyse et aborde les applications medicales. (auteur)

  8. A new class of medicament: radioactivity isotopes (1962); Une nouvelle classe de medicaments: les isotopes radioactifs (1962)

    Energy Technology Data Exchange (ETDEWEB)

    Cohen, Y [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1962-07-01

    Very many radioelement are used in medicine, either for diagnosis or as therapeutics. The development of medicine has entailed an increase in the number of application of radioactive isotopes. Firstly used in the form of simple inorganic molecules for diagnosis or as anticancer therapeutics, radioelements are now used for labelling organic molecules, allowing functional specific studies of any kind of nature. Their production is made difficult by their radio-active properties. Their pharmaceutical properties, determined by tests and controls, depend either from radiochemistry and from medicine. The author reminds, in this report, the methods for the preparation and analysis, and set out the medical application. (author) [French] De tres nombreux radioelements trouvent une application en medecine humaine, soit dans le diagnostic, soit en therapeutique. L'evolution de la medecine entraine un accroissement du champ d'application des isotopes radioactifs. D'abord utilises sous forme de molecules minerales simples, pour les diagnostics ou des therapeutiques anticancereuses, les radioelements sont maintenant introduits dans des molecules organiques qui permettent des etudes fonctionnelles specifiques de toute nature. Leur fabrication est compliquee par leurs proprietes radioactives. Leurs caracteristiques pharmaceutiques determinees par des essais et controles, sont liees d'une part a la radiochimie, d'autre part a la medecine. L'auteur rappelle, dans cet expose, les methodes de preparation et d'analyse et aborde les applications medicales. (auteur)

  9. Elimination of slightly radioactive liquid effluent by dilution. Its consequences (1960); Elimination par dilution d'effluents liquides faiblement radioactifs. Leurs consequences (1960)

    Energy Technology Data Exchange (ETDEWEB)

    Bovard, P; Candillon, C [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1960-07-01

    Nuclear centres often have to solve problems raised by the elimination of large volumes of slightly radioactive liquid effluent. As things stand at present, the method usually adopted consists in expelling this effluent into the main water system in order to dilute it to a maximum, and thus to lower its radioactive isotope concentration to below the norms imposed by the Public Health Service. This technique requires systematic checking of the water system and its dependences, and demands a thorough knowledge of adsorption and fixation processes. (author) [French] Les centres nucleaires ont frequemment a resoudre des problemes poses par l'elimination de volumes importants d'effluents liquides faiblement radioactifs. Dans l'etat actuel des choses, la solution la plus utilisee consiste a rejeter ces effluents dans le reseau hydrographique de maniere a les diluer au maximum et abaisser ainsi leurs teneurs en isotopes radioactifs au-dessous des normes imposees par la Sante Publique. Cette technique necessite un controle systematique du reseau et de ses dependances et demande une connaissance approfondie des processus d'adsorption et de fixation. (auteur)

  10. Determination of the concentration of {alpha} emitting radioactive aerosols; Mesure de la concentration des aerosols radioactifs emetteurs {alpha}

    Energy Technology Data Exchange (ETDEWEB)

    Labeyrie, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1953-06-15

    In the first part of this work the techniques used for the quantitative measurement of the concentrations of aerosols carrying short lived (radon or thoron daughters) or long lived (uranium) {alpha} radioactive emitters are described. In the second part the author investigates the problem of the determination of radon concentration in air by means of activity determinations on airborne dusts. Special reference is made to the measurement of the radon active deposit on two types of dusts (iron oxide (yellow) and uranium oxide) in small chambers (6 liters). In the third part are given data resulting from determinations of radon and thoron concentrations in atmospheric air in the south of Paris area using this method. (author) [French] Dans la premiere partie de ce travail on expose les techniques utilisees pour la mesure quantitative des concentrations d'aerosols contenant des emetteurs radioactifs {alpha}, tant pour ceux a vie courte (derives du radon ou du thoron) que pour ceux a vie longue (uranium). Dans la seconde partie on traite le probleme de la determination de la concentration de l'air en radon par la mesure de l'activite des poussieres ayant sejourne dans cet air. En particulier, on indique pour de petits volumes (6 litres) la proportion de depot actif du radon qui est fixee sur deux types de poussieres (limonite et oxyde d'uranium) en fonction de la concentration de celles-ci. Dans la troisieme partie on donne quelques exemples de mesure par cette methode de la concentration en radon et en thoron de l'atmosphere de la region parisienne. (auteur)

  11. Territory of Upper Volta. Interest and Programme of Prospecting for Radioactive Metals; Territoire de la Haute-Volta. Interet et Programme d'une Prospection pour Metaux Radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1958-04-15

    The costs of a programme for prospecting for radioactive metals (esp. Uranium) can amount to a total cost of the order of 600 to 700 millions FF over 10 years. Such a programme represents a rather high risk, because in order to succeed, a reserve capable to pay for the programme must be found in the foreseen period. The first part of the report describes the Uranium reserves already known in Africa. [French] Un programme de prospection pour metaux radioactifs (notamment l'Uranium) pourrait etaler des depenses totales de l'ordre de 600 a 700 millions FF sur 10 ans. Un tel programme represente un risque assez grand, puisque pour reussir, il faut trouver dans le delai envisage, et avec les moyens prevus, un gisement capable d'amortir une telle depense. Une premiere partie du rapport expose les caracteres des gisments d'Uranium actuellement connus en Afrique.

  12. Beach sediments drift study by means of radioactive tracers; L'etude du transport littoral par la methode des traceurs radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Hours, R [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires; Jaffry, P [Electricite de France (EDF), 78 - Chatou (France). Lab. National d' Hydraulique

    1959-07-01

    The present state of the sediments drift studies by means of radioactive tracers is exposed. Various processes of labelling, immersion and detection, used in France and other countries, are reviewed. A more extended analysis of some aspects of the problem by the same authors can be found in 'La Houille Blanche', number 3, may-june 1959 (Rapport C.E.A. number 1269). (author) [French] L'etude du transport littoral des sediments et galets par la methode des traceurs radioactifs est en plein developpement. Le present rapport precise l'etat actuel de la question. Les techniques de marquage, d'immersion et de detection utilisees en France et a l'etranger sont decrites; une analyse plus detaillee de certains aspects de la question est presentee par les memes auteurs dans 'La Houille Blanche', numero 3, mai-juin 1959 (Rapport C.E.A. numero 1269). (auteur)

  13. Determination of mineral radioactive strontium-{sup 90} in urines; Recherche du strontium mineral radioactif {sup 90}Sr dans les urines

    Energy Technology Data Exchange (ETDEWEB)

    Jeanmaire, L; Jammet, H; Bertrand, S [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1959-07-01

    An analytical procedure for radioactive strontium in urine is described. As a first step, a precipitation of calcium oxalate performed on the urine, allows to detect the presence of various fission products and particularly of strontium which is carried by the precipitate. Strontium can then be selectively separated on ion exchange resins. By studying the growth curve of {beta} activity, it is possible to determine the activities which may be attributed to {sup 89}Sr and {sup 90}Sr respectively. (author) [French] Cet article decrit une technique de dosage du strontium radioactif dans les urines. Dans un premier stade, une precipitation d'oxalate de calcium effectuee sur l'urine permet de deceler la presence de differents produits de fission et en particulier du strontium qui est entraine sur ce precipite. Il est possible ensuite de separer selectivement le strontium au moyen de resines echangeuses d'ions. L'examen de le courbe de croissance de l'activite {beta} permet de determiner les activites dues respectivement a {sup 89}Sr et {sup 90}Sr. (auteur)

  14. Collection and processing of information in biological kinetics studies with radioactive tracers; Collecte et traitement de l'information dans les etudes de cinetique biologique avec traceurs radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Remy, J; Lafuma, J [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1968-07-01

    The authors present an automatic method for the collection and treatment of information in biological kinetics experiments using radioactive tracers. The recording are made without any time constant on magnetic tape. The information recorded is sampled by a 400 channel multi-scale analyzer and transferred to punched cards. The digital analysis is done by an I.B.M. computer. The method is illustrated by an example: the hepatic fixation of colloidal gold in the pig. Its advantages and requirements are discussed. In the appendix are given the FORTRAN texts for two programmes used in treating the example presented. (authors) [French] Les auteurs presentent une methode automatique de collecte et de traitement de l'information dans les experiences de cinetique biologique utilisant les traceurs radioactifs. Les enregistrements sont realises sans constante de temps sur bande magnetique. L'information enregistree fait l'objet d'un echantillonnage a l'aide d'un analyseur a 400 canaux en mode multi-echelle puis est transferee sur cartes perforees. L'exploitation digitale est confiee a un ordinateur I.B.M.. La methode est illustree par un exemple d'etude de la fixation hepatique de l'or colloidal chez le porc. Ses avantages et ses exigences sont discutes. En annexe figurent les textes en FORTRAN de deux programmes utilises pour le traitement de l'exemple cite. (auteurs)

  15. Code of Practice on the International Transboundary Movement of Radioactive Waste; Code De Bonne Pratique Sur Le Mouvement Transfrontiere International De Dechets Radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1990-11-03

    On 21 September 1990, the General Conference, by resolution GC(XXXIV)/RES/530, adopted a Code of Practice on the International Transboundary Movement of Radioactive Waste and requested the Director General - inter alia - to take all necessary steps to ensure wide dissemination of the Code of Practice at both the national and the international level. The Code of Practice was elaborated by a Group of Experts established pursuant to resolution GC(XXXII)/RES/490 adopted by the General Conference in 1988. The text of the Code of Practice is reproduced herewith for the information of all Member States [French] Le 21 septembre 1990, la Conference generale, par la resolution GC(XXXIV)/RES/530, a adopte le Code de bonne pratique sur le mouvement transfrontiere international de dechets radioactifs et a prie le Directeur general-notamment-de prendre toutes les mesures necessaires pour assurer une large diffusion du Code de bonne pratique aux niveaux tant national qu'international. Le Code de bonne pratique a ete elabore par un groupe d'experts cree en application de la resolution GC(XXXII)/RES/490 adoptee par la Conference generale en 1988. Le texte du Code de bonne pratique est reproduit ci-apres pour l'information de tous les Etats Membres.

  16. Experimental study of contamination by inhalation of radioactive iodine aerosols. Biological balance; Etude experimentale de la contamination par inhalation d'aerosols d'iode radioactif bilan biologique

    Energy Technology Data Exchange (ETDEWEB)

    Marble, G. [Commissariat a l' Energie Atomique, 92 - Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1968-07-01

    Several articles have been published concerning research into contamination produced by inhalation of radioactive iodine aerosols in monkeys. Results dealing with the biological balance of this contamination are presented and discussed in this report. (author) [French] L'etude experimentale de la contamination par inhalation d'aerosols d'iode radioactif effectuee chez le singe a fait l'objet de plusieurs publications. Les resultats concernant le bilan biologique de cette contamination sont presentes et discutes dans ce rapport. (auteur)

  17. Treatment and Processing of Radioactive Wastes; Traitement des Dechets Radioactifs; 041e 0411 0420 0414 ; Tratamiento de Desechos Radiactivos

    Energy Technology Data Exchange (ETDEWEB)

    Rodger, Walton A. [Chemical Engineering Division, Argonne National Laboratory, Lemont, IL (United States)

    1960-07-01

    'auteur decrit des installations type. On a envisage la possibilite d'incinerer les dechets combustibles et l'auteur decrit cette methode en precisant les modalites d'application. La mise en paquets peut souvent completer utilement la collecte des dechets. L'auteur etudie un certain nombre de procedes pour les dechets liquides. Il decrit egalement des systemes type en expliquant leur fonctionnement. Dechets de haute radioactivite - Les gaz sont parfois decharges directement dans des cheminees, mais le plus souvent on leur fait subir certains traitements. On peut, soit les epurer par des processus chimiques, retirer l'iode par reaction avec l'argent, extraire les gaz rares ou encore recourir au filtrage. Les solides fortement contamines peuvent necessiter une decontamination sur place avant la collecte. Les dechets liquides fortement radioactifs constituent a l'heure actuelle la plus forte proportion de dechets a eliminer par l'industrie. On a cherche a resoudre le probleme en reduisant le volume des dechets produits en changeant le processus ; on peut aussi concentrer les dechets produits ou bien les reduire sous forme solide - plusieurs methodes sont employees a cet effet, notamment la concentration, l'utilisation de ciment de Portland, l'adsorption sur argile ou autre materiau naturel et la calcination. L'auteur examine les problemes techniques et economiques qui se posent a propos de l'entreposage provisoire. Il peut etre necessaire de ne traiter les dechets qu'en un petit nombre d'endroits soigneusement determines. L'auteur a calcule approximativement les quantites et le materiel necessaire au deplacement. Il etudie egalement les risques afferents et les incidences financieres. (author) [Spanish] El autor examina algunos de los metodos que se han propuesto para tratar los desechos radiactivos de baja y elevada actividad. Desechos de baja actividad - Una vez diluidos, los gases se descargan en la atmosfera mediante chimeneas o se hacen pasar por filtros de elevado poder de

  18. Study of filterable materials and protection instruments by the use of radioactive aerosols; Etude de materiaux filtrants et d'appareils de protection a l'aide des aerosols radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Billard,; Chevalier,; Pradel, [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1960-07-01

    Many filtration problems can be studied by means of radioactive aerosols. For the investigations described in this paper we have chosen the solid disintegration products of radon, the radioactive gas formed from radium, because of the facilities of generation and measurement it offers. Radon and its daughters are in fact always present in the atmosphere in sufficient concentration for certain tests. In order to improve the sensitivity of the measurements, radon from uranium ore can be used. The technique of measuring by counting {alpha} particles is rapid and easy to employ. We have thus been able to define a test for filterable substances, and to check filtering installation and individual protection instruments. (author) [French] Les aerosols radioactifs permettent d'etudier de nombreux problemes de filtration. Pour les etudes decrites dans ce document, nous avons choisi les produits solides de desintegration du radon, gaz radioactif forme a partir du radium en raison des facilites de generation et de mesure. Le radon et ses descendants sont, en effet, toujours presents dans l'atmosphere en concentration suffisante pour certains essais. Pour ameliorer la sensibilite des mesures, il suffit d'utiliser le radon provenant de minerai d'uranium. La technique de mesure par comptage des particules {alpha} est rapide et facile a mettre en oeuvre. Nous avons pu ainsi definir un test pour les substances filtrantes et controler les installations de filtration et des appareils de protection individuelle. (auteur)

  19. Some examples of the use of radioactive tracers in pharmacodynamic; Quelques exemples de l'emploi des traceurs radioactifs en pharmacodynamie

    Energy Technology Data Exchange (ETDEWEB)

    Cohen, Y [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1960-07-01

    The study of absorption, of distribution in the organism and of the elimination of a medicament has been greatly facilitated by the development of nuclear applications. In effect, the introduction into the molecule of one or several radioactive atoms makes it possible to follow the path and destination of minute quantities of the drug and to thus carry out analyses on the animal within limits of posology close to those of therapeutics. However the qualitative or quantitative methods used have certain limits and they must be compared amongst themselves and with others. Some examples will show : - the importance of the way of administering the drug on the changes in the distribution; - the quite relative selectivity of this latter; - and lastly, the different process involved in the elimination mechanisms. (author) [French] L'etude de l'absorption, de la repartition dans l'organisme et de l'elimination d'un medicament s'est trouvee grandement facilitee par le developpement des applications nucleaires. En effet, l'introduction dans une molecule d'un ou plusieurs atomes radioactifs permet de suivre le sort de quantites infimes de la drogue et de ce fait d'en effectuer l'analyse chez l'animal dans des limites de posologie se rapprochant de celles de la therapeutique. Cependant les methodes employees, qualitatives ou quantitatives, presentent des limites et doivent etre confrontees entre elles et avec d'autres methodes. Quelques exemples mettront en evidence: - l'importance du mode d'administration sur l'evolution de la repartition, - l'electivite toute relative de cette derniere, - et enfin, les modalites diverses des mecanismes d'elimination. (auteur)

  20. Review of the incineration of 500 tonnes of radio-active residues; Bilan de l'incineration de 500 tonnes de residus radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Rodier, J; Seyfried, P; Charbonneaux, M [Commissariat a l' Energie Atomique, Chusclan (France). Centre de Production de Plutonium de Marcoule

    1969-07-01

    During its first five years operation, the incinerator at the Marcoule Centre has burnt almost 500 tonnes of radio-active residues. Improvements in some of the details of the process have been made during this period; they concern the nature of the materials involved. The technical and radiological results for the installation are very favorable, and have made it possible to maintain a high charge factor.Although the overall economic results are not advantageous in the case of ungraded solid residues this method represents nevertheless the best available for eliminating oils, solvents, wood and dead animals. It can also be of use furthermore each time that a dilution in the atmosphere can advantageously be used as a method of disposing of certain radio elements such as tritium or carbon 14 in the form of gases or vapours. (author) [French] L'incinerateur du Centre de Marcoule a brule, durant les 5 premieres annees de fonctionnement, pres de 500 tonnes de residus radioactifs. Les ameliorations de detail realisees au cours de cette periode ont porte sur la nature des materiaux employes. Les bilans techniques et radiologiques de l'installation sont tres favorables et ont permis de maintenir un facteur de charge eleve. Si le bilan economique n'est pas favorable a l'incineration des residus solides 'tout venant' cette methode constitue cependant la solution ideale pour l'elimination des huiles, des solvants, du bois et des cadavres d'animaux. En outre, elle peut etre interessante chaque fois que la dilution dans l'atmosphere peut etre avantageusement mise a profit pour rejeter certains radioelements tels que le tritium ou le carbone 14 sous forme de gaz ou de vapeurs. (auteur)

  1. Results of concentration measurements of artificial radioactive aerosols in the lower atmosphere; Resultats des mesures de concentration, dans la basse atmosphere, des aerosols radioactifs artificiels

    Energy Technology Data Exchange (ETDEWEB)

    Ardouin, B; Jehanno, C; Labeyrie, J; Lambert, G; Tanaevsky, O; Vassy, E [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1963-07-01

    This report gives the results of the measurements of artificial gross-{beta}-radioactivity in aerosols in the lower atmosphere; these measurements have been made by the Electronic Physics Service of the Electronic Department, and by the Atmospheric Physics Laboratory of the Paris Science Faculty. The measurements were begun in September 1956 and were continued in an increasing number of stations both in France and in the rest of the world. The present report deals with the period up to the end of august 1961, that is up to the end of the nuclear moratorium. After recalling the constitution and the properties of radioactive aerosols present in the atmosphere, the authors describe the measurement methods, estimate their accuracy and discuss various aspects of the results. (authors) [French] Ce rapport contient les resultats des mesures de radioactivite {beta} globale d'origine artificielle des aerosols dans la basse atmosphere, effectuees conjointement par le Service d'Electronique Physique du Departement d'Electronique et le Laboratoire de Physique de l'Atmosphere de la Faculte des Sciences de Paris. Les mesures ont commence en septembre 1956 et ont ete poursuivies dans un nombre croissant de stations, tant en France que dans le reste du monde. Le present rapport s'arrete a la fin aout 1961, c'est-a-dire au moment de la reprise des essais nucleaires. Apres avoir rappele la constitution et les proprietes des aerosols radioactifs presents dans l'atmosphere, les auteurs indiquent les methodes de mesure utilisees, evaluent leur precision et discutent les differents aspects des resultats de leurs mesures. (auteurs)

  2. Kinetic ion exchange studies in ultramarines by the radioactive tracer method; Etudes cinetiques d'echanges d'ions dans les outremers par la technique des traceurs radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    May, S; Goenvec, H; Pinte, G [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1960-07-01

    The possibility of ion exchanges in various ultramarines has been studied in the aqueous phase. The kinetics of the exchange reactions is followed by studying the behaviour of a radioactive ion, either in the solution of the exchanging salt or in the ultramarine itself. The sodium in the make-up of the ultramarine, is found to exchange with various ions in solution. The reaction speeds appear to be governed by a diffusion process inside the grains of ultramarine. The diffusion coefficients and the activation energies are determined for the exchanges studied. Several exchange studies were carried out in an organic medium. The kinetics of ion exchange is also investigated in ultramarines from which most of the constituent sulphur has been eliminated. The results obtained in these ultramarines are compared with the exchange kinetics of the same ions in ordinary ultramarine. (author) [French] Nous avons etudie la possibilite d'echanges ioniques dans differents outremers, en phase aqueuse. L'etude cinetique des reactions d'echanges est suivie en etudiant le comportement d'ion radioactif, soit dans la solution du sel echangeant, soit dans l'outremer lui-meme. C'est le sodium de constitution de l'outremer qui s'echange avec differents ions en solution. Les vitesses de reactions semblent etre controlees par un processus de diffusion a l'interieur des grains d'outremer. Les coefficients de diffusion et les energies d'activation sont determines pour les echanges etudies. Quelques etudes sont realisees en milieu organique ou quelques echanges ont ete etudies. La cinetique d'echange d'ions est egalement etudie dans des outremers dans lesquels la majorite du soufre de constitution a ete eliminee. On compare les resultats obtenus dans ces outremers avec les cinetiques d'echanges des memes ions dans l'outremer ordinaire. (auteur)

  3. Processing radioactive effluents with ion-exchanging resins: study of result extrapolation; Traitement des effluents radioactifs par resines echangeuses d'ions: etude de l'extrapolation des resultats

    Energy Technology Data Exchange (ETDEWEB)

    Wormser, G.

    1960-05-03

    As a previous study showed the ion-exchanging resins could be used in Saclay for the treatment of radioactive effluents, the author reports a study which aimed at investigating to which extent thus obtained results could be extrapolated to the case of higher industrial columns. The author reports experiments which aimed at determining extrapolation modes which could be used for columns of organic resin used for radioactive effluent decontamination. He notably studied whether the Hiester and Vermeulen extrapolation law could be applied. Experiments are performed at constant percolation flow rate, at varying flow rate, and at constant flow rate [French] Plusieurs etudes ont ete faites dans le but d'examiner les possibilites d'emploi des resines echangeuses d'ions pour le traitement des effluents radioactifs. Dans un rapport preliminaire, nous avons montre dans quelles limites un tel procede pouvait etre utilise au Centre d'Etudes Nucleaires de Saclay. Les essais ont ete effectues sur des petites colonnes de resine au laboratoire; il est apparu ensuite necessaire de prevoir dans quelle mesure les resultats ainsi obtenus peuvent etre extrapoles a des colonnes industrielles, de plus grande hauteur. Les experiences dont les resultats sont exposes dans ce rapport, ont pour but de determiner les modes d'extrapolation qui pourraient etre employes pour des colonnes de resine organique utilisees pour la decontamination d'effluents radioactifs. Nous avons en particulier recherche si la loi d'extrapolation de Hiester et Vermeulen qui donne de bons resultats dans le cas de fixation d'ions radioactifs en presence d'un ion macrocomposant sur des terres, pouvait etre appliquee. Les experiences, en nombre limite, ont montre que la loi d'extrapolation de Hiester et Vermeulen pouvait s'appliquer dans le cas de l'effluent considere quand les debits de percolation sont tres faibles; quand ils sont plus forts, les volumes de liquide percoles, a fixation egale, sont proportionnels aux

  4. Origin, Nature, Disposal and Control of Radioactive Wastes Arising from the Use of Radioisotopes; Origine, Nature, Elimination et Controle des Dechets Radioactifs Decoulant de l'Emploi des Radioisotopes; 041f 0420 041e 0414 ; Origen, Naturaleza, Evacuacion y Control de los Desechos Radiactivos Producidos en la Utilizacion de Radioisotopos

    Energy Technology Data Exchange (ETDEWEB)

    Kenny, A. W. [Ministry of Housing and Local Government (United Kingdom)

    1960-07-01

    The paper describes the different types of radioactive waste arising from industrial, medical and scientific uses of radioisotopes. An outline is given of methods used for waste disposal, depending on the content of radioactivity. (author) [French] L'auteur decrit les differents types de dechets radioactifs decoulant de l'utilisation de radioisotopes dans l'industrie, en medecine et dans la science. Il donne un apercu des methodes employees pour l'elimination des dechets selon leur teneur en elements radioactifs. (author) [Spanish] En la memoria se describen los diferentes tipos de desechos radiactivos producidos por la utilizacion industrial, medica y cientifica de los radioisotopos y se hace una exposicion de los metodos empleados para la evacuacion de desechos segun su contenido radiactivo. (author) [Russian] V doklade daetsja opisanie razlichnyh tipov radioaktivnyh othodov, voznikajushhih v rezul'tate promyshlennogo, medicinskogo i nauchnogo ispol'zovanija radioizotopov. Osobo razbirajutsja metody, ispol'zuemye dlja udalenija radioaktivnyh othodov v zavisimosti ot ih radioaktivnosti. (author)

  5. Determination of radioactive risks connected with the working of a nuclear plant; Evaluation des risques radioactifs lies au fonctionnement d'une installation nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Lavie, J M; Doury, A [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1960-07-01

    Numerous problems which are posed by the evaluation of the radioactive risks linked to the working of a nuclear plant are new problems which have not yet been satisfactorily solved. In these conditions this study must be considered only as a preliminary approach whose essential aims are the following: - development and synthesis of the existing data; - rapid determination of conservative and usable orders of greatness for the security factors, both for normal working and in the case of an accident. The most probable typical accidents are reviewed together with the nature of the resulting risks and the principal factors on which these risks depend. Among these factors, one of the most important is atmospheric diffusion which is studied in some detail using the analytic model due to Sutton. A logical graphical presentation increasing the flexibility in the use of the results and presents the responsible authorities with a flexible, practical and rapid means of evaluating the risks involved starting from a sufficiently general system of initial and simultaneously valid conditions (types of accident, atmospheric conditions). (author) [French] De nombreux problemes souleves par l'evaluation des risques radioactifs lies au fonctionnement d'une installation nucleaire sont des problemes nouveaux qui n'ont pas encore recu de solution satisfaisante. Dans ces conditions cette etude ne doit etre consideree que comme une premiere approche dont les objectifs essentiels sont les suivants: - mise au point et synthese de donnees existantes; - determination rapide d'ordres de grandeur conservatifs et utilisables de valeurs de securite, tant en fonctionnement normal qu'en cas d'accident. Les accidents types les plus probables sont passes en revue ainsi que la nature des risques qui en decoulent et les principaux facteurs dont dependent ces risques. Parmi ces facteurs, l'un des plus importants est la diffusion atmospherique qui fait l'objet d'une etude particuliere a l'aide du modele

  6. Usefulness of the decay rate in the management of radioactive waste stocks; De l'interet de la decroissance pour la gestion des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Rodier, J; Cohendy, G [Commissariat a l' Energie Atomique, Chusclan (France). Centre de Production de Plutonium de Marcoule

    1969-07-01

    It became apparent, during first few years operation of the Marcoule Centre, that it was very useful to exploit the natural decay rate of the radioactive element contaminating the waste. The storage of this waste under the best possible conditions in each case, was first of all favorable for the radiological safety point of view; it led, furthermore, to a marked reduction in the cost price since it made it possible to avoid employing protection means which would have proved to be excessively outsize after a few years. Finally, even when the half-life of the radioelements involved seemed to annul any possible advantages of this method, the temporary storage made it possible to develop treatment processes which were unknown at the time. The overall result of this policy is that at the present time over 98 per cent of the solid waste produced by the Marcoule Centre has been processed in such a way that it can, at any moment, be discharged from the site without difficulty. (authors) [French] Des les premieres annees de fonctionnement du Centre de Marcoule, il est apparu qu'il etait extremement benefique de mettre a profit la decroissance naturelle des elements radioactifs contaminant les dechets. Le stockage de ces dechets dans des conditions appropriees a chaque cas d'espece a tout d'abord ete favorable a la surete radiologique; en outre, il a abouti a une reduction sensible des prix de revient, du fait qu'il a evite de mettre en oeuvre des moyens de protection qui se seraient reveles surdimensionnes au bout de quelques annees. Enfin, meme lorsque la periode des radioelements en cause semblait enlever tout interet a cette methode, le stockage d'attente a permis de mettre au point des procedes de traitement inconnus a l'epoque. Le resultat global de cette politique est que, actuellement, plus de 98 pour cent des dechets solides produits depuis l'origine du Centre de Marcoule ont ete conditionnes de telle sorte qu'ils peuvent, a tout moment, etre evacues hors du Site

  7. Storage and Disposal of Solid Radioactive Waste; Stockage et Evacuation des Dechets Radioactifs Solides; 0425 0420 0414 ; Almacenamiento y Evacuacion de Desechos Radiactivos Solidos

    Energy Technology Data Exchange (ETDEWEB)

    Pomarola, J. [Chef du Bureau Technique, Service de Controle des Radiations et de Genie Radioactif, Commissariat a l' Energie Atomique, Saclay (France)

    1960-07-01

    This paper deals with solutions for the problem of final disposal of solid radioactive waste. I. It is first essential to organize a proper system of temporary storage. II. Final Storage In order to organize final storage, it is necessary to fix, according to the activity and form of the waste, the site and the modes of transport to be used within and outside the nuclear centre. The choice of solutions follows from the foregoing essentials. The paper then considers, in turn, final storage, on the ground, in the sub-soil and in the sea. Economic considerations are an important factor in determining the choice of solution. (author) [French] La presente communication a pour objet les solutions envisagees pour une destination finale des dechets radioactifs solides. I - Il est tout d'abord necessaire de prevoir un stockage provisoire organise. II - Stockage definitif: La realisation d'un stockage definitif rend necessaire, en fonction de l'activite et du conditionnement des dechets, la definition: - du site et des modes de transports envisages a l'interieur et a l'exterieur des Centres Nucleaires. Le choix des solutions decoule des imperatifs ci-dessus et on examine successivement le stockage definitif: - sur le sol, - dans le sous-sol, - en mer. Les considerations d'ordre economique constituent un facteur important dans le choix de la solution. (author) [Spanish] El autor de la memoria estudia las diferentes soluciones previstas para la evacuacion definitiva de los desechos radiactivos solidos. I - Antes que nada hay que preparar un almacenamiento provisional organizado. II - Evacuacion definitiva : Para organizar la evacuacion definitiva es necesario definir antes, en funcion de la actividad y acondicionamiento de los desechos: - el emplazamiento y la forma de transporte que se piensa utilizar en el interior y en el exterior de los centros nucleares. La eleccion de las diversas soluciones depende de las dos condiciones mencionadas; el autor examina sucesivamente la

  8. Study of the behaviour of artificial radioactive aerosols. Applications to some problems of atmospheric circulation (1963); Etude du comportement dcs aerosols radioactifs artificiels. Applications a quelques problemes de circulation atmospherique (1963)

    Energy Technology Data Exchange (ETDEWEB)

    Lambert, G. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1963-11-15

    The aim of this work, consists in the examination of the behaviour of radioactive aerosols produced in the atmosphere by nuclear explosions, in order to deduce the most general laws governing atmospheric circulation and diffusion. After having given a general table of the radioactive aerosols present the authors consider the validity and the precision of the measurement methods and the concentration of the aerosols at ground level and in the upper atmosphere, as well as their deposition on the ground. The existence is thus demonstrated of a tropospheric equatorial barrier and of discontinuous and seasonal aspects of stratosphere-troposphere transfers. The role is shown of precipitations and dry auto-filtration in the lower atmosphere cleaning processes. This work makes it possible to describe the general behaviour of dust from the stratosphere, and to improve the total radioactive contamination of the globe. (author) [French] L'objectif de ce travail consiste a examiner le comportement des aerosols radioactifs introduits dans l'atmosphere par les explosions nucleaires, pour en deduire les lois les plus generals de la circulation et diffusion atmospheriques. Apres avoir dresse un tableau d'ensemble des aerosols radioactifs presents, on examine la validite et la precision des methodes de mesure de leur concentration, au niveau du sol et en haute atmosphere, ainsi que de leur depot a la surface du sol. On met ainsi en evidence l'existence d'une barriere equatoriale tropospherique; l'aspect discontinu et saisonnier des transferts stratosphere-troposphere; le role des precipitations et de l'auto-filtration seche, dans les processus de nettoyage de la basse atmosphere. Ces etudes permettent de decrire le comportement general des poussieres d'origine stratospherique et d'ameliorer le bilan de la contamination radioactive du globe. (auteur)

  9. Study of the behaviour of artificial radioactive aerosols. Applications to some problems of atmospheric circulation (1963); Etude du comportement dcs aerosols radioactifs artificiels. Applications a quelques problemes de circulation atmospherique (1963)

    Energy Technology Data Exchange (ETDEWEB)

    Lambert, G [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1963-11-15

    The aim of this work, consists in the examination of the behaviour of radioactive aerosols produced in the atmosphere by nuclear explosions, in order to deduce the most general laws governing atmospheric circulation and diffusion. After having given a general table of the radioactive aerosols present the authors consider the validity and the precision of the measurement methods and the concentration of the aerosols at ground level and in the upper atmosphere, as well as their deposition on the ground. The existence is thus demonstrated of a tropospheric equatorial barrier and of discontinuous and seasonal aspects of stratosphere-troposphere transfers. The role is shown of precipitations and dry auto-filtration in the lower atmosphere cleaning processes. This work makes it possible to describe the general behaviour of dust from the stratosphere, and to improve the total radioactive contamination of the globe. (author) [French] L'objectif de ce travail consiste a examiner le comportement des aerosols radioactifs introduits dans l'atmosphere par les explosions nucleaires, pour en deduire les lois les plus generals de la circulation et diffusion atmospheriques. Apres avoir dresse un tableau d'ensemble des aerosols radioactifs presents, on examine la validite et la precision des methodes de mesure de leur concentration, au niveau du sol et en haute atmosphere, ainsi que de leur depot a la surface du sol. On met ainsi en evidence l'existence d'une barriere equatoriale tropospherique; l'aspect discontinu et saisonnier des transferts stratosphere-troposphere; le role des precipitations et de l'auto-filtration seche, dans les processus de nettoyage de la basse atmosphere. Ces etudes permettent de decrire le comportement general des poussieres d'origine stratospherique et d'ameliorer le bilan de la contamination radioactive du globe. (auteur)

  10. Disposal of Waste into the Atmosphere; Elimination des Dechets Radioactifs dans l'Atmosphere; 0423 0414 0410 ; Evacuacion de Desechos Radiactivos en la Atmosfera

    Energy Technology Data Exchange (ETDEWEB)

    Schulte, H. F. [Health Division, Los Alamos Scientific Laboratory, University of California, Los Alamos, NM (United States)

    1960-07-01

    The atmosphere can be compared to the hydrosphere and the lithosphere as a recipient of wastes, but the presence of airborne wastes is of more immediate concern to human life. There are two very distinct problems presented by atmospheric pollution, (1) that in the immediate vicinity of a plant and (2) the world-wide problem from long-term, widespread air pollution. Short- range problems have existed for many years as a result of non-radioactive wastes such as coal-smoke, sulphur dioxide and hydrogen fluoride. However, only in recent years has this problem received intense scientific study. Meteorological conditions play an important role in this problem. In some cases emission rates have been controlled in keeping with meteorological predictions. However, the basic solution is still that of reducing emission rates to the lowest possible values. (author) [French] L'atmosphere peut etre comparee a l'hydrosphere et a la lithosphere en tant que receptacle eventuel de dechets, mais la presence de dechets en suspension dans l'air est plus preoccupante pour la vie humaine. La pollution atmospherique pose deux problemes nettement distincts: 1) un probleme de portee limitee concernant le voisinage immediat d'une usine, et 2) un probleme de portee mondiale, savoir la pollution largement repandue, a long terme, de l'atmosphere. Des problemes de portee limitee se sont poses depuis de nombreuses annees ; ils sont lies a la presence dans l'atmosphere de dechets non radioactifs, tels que les fumees produites par le charbon, l'anhydride sulfurique et l'anhydride fluorhydrique. Cependant, ce n'est que recemment que ce probleme a ete soumis a une etude scientifique poussee. Les conditions meteorologiques jouent la un role important. Dans certains cas, les intensites d'emission ont ete controlees en tablant sur les previsions meteorologiques. Toutefois, la solution fondamentale est encore de reduire l'intensite d'emission a la plus faible valeur possible. (author) [Spanish] Si bien

  11. Health problems raised by the elimination of radioactive wastes and nuclear accidents; Problemes sanitaires poses par l'elimination des dechets radioactifs et par les accidents nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Jammet, H; Mechali, D; Dousset, M [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1964-07-01

    residus radioactifs produits par les installations nucleaires. L'evaluation du risque encouru par les populations et la fixation des limites admissibles pour les rejets ne peuvent resulter que d'une connaissance exacte du cheminement des radioelements rejetes, depuis leur source d'emission jusqu'a l'homme. L'incorporation des radioelements dans les chaines alimentaires constitue le premier risque a prendre en consideration. Les facteurs de passage doivent etre envisages, dans toutes les etapes de cette transmission, qu'elles interessent les milieux physiques ou les milieux proprement biologiques, du fait de leur continuite et de leur interdependance. Enfin, les donnees de caractere socio-economique et dietetique doivent etre recueillies pour conduire a une evaluation des risques et des niveaux admissibles reposant non sur des donnees theoriques mais sur des bases concretes et experimentales. Le risque d'accidents nucleaires dans l'industrie atomique, bien que de probabilite tres reduite, doit etre pris en consideration du fait de la gravite de leurs consequences. Les problemes sanitaires se posent d'une part dans le domaine de l'hygiene professionnelle, d'autre part dans celui de l'hygiene publique. Le premier domaine implique un risque double: d'irradiation et de contamination. Le domaine public n'est soumis essentiellement qu'au risque de contamination par les substances radioactives liberees accidentellement dans le milieu. Les etudes sanitaires a mener dans ce domaine comprennent, de ce fait, les recherches sur la therapeutique des irradiations ou des contaminations mais aussi celles relatives au transfert des radioelements depuis l'installation accidentee jusqu'a l'homme, principalement a travers les chaines alimentaires, dans leurs composantes physiques comme dans leurs composantes biologiques. De telles etudes sont a la base des decisions d'ordre sanitaire qu'il conviendrait de prendre dans le cas d'un accident. (auteurs)

  12. Disposal of Radioactive Wastes in Natural Salt; Elimination des Dechets Radioactifs dans le Sel Naturel; 0423 0414 ; Evacuacion de Desechos Radiactivos en Formaciones Salinas Naturales

    Energy Technology Data Exchange (ETDEWEB)

    Parker, F. L.; Boegly, W. J.; Bradshaw, R. L.; Empson, F. M.; Hemphill, L.; Struxness, E. G.; Tamura, T. [Health Physics Division, Oak Ridge National Laboratory, Oak Ridge, TN (United States)

    1960-07-01

    The proposed use of cavities in salt formations as a disposal site for radioactive wastes is based upon : 1. Existence of salt for geologic time periods, 2. The impermeability of salt to the passage of water; 3. The widespread geographical distribution of salt; 4. The extremely large quantities of salt available; 5. The structural strength of salt; 6. The relatively high thermal conductivity of salt in comparison with other general geologic formations; 7. The possible recovery of valuable fission products in the wastes injected into the salt; 8. The relative ease of forming cavities in salt by mining, and the even greater ease and low cost of developing solution cavities in salt; and 9. The low seismicity in the areas of major salt deposits. Radioactive liquid wastes can be stored in cavities in natural salt formations if the structural properties of the salt are not adversely affected by chemical interaction, pressure, temperature, and radiation. Analytical studies show that it is possible to-store 2-year-old 10,000 MWD/T, 800 gal/ton waste in a sphere of 10 ft diameter without exceeding a temperature of 200 Degree-Sign F. Laboratory tests show that the structural properties and thermal conductivity of rock salt are not greatly altered by high radiation doses, although high temperatures increase the creep rate for both irradiated and unirradiated samples. Chemical interaction of liquid wastes with salt produces chlorine and other chlorine compound gases, but the volumes are not excessive. The migration of nuclides through the salt and deformation of the cavity and chamber can only be studied in undisturbed salt in situ. One-fifth-scale models have been run in a bedded salt deposit in Hutchinson, Kansas, and full-scale field tests are in progress. (author) [French] L'emploi envisage des cavites des gisements de sel comme lieu d'evacuation des dechets radioactifs se-fonde sur les considerations suivantes: 1. L'existence du sel dans des formations correspondant a

  13. Health problems raised by the elimination of radioactive wastes and nuclear accidents; Problemes sanitaires poses par l'elimination des dechets radioactifs et par les accidents nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Jammet, H.; Mechali, D.; Dousset, M. [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1964-07-01

    residus radioactifs produits par les installations nucleaires. L'evaluation du risque encouru par les populations et la fixation des limites admissibles pour les rejets ne peuvent resulter que d'une connaissance exacte du cheminement des radioelements rejetes, depuis leur source d'emission jusqu'a l'homme. L'incorporation des radioelements dans les chaines alimentaires constitue le premier risque a prendre en consideration. Les facteurs de passage doivent etre envisages, dans toutes les etapes de cette transmission, qu'elles interessent les milieux physiques ou les milieux proprement biologiques, du fait de leur continuite et de leur interdependance. Enfin, les donnees de caractere socio-economique et dietetique doivent etre recueillies pour conduire a une evaluation des risques et des niveaux admissibles reposant non sur des donnees theoriques mais sur des bases concretes et experimentales. Le risque d'accidents nucleaires dans l'industrie atomique, bien que de probabilite tres reduite, doit etre pris en consideration du fait de la gravite de leurs consequences. Les problemes sanitaires se posent d'une part dans le domaine de l'hygiene professionnelle, d'autre part dans celui de l'hygiene publique. Le premier domaine implique un risque double: d'irradiation et de contamination. Le domaine public n'est soumis essentiellement qu'au risque de contamination par les substances radioactives liberees accidentellement dans le milieu. Les etudes sanitaires a mener dans ce domaine comprennent, de ce fait, les recherches sur la therapeutique des irradiations ou des contaminations mais aussi celles relatives au transfert des radioelements depuis l'installation accidentee jusqu'a l'homme, principalement a travers les chaines alimentaires, dans leurs composantes physiques comme dans leurs composantes biologiques. De telles etudes sont a la base des decisions d'ordre sanitaire qu

  14. A treatment station for solid radio-active waste at the Saclay nuclear research centre (1962); Station de traitement des dechets radioactifs solides au centre d'etudes nucleaires de Saclay (1962)

    Energy Technology Data Exchange (ETDEWEB)

    Cerre, P; Mestre, E; Lebrun, P [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1962-07-01

    The waste from an atomic centre is very varied in nature, in form, and in activity, going from weakly contaminated laboratory waste to objects actuated in a pile and strongly radioactive. After one year's working of a pilot plant, a factory has been built, in which solide waste is treated and then conditioned in concrete blocks. The present communication describes the treatment and conditioning techniques in this factory which uses to a maximum remotely controlled operation. (authors) [French] Les dechets d'un Centre Atomique sont de natures, de forme et d'activites extremement variees, allant des dechets de laboratoires faiblement contamines, aux dispositifs actives en pile et fortement radioactifs. Apres l'exploitation pendant un an d'une unite pilote, une usine a ete construite dans laquelle les dechets solides sont traites, puis conditionnes en bloc de beton. La presente communication a pour objet la description des techniques de traitement et de conditionnement dans cette usine ou les operations sont au maximum commandees automatiquement et a distance. (auteurs)

  15. A contribution to the study of radioactive waste dilution in the Rhone involving tests with a rhodamine B tracer; Contribution a l'etude de la dilution des effluents radioactifs dans le Rhone par le rejet experimental de rhodamine B

    Energy Technology Data Exchange (ETDEWEB)

    Rodier, J.; Marichal, M. [Commissariat a l' energie atomique et aux energies alternatives - CEA, Centre de production de plutonium de Marcoule, Service de protection contre les radiations (France)

    1961-07-01

    The process whereby waste from the Marcoule plant mixes with the water in the Rhone was followed in tests with rhodamine as a chemical tracer. Satisfactory dispersion was noted less than 4 km downstream from the waste discharge duct outlet, and the degree of homogeneity was considered to be satisfactory at the bridge of Roquemaure, und perfect at Avignon. This investigation not only revealed a complete absence of any preferential flow paths containing high radioactive waste concentrations, but it also enabled the most representative points to be selected at which to take Rhone water samples during future radioactive waste discharges. Reprint of a paper published in 'La Houille Blanche' N. 5 - Aug 196, p. 636-641 [French] L'emploi de la rhodamine comme traceur chimique a permis de suivre l'evolution du melange des effluents du Centre de Marcoule aux eaux du Rhone. La dispersion est deja satisfaisante a moins de 4 km en aval de la conduite des rejets, et l'homogeneite peut etre consideree comme atteinte au pont de Roquemaure et parfaite a Avignon. Cette etude a montre que les veines preferentielles ou se concentrait l'ecoulement des effluents radioactifs n'existent pas. Elle a permis de preciser en outre les emplacements les plus representatifs des points d'echantillonnage des eaux du Rhone au cours des rejets. Reproduction d'un article publie dans 'La houille blanche' N. 5 - Aug 196, p. 636-641.

  16. Tests of the use of cation exchange organic resins for the decontamination of radioactive aqueous effluents; Essais d'emploi des resines organiques echangeuses de cations pour la decontamination des effluents aqueux radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Bourdrez, Jean; Girault, Jacques; Wormser, Gerald

    1962-12-14

    The authors report tests performed in laboratory and results obtained during an investigation of the use of synthetic ion exchangers for the decontamination of radioactive effluents of moderate activity level and with a non neglectable salt loading. Resins are used under sodium form and regenerated after each fixing operation. Once decontaminated and free of its disturbing ions, the regenerating agent (NaCl) is used for several operations. The authors present the used resins, the treated effluents, describe the tests, and discuss the obtained results [French] Dans ce rapport nous faisons le point des essais et resultats obtenus au laboratoire au cours d'une etude concernant l'utilisation des echangeurs d'ions synthetiques pour la decontamination des effluents radioactifs de niveau d'activite moyenne et de charge en sels non negligeable. Les resines sont employees sous forme sodique et regenerees apres chaque operation de fixation. Le regenerant decontamine et debarrasse de ses ions genants est utilise pour plusieurs operations d'elution. Les seuls residus a stocker proviennent d'une part eventuellement d'un pretraitement de l'effluent, d'autre part, dans tous les cas des precipites consecutifs a la purification de l'eluant dont le traitement chimique est plus aise et donne lieu a des boues beaucoup moins volumineuses qu'une coprecipitation effectuee sur la totalite de l'effluent. (auteurs)

  17. The use of an experimental device for the determination of the concentration of artificial radioactive aerosols at high altitudes; Utilisation d'un missile experimental pour l'evaluation des concentrations en aerosols radioactifs artificiels en haute altitude

    Energy Technology Data Exchange (ETDEWEB)

    Boclet, D; Jehanno, C; Labeyrie, J [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires; Le Boiteux, H [Office National d' Etudes et de Recherches Aeronautique, 92 - Chatillon sous Bagneux (France)

    1960-07-01

    By means of measurements with a Geiger counter on january, the 27{sup th}, in 1959 at an altitude reaching 65 km approximately, and following comparison with similar measurements made by Gangnes, Jenkins and Van Allen in 1949 at the same geomagnetic latitude (41 deg. North), it is concluded that radioactive aerosols above Southern France tropopause had a concentration less than 100.10{sup -12} curies/m{sup 3} at that time. The missile used for this purpose and its performance are quickly described in this paper. (author) [French] Au moyen de mesures faites au compteur Geiger le 27 janvier 1959 jusqu'au environ de 65 km et apres comparaison avec des mesures analogues faites en 1949 par Gangnes, Jenkins et Van Allen a la meme altitude geomagnetique (41deg. N), on conclut que les aerosols radioactifs au-dessus de la tropopause de la France meridionale avaient a cette epoque une concentration inferieure a 100.10{sup -12} curies/m{sup 3}. Une rapide description du missile utilise et de ses performances complete cette communication. (auteur)

  18. Count rate balance method of measuring sediment transport of sand beds by radioactive tracers; Methode du bilan des taux de comptage d'indicateurs radioactifs pour la determination du debit de charriage des lits sableux

    Energy Technology Data Exchange (ETDEWEB)

    Sauzay, G [Commissariat a l' Energie Atomique, 91 - Saclay (France). Centre d' Etudes Nucleaires

    1967-11-01

    Radioactive tracers are applied to the direct measurement of the sediment transport rate of sand beds. The theoretical measurement formula is derived: the variation of the count rate balance is inverse of that of the transport thickness. Simultaneously the representativeness of the tracer is critically studied. The minimum quantity of tracer which has to be injected in order to obtain a correct statistical definition of count rate given by a low number of grains 'seen' by the detector is then studied. A field experiment was made and has let to study the technological conditions for applying this method: only the treatment of results is new, the experiment itself is carried out with conventional techniques applied with great care. (author) [French] Les indicateurs radioactifs sont appliques a la mesure directe du debit de charriage des lits sableux. On etablit la formule theorique de mesure: le bilan des taux de comptage varie en sens inverse de l'epaisseur de charriage. Parallelement on fait une etude critique de la representativite de l'indicateur, puis on determine la quantite minimale de traceur qu'il faut immerger pour que les taux de comptage fournis pour un faible nombre de grains 'vus' par le detecteur aient une definition statistique correcte. Une experience de terrain a permis d'etudier les conditions technologiques de cette methode: seul le depouillement des resultats est nouveau. L'experimentation in-situ se fait suivant les procedes classiques avec un tres grand soin. (auteur)

  19. A Study Of The Dilution Of Radio-Active Waste In The Rhone (1961); Etude de la dilution dans le rhone des effluents radioactifs du Centre de Marcoule (1961)

    Energy Technology Data Exchange (ETDEWEB)

    Rodier, J; Scheidhauer, J; Marichal, M; Court, R [Commissariat a l' Energie Atomique, Centre de Production de Plutonium, Marcoule (France). Centre d' Etudes Nucleaires

    1961-07-01

    The discharge into the Rhone of liquid radio-active waste from the Marcoule Centre necessitates a large number of measurements, in particular chemical and radio-chemical analysis of the waste, itself and of the waters of the Rhone both above arid below the point of discharge. The results thus obtained during 1960 made it possible to evaluate the total amount of active waste discharged and its dilution in the receiving medium. A statistical study of the results of the analysis of the Rhone waters shows that a satisfactory dilution of the waste occurs rapidly; the experimental results obtained with an experimental discharge of rhodamine are thus confirmed. (authors) [French] Le rejet au Rhone des effluents radioactifs liquides produits sur le Centre de Marcoule donne lieu a un grand nombre de mesures et en particulier d'analyses chimiques et radio-chimiques des effluents eux-memes ainsi que des eaux du Rhone avant et apres rejet. Au cours de l'annee 1960, l'ensemble des resultats ainsi obtenus a permis de dresser un bilan des activites rejetees et de leur dispersion dans le milieu recepteur. Une etude statistique des resultats d'analyses des eaux du Rhone montre qu'une dilution satisfaisante des effluents s'effectue rapidement confirmant ainsi les resultats obtenus lors d'un rejet experimental de rhodamine. (auteurs)

  20. Recovery of sludge from the treatment of liquid radioactive effluents by co-precipitation with calcium carbonate: laboratory study; Recuperation des boues de traitement des effluents radioactifs liquides par coprecipitation avec le carbonate de calcium: etude de laboratoire

    Energy Technology Data Exchange (ETDEWEB)

    Patti, F.; Gailledreau, C.; Cohen, P.

    1961-02-24

    As during the treatment by co-precipitation with calcium carbonate of liquid radioactive residues, a partial decontamination can be obtained by simply agitating an already formed radioactive sludge with the effluent to be processed, the authors study whether it would be possible to first perform a co-precipitation with a lower dose of calcium carbonate and then to complete decontamination by agitating with an adequate quantity of sludge stored during preceding operations. The authors report the study of the influence of reactant quantity on the chemical treatment efficiency, of the evolution of the activity of a radioactive residual solution in contact with a precipitate, of the cleaner element, of a precipitate reuse, of the technological and economic aspects, and of another possibility of reduction of the precipitate volume [French] Dans le traitement par coprecipitation avec le carbonate de calcium des residus radioactifs liquides, une decontamination partielle peut etre obtenue en agitant simplement une boue radioactive deja formee avec l'effluent a traiter. En consequence, il pourrait etre possible d'effectuer d'abord une coprecipitation avec une dose plus faible de carbonate de calcium et de completer ensuite la decontamination en agitant le liquide avec une quantite convenable de boue stockee a partir d'operations precedentes. (auteurs)

  1. Temperature Distribution in Radioactive Solid Wastes. Part I - Beta-Active Solids; Repartition des Temperatures dans les Dechets Radioactifs Solides. Partie I - Solides Radioactifs Beta; 0420 0410 0421 041f 0420 0415 0414 ; Distribucion de la Temperatura en los Desechos Radiactivos Solidos. Parte I - Desechos Solidos Emisores de Radiaciones Beta

    Energy Technology Data Exchange (ETDEWEB)

    Kotewale, D. A.; Ganguly, A. K. [Atomic Energy Establishment, Trombay (India)

    1960-07-01

    The paper deals with the calculations for temperature distribution over time in a radioactive sphere and in a finite radioactive cylinder buried in a medium having the same thermal properties. Formulae are given for such calculations. Numerical results on temperature build-up are presented graphically for the cases where the activity is due to beta-emitters such as P{sup 32}, Sr{sup 89}, Cs{sup 135} and Sr{sup 90} + (Y{sup 90}). General graphs for calculation of temperature build-up for any long-lived beta-emitter at certain points of interest in a sphere and in a cylinder of particular dimensions and diffusivity are presented. (author) [French] Ce memoire a trait aux calculs servant a evaluer la variation des temperatures en fonction du temps dans une sphere radioactive et dans un cylindre radioactif limite enfouis dans un milieue ayant les memes proprietes thermiques. Les formules utilisees dans ces calculs sont indiquees. Les resultats numeriques concernant la formation des temperatures sont representes graphiquement pour les cas ou l'activite est due a des emetteurs beta tels que {sup 32}P, {sup 89}Sr, {sup 135}Cs et {sup 90}Sr + ({sup 90}Y). Le memoire contient des abaques pour le calcul de la formation des temperatures dans les emetteurs gamma de longue periode a certains points interessants des spheres et des cylindres ayant des dimensions et une capacite de diffusion particulieres. (author) [Spanish] En la memoria se estudia el calculo de la distribucion de temperaturas en funcion del tiempo en una esfera radiactiva y en un cilindro radiactivo finito enterrados en un medio de identicas propiedades termicas. Se dan formulas para efectuar dicho calculo. En el caso en que la actividad se deba a emisores beta, tales como {sup 32}P, {sup 89}Sr, {sup 135}Cs y {sup 90}Sr + ({sup 90}Y), se representan graficamente los resultados numericos relativos al incremento de ]a temperatura. Asimismo, se proporcionan graficos generales para calcular el incremento de la

  2. Some Questions on the Fixation of Radioisotopes in Connexion with the Problem of their Safe Burial; Quelques Aspects de la Fixation des Isotopes Radioactifs en Rapport avec le Probleme de leur Elimination dans le Sol; 041d 0414 ; Algunos Aspectos de la Fijacion de los Isotopos Radiactivos en Relacion con los Problemas de su Evacuacion sin Riesgos en el Suelo

    Energy Technology Data Exchange (ETDEWEB)

    Zimakov, P. V.; Kulichenko, V. V.

    1960-07-01

    The results given in this paper are based on the fact that the best way of burying fission products is to incorporate them in vitrified fused blocks containing these fission products. The physico-chemical bases of the transformation of liquid waste into solid blocks are shown. The thermogram of this process is presented and the analysis of its characteristics given. The conditions of fusion of the vitrified mass, in particular those contributing to the fixation of radioactive aerosols, are shown. Some results of studies on the chemical state of radioactive fission products in the solid mass in connexion with the leaching of their radioactivity are given. In conclusion, the results of calculations of the temperatures up to which the radioactive blocks may be heated according to their characteristics are presented. (author) [French] Le present memoire est base sur l'hypothese que le meilleur procede d'elimination des dechets radioactifs dans le sous:sol consiste a les enfouir sous forme de blocs coules dans lesquels ils seraient intimement meles a du verre. Les auteurs decrivent les phenomenes physico-chimiques qui permettent la transformation des dechets radioactifs liquides en blocs solides. Ils donnent le thermogramme de ce processus et examinent certaines de ses particularites. Ils exposent en outre les conditions de coulage de la masse de verre, notamment celles qui facilitent la formation d'aerosols radioactifs. Les auteurs donnent quelques resultats des etudes effectuees sur l'etat chimique des elements radioactifs au sein de la masse solide, dans la mesure ou ces resultats touchent aux problemes que pose la fuite de la radioactivite due au 'lessivage' du bloc par l'eau. En conclusion, les auteurs indiquent les resultats du calcul des temperatures maxima auxquelles on peut porter les blocs radioactifs compte tenu de leurs caracteristiques. (author) [Spanish] Los autores de la memoria parten del supuesto de que la mejor manera de evacuar en el suelo los

  3. The use radioactive tracers in the study of solid transport in water streams; Emploi de traceurs radioactifs pour l'etude du transport solide dans les cours d'eau

    Energy Technology Data Exchange (ETDEWEB)

    Courtois, G [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires; Jaffry, P; Heuzel, M [Laboratoire National d' Hydraulique de Chatou, 78 (France)

    1960-07-01

    The Laboratoire National d'Hydraulique which has been studying, during the last few years in conjunction with the Centre d'Etudes Nucleaires at Saclay, the development of apparatus and of methods of investigation of sediment transport by radioactive tracer techniques, is at the moment trying to perfect a genuinely quantitative method of investigation. Two experiments have recently been carried out in rivers, the first designed to investigate the transport of pebbles in the river Rhone, the other to investigate the movement of sands in the Niger. This second experiment has been supported by parallel experiments carried out on a reduced scale model of the Niger built at the laboratories of Chatou: in this experiment are used the radiation from {sup 56}Mn and {sup 24}Na obtained by direct activation of the crushed apricot store which represents, in the scale model, the natural sediment on the bed of the Niger. The combined efforts of the laboratories of Chatou and of the Centre d'Etudes Nucleaires at Saclay are at the moment directed to the application of radioactive tracers to studies on the scale models with the double aim: a) of having a single investigational method for the actual experiment and for the model making it possible to control the accuracy of the model in the preliminary stage of calibrating this model; b) of making the most of the possibilities of observation and of direct measurement offered by the scale models for studying the possibility of improving the tracer method, in particular with respect to the collecting of quantitative data. (author) [French] La Laboratoire National d'Hydraulique qui, depuis quelques annees a developpe, en collaboration avec le Centre d'Etudes Nucleaires de Saclay, les appareillages et les techniques d'etudes des mouvements de sediments par la methode des traceurs radioactifs, s'efforce actuellement de mettre au point un moyen d'investigation veritablement quantitatif. Deux experiences ont ete effectuees recemment en

  4. Technical and Economic Problems Associated with the Development of Methods of Processing and Using Radioactive Waste; Problemes techniques et economiques lies au developpement des methodes de traitement et d'utilisation des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Thiriet, L; Sauteron, J; Oger, C [Commissariat a l' Energie Atomique, Fontenay-Aux-Roses (France). Centre d' Etudes Nucleaires

    1968-07-01

    The paper briefly reviews the various techniques used in processing the radioactive wastes which unavoidably result from the generation of electric power from nuclear sources. The paper goes on to define the relative importance, in nuclear fuel cycles, of the problem raised by these wastes. Emphasis is placed on the economic influence of management policies on the cost of power generation, and hence on the relative position of nuclear energy. A substantial percentage of these wastes can be economically utilized. Attention is drawn to the major technical and economic features of the industry which will come into being as a result of this utilization. The major uses anticipated are discussed: radiation sources, heat sources, auxiliary power generation. The paper concludes that satisfactory solutions have already been found to these problems, and describes possible improvements. (author) [French] La communication rappelle d'abord succinctement les differentes techniques de traitement des dechets radioactifs resultant necessairement de la production d'electricite d'origine nucleaire. On situe ensuite l'importance du probleme pose par ces residus dans le cycle du combustible nucleaire. On fait ressortir l'influence economique du choix des methodes de gestion sur le cout de production de l'energie, et par consequent sur la place devolue a l'energie nucleaire. Une part importante de ces dechets peut faire l'objet d'une utilisation rentable de l'industrie qui naitra de cette utilisation. Les principales applications envisagees sont evoquees: sources d'irradiation, sources chauffantes, generateurs auxiliaires d'energie. On conclut que d'ores et deja des solutions satisfaisantes ont ete apportees a ces problemes, et l'on decrit les perspectives d'amelioration concevables. (auteur)

  5. Quantitative measurements of small isotopic samples in gaseous mixtures by utilization of some nuclear properties; Etude des possibilites de mesures de faibles quantites de gaz radioactifs dans un melange en utilisant simultanement plusieurs proprietes nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Maragnon, J; Delperie, C

    1967-12-01

    The question is to define the characteristics of a group of measurements allowing the analysis of traces of radioactive rare gases in gas mixtures of different composition. To distinguish the radioactive isotopes from each other and the activity level reaching 10{sup 6} due to their nuclear properties, the method was chosen to use several nuclear properties: gamma radiation energy, beta particle energy, lifetime of excited states. The choice of a plastic scintillator as beta detector allows to answer satisfactorilly to this demand by measurement of nuclear constants because of the short de/excitation time of this detector. Another advantage is that it can be a reservoir for the sample without any destruction nor modification of the sample. The study has been based on the mixture of Kr-85, the analysis of other rare gases follwos immediately from the adopted principle. [French] Les auteurs ont oriente leur recherche vers une solution permettant de distinguer les isotopes radioactifs les uns des autres et dans des rapports d'activite pouvant atteindre 10{sup 6}, grace a plusieurs de leurs proprietes nucleaires, energie de rayonnement gamma, energie de la particule beta, temps de vie des niveaux excites. Le choix d'un scintillateur plastique comme detecteur beta permet de repondre d'une maniere satisfaisante a la mesure des constantes nucleaires en raison du temps de de/excitation rapide de ce scintillateur. Il offre en outre l'avantage de pouvoir servir de reservoir a l'echantillon sans entrainer aucune destruction ni modification de celui-ci. L'etude a ete basee sur la mixture de Kr-85, l'analyse des autre gaz rares decoulant immediatement du principe adopte. (auteur)

  6. The application of radioactive isotopes to the study of motion of silt and pebbles in the rivers and in the sea; Application des isotopes radioactifs a l'etude des mouvements des sediments et des galets dans les cours d'eau et en mer

    Energy Technology Data Exchange (ETDEWEB)

    Hours, R [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires; Jaffry, P [Electricite de France (EDF), 78 - Chatou (France). Lab. National d' Hydraulique

    1959-07-01

    The application of radioactive tracers to the study of sediments drift has received considerable attention since 1954 in various countries. A comparative review is made of a number of techniques of labelling, immersing and detecting silts, sands, and pebbles. The influence of the burying of the active material is emphasized. The different experiments which have been so far carried out are described. (author) [French] L'application des traceurs radioactifs a l'etude des deplacements de sediments a fait depuis 1954 l'objet de travaux nombreux dans divers pays. On passe en revue et on compare differentes techniques de marquage, d'immersion et de detection des vases, sables et galets; on insiste sur l'influence de l'enfouissement du materiau actif. On decrit les differentes experiences effectuees jusqu'a ce jour. (auteur)

  7. Disposal of the radioactive effluents at the 'Commissariat a l'Energie Atomique'. Treatment leading to evacuation into a river; Probleme du rejet des residus radioactifs liquides au CEA. Traitements aboutissant a des rejets en riviere

    Energy Technology Data Exchange (ETDEWEB)

    Duhamel,; Menoux,; Candillon, [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    loaded water, 10) Impot elements other than Sr{sup 90} are also studied. (author) [French] Le probleme du traitement des residus radioactifs liquides au CEA est envisage sous l'angle du rejet ultime en riviere dans des conditions optima permettant de satisfaire aux Normes de la protection. 2) A Saclay, ou l'on ne dispose que d'un etang ou l'eau ne se renouvelle pas, les liquides epures sont envoyes par camion citerne a Fontenay-aux-Roses, ou ils sont deverses provisoirement - dans les egouts - en attendant qu'un point de rejet en Seine ait ete determine. 3) Au Bouchet, les eaux residuaires de l'Usine de traitement de minerais d'urano-thorianite devront etre traitees en deux temps de facon a separer le radium dans une premiere phase, ce qui facilitera l'epuration au cours de la deuxieme phase. 4) En vue des futurs rejets a Marcoule, une etude a ete conduite a Saclay, sur des effluents synthetiques - type Marcoule - ayant pour but de mettre au point des procedes d'elimination selective du Sr d'une part, du Cs d'autre part, par coprecipitation. 5) Dans le cas general du rejet ultime en riviere, les problemes suivants sont successivement envisages: - predilution entre les bassins de stockage des eaux epurees et le fleuve; - mode d'injection dans le fleuve; - dilution dans le fleuve (etude prealable par traceurs); - evolution de l'activite dans les eaux du fleuve (adsorption par les organismes inertes ou vivants, contamination des berges); - incidence sur le choix d'un site; - dilution isotopique. 6) Ce dernier probleme est specialement detaille. 7) La teneur de l'eau en un element donne conditionne la dilution isotopique de son isotope radioactif. L'analyse decelant une carence, il est possible d'y suppleer par des rejets d'isotope stable. 8) Cette methode conduit en certains cas a des analyses delicates (en particulier dans le cas du {sup 90}Sr), la teneur en isotope stable necessaire a une forte dilution isotopique restant faible (ce qui est d'ailleurs un avantage). 9

  8. On the Waste Disposal Potentiality of the Atmosphere; Possibilites d'Elimination des Dechets Radioactifs dans l'Atmosphere; 041a 0412 041e 041f 0414 ; Sobre la Posibilidad de Evacuar Desechos en la Atmosfera

    Energy Technology Data Exchange (ETDEWEB)

    Small, S. H.; Storebo, P. B. [Norwegian Defence Research Establishment (Norway)

    1960-07-01

    The whole scale of atmospheric mixing, transport and removal processes is reviewed. Certain measurements indicate replacement of stratospheric air within about two years, making high-altitude disposal of radioactive waste materials even less attractive than earlier assumed. Deposition of radioactive materials is to some extent systematically non-uniform, and permissible levels of atmospheric radioactivity should be based upon the probable hazards in the most exposed regions, e.g. regions of considerable orographic precipitation. In connexion with the measurement of atmospheric radioactivity, it is pointed out that sampling techniques should cover the probable effects of gradual changes in particle sizes, and removal of particles by settling, impingement and absorption on vegetation and buildings etc. Meteorological problems in connexion with radiation monitoring and warning systems are discussed in relation to reactor operations. Technical details of relatively simple warning systems are given. (author) [French] Les auteurs examinent l'ensemble des processus suivant lesquels les dechets radioactifs sont brasses, transportes et disperses dans les couches atmospheriques. Certaines mesures indiquent que le renouvellement des masses d'air stratospheriques se fait' en moins de deux ans environ; la possibilite d'eliminer les dechets radioactifs dans les couches superieures de l'atmosphere semble donc encore moins seduisante qu'elle ne le paraissait tout d'abord. On peut dire que, dans une certaine mesure, le depot des substances radioactives s'effectue systematiquement de facon non uniforme; pour determiner le taux de radioactivite atmospherique admissible, il faut donc se baser sur les risques probables encourus dans les regions les plus exposees, par exemple dans les regions a fortes precipitations orographiques. En ce qui concerne la mesure de la radioactivite atmospherique, les techniques d'echantillonnage devraient tenir compte des consequences probables de la

  9. Applicability of ICRP principles for safety analysis of radioactive waste geological storage; Etude de l'applicabilite des principes de la CIPR a l'analyse de surete du stockage geologique des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Lombard, J; Hubert, P; Pages, P

    1987-07-01

    Since the beginning of the eighties, the international organisations have established new recommendations for radioactive waste management. These recommendations are based on two principles. First is concerned with limitation of risks. It should be shown that the risk is smaller than the limit of acceptance. Practically only on risk criterion is foreseen. The principle demands, if a storage causes an event of individual risk (defined as a product of probability of occurrence and the probability of its causing severe health effects) is higher than 10 {sup -5} per year, this storage is not acceptable. The second principle deals with optimisation, demands that the level of protection related to the storage should be determined by a comparative process choosing the best compromise between the price of protection and the residual risk. These recommendations, especially the second one, differ from the safety analysis principles adopted presently in France and other countries. This study analyzes the advantages and potential inconveniences related to the introduction of the second principle. (author) [French] Depuis le debut des annees quatre vingt, de nouvelles recommandations ont ete formulees par les organismes internationaux (AIEA, OCDE, OIPR) en matiere de gestion des dechets radioactifs. Ces recommandations s'articulent autour de deux principes. Le premier, est celui de limitation des risques. II s'agit de demontrer que le risque est inferieur a un seuil d'acceptabilite. En pratique, un seul critere de risque est envisage. Ainsi le principe stipule, que si un stockage est a I'origine d'evenements conduisant a un risque individuel (defini comme le produit de a probabilite d'occurrence de l'evenement par Ia probabilite que cet evenement cause un effet sanitaire grave) total annuel superieur a 10{sup -5}/an, alors le risque lie a ce stockage est juge inacceptable. Le second, dit d'optimisation, stipule que le niveau de protection associe a un stockage (donc les

  10. Study of the diffusion of iron, of silver and of carbon in beryllium using radioactive tracers; Etude de la diffusion du fer, de l'argent et du carbone dans le beryllium au moyen des traceurs radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Naik, M Ch [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1964-06-01

    A study has been made of the diffusion of radioactive iron and silver tracers in beryllium. The following values have been found. D{sub Fe} = 0.53 exp - [51800 / RT], D{sub Ag} = 62 exp - [46100 / RT]. The values for iron are in good agreement with those found previously for chemical diffusion. A comparison of the diffusion coefficients for iron, silver and nickel shows that the diffusion rate increases with increasing solute atom radius. The existence has been shown of diffusion anisotropy for silver; it has been studied quantitatively on monocrystals. It is found that: D{sub parallel} 0.41 exp - [39100 / RT], D{sub perpendicular} = 1.98 exp - [45700 / RT]. The anisotropy decreases as the temperature increases. The silver diffuses more rapidly along the C axis than in the base plane. This result cannot be explained in terms of the model proposed for the diffusion of foreign atoms in solution in zinc. A greater number of experiments is required before a model can be put forward. An attempt has also been made to determine the diffusion coefficients of carbon in beryllium by treatment in an atmosphere of acetylene marked with C-14. Diffusion coefficients have been obtained but these should not be considered to be very significant since a chemical reaction occurs at the surface of the samples. (author) [French] On a etudie la diffusion dans le beryllium de traceurs radioactifs du fer et de l'argent. On trouve: D{sub Fe} = 0.53 exp - [51800 / RT], D{sub Ag} = 62 exp - [46100 / RT].Les valeurs trouvees pour le fer sont en bon accord avec les valeurs obtenues precedemment pour la diffusion chimique. La comparaison des coefficients de diffusion du fer, de l'argent et du nickel montre que la diffusion est d'autant plus rapide que le rayon atomique du solute est plus grand. On a mis en evidence une anisotropie de diffusion de l'argent qui a ete etudiee quantitativement sur des monocristaux. On trouve: D{sub parallele} = 0.41 exp - [39100 / RT], D{sub perpendiculaire} = 1

  11. Pharmacological study of radioactive-gold colloid transport by blood and by serous exudate; Contribution a l'etude pharmacologique du transport des colloides d'or radioactif par le sang et les exsudats sereux

    Energy Technology Data Exchange (ETDEWEB)

    Rousselet, J. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1966-06-01

    substances et particulierement dans le transport de l'or colloidal radioactif. Les fractions sanguines qui peuvent participer au transport de l'or colloidal sont les hematies, les leucocytes et elements histiocytaires, et le plasma. La repartition de la radioactivite dans ces elements est precisee en pratiquant des autoradiographies de coupes de culots de sang centrifuge et congele apres incubation avec de l'or colloidal. Cette etude montre l'importance du plasma dans le transport des particules radioactives. Nous avons alors recherche une fixation eventuelle de l'or colloidal 198 sur les diverses proteines seriques en appliquant certaines methodes de separation a savoir une filtration-exclusion sur colonne de gel de Sephadex G-200 et un fractionnement electrophoretique sur papier et sur acetate de cellulose gelatineux (cellogel). Nous avons etudie la liaison ''in vitro'' et ''in vivo'' des particules colloidales d'or 198 d'abord avec les proteines seriques de sujets sains puis avec les proteines des liquides d'epanchement d'origine pathologique, chez l'homme, ou du a une inflammation experimentale a la carragenine chez le rat. Les particules d'or colloidal 198 de 30 m{mu} (S-2) sont liees dans une certaine mesure aux {alpha}2 globulines sanguines ou ascitiques, celles de 5 m{mu} (S-6) sont liees aux {alpha}1 globulines de meme que les grains contenus dans l'or polydisperse. Cette liaison semble intervenir grace a la couche protectrice de macromolecules constituees par la gelatine. Seules les caracteristiques physicochimiques de grains colloidaux peuvent expliquer leur difference de localisation sur l'electrophoregramme. L'or sous forme ionique, par contre, est combine, aux seules albumines si la quantite de metal presente ne depasse pas une certaine limite. (auteur)

  12. Pharmacological study of radioactive-gold colloid transport by blood and by serous exudate; Contribution a l'etude pharmacologique du transport des colloides d'or radioactif par le sang et les exsudats sereux

    Energy Technology Data Exchange (ETDEWEB)

    Rousselet, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1966-06-01

    transport de l'or colloidal radioactif. Les fractions sanguines qui peuvent participer au transport de l'or colloidal sont les hematies, les leucocytes et elements histiocytaires, et le plasma. La repartition de la radioactivite dans ces elements est precisee en pratiquant des autoradiographies de coupes de culots de sang centrifuge et congele apres incubation avec de l'or colloidal. Cette etude montre l'importance du plasma dans le transport des particules radioactives. Nous avons alors recherche une fixation eventuelle de l'or colloidal 198 sur les diverses proteines seriques en appliquant certaines methodes de separation a savoir une filtration-exclusion sur colonne de gel de Sephadex G-200 et un fractionnement electrophoretique sur papier et sur acetate de cellulose gelatineux (cellogel). Nous avons etudie la liaison ''in vitro'' et ''in vivo'' des particules colloidales d'or 198 d'abord avec les proteines seriques de sujets sains puis avec les proteines des liquides d'epanchement d'origine pathologique, chez l'homme, ou du a une inflammation experimentale a la carragenine chez le rat. Les particules d'or colloidal 198 de 30 m{mu} (S-2) sont liees dans une certaine mesure aux {alpha}2 globulines sanguines ou ascitiques, celles de 5 m{mu} (S-6) sont liees aux {alpha}1 globulines de meme que les grains contenus dans l'or polydisperse. Cette liaison semble intervenir grace a la couche protectrice de macromolecules constituees par la gelatine. Seules les caracteristiques physicochimiques de grains colloidaux peuvent expliquer leur difference de localisation sur l'electrophoregramme. L'or sous forme ionique, par contre, est combine, aux seules albumines si la quantite de metal presente ne depasse pas une certaine limite. (auteur)

  13. Waste Disposal Research and Development in the United States of America; L'Elimination des Dechets Radioactifs aux Etats-Unis d'Amerique: Travaux de Recherche et Progres Accomplis; 0418 0417 0423 0427 0414 ; Investigaciones y Trabajos Realizados en los Estados Unidos en Materia de Evacuacion de Desechos Radiactivos

    Energy Technology Data Exchange (ETDEWEB)

    Struxness, E. G.; Cowser, K. E.; De Laguna, W.; Jacobs, D. G.; Morton, R. J.; Tamura, T. [Health Physics Division, Oak Ridge National Laboratory, Oak Ridge, TN (United States)

    1960-07-01

    A review of the waste-disposal research and development carried out in the United States of America is given. The major research effort concerns the conversion of high-level liquid wastes into solids. At Hanford and Oak Ridge low-level wastes are disposed to the ground in pits, cribs and lagoons. Geochemical studies related to waste disposal are conducted at Hanford, Oak Ridge and the University of North Carolina. Experiments with soil columns ate described ; these are more effective for the decontamination of waste streams than either cribs or pits. The most suitable exchange materials for the soil columns are found to be vermiculite supported by rock phosphate and the latter supported by graded gravel. The progress of research work on the possibility of injecting radioactive liquid wastes into porous formations through deep wells and disposing of radioactive wastes in impermeable formations by hydraulic fracturing is outlined. (author) [French] L'auteur passe en revue les recherches effectuees aux Etats-Unis en matiere d'elimination des dechets radioactifs et les progres accomplis dans ce domaine. En matiere de recherche, on s'attache principalement a la conversion en solides des dechets liquides de haute activite. A Hanford et a Oak Ridge, les dechets de faible activite sont elimines par decharge terrestre dans des coffres, puits et depots lagunaires. Des etudes de geochimie se rapportant a l'elimination des dechets sont en cours a Hanford, a Oak Ridge et l'Universite de Caroline du Nord. Le memoire decrit les experiences faites avec des colonnes ; pour decontaminer les dechets liquides, ces dernieres sont plus efficaces que les coffres ou les puits. Les substances echangeuses d'ions les plus appropriees pour les colonnes sont vermiculite-phosphate naturel-gravier trie. L'auteur expose les progres dea travaux de recherche portant sur la possibilite d'injecter des dechets radioactifs liquides dans des formations poreuses, par decharge dans des puits profonds, et

  14. Fisheries Radiobiology and the Discharge of Radioactive Wastes; Radiobiologie des Pecheries et Evacuation des Dechets Radioactifs; 041f 0420 0418 014 ; Radiobiologia de las Pesquerias y Evacuacion de Desechos Radiactivos

    Energy Technology Data Exchange (ETDEWEB)

    Morgan, F. [Fisheries Radiobiological Laboratory, Ministry of Agriculture, Fisheries and Food (United Kingdom)

    1960-07-01

    In the United Kingdom authorizations to discharge radioactive wastes are granted by the Minister of Housing and Local Government, the Minister of Agriculture, Fisheries and Food, and by the Secretary of State for Scotland. The hazards arising from contamination of aquatic animals and plants concern the Department of Fisheries ; before authorizations to discharge liquid wastes have been given, the Department has made independent forecasts of permissible levels of discharge based on extensive studies carried out in its research vessels and radiobiological laboratory: for example, where fish have been affected this has meant studies of fish populations and fish migration: uptake of radioactivity by fish : public consumption of fish : commercial distribution of affected fish: L.D.{sub 50}: effects of radiation on tissue, etc. In the course of such work there has been close consultation with the Atomic Energy Authority, and agreement with the Atomic Energy Authority about the safety factor to be incorporated during the first two years of discharge. During these two years, monitoring data collected by the Atomic Energy Authority and the Ministry of Agriculture, Fisheries and Food enable checks and revisions of the original estimates to be made, and at the end of that time formal authorizations, based on operating experience, are issued. (author) [French] Au Royaume-Uni, les autorisations d'evacuer des dechets radioactifs sont accordees par le Ministre du logement et de l'administration locale, par le Ministre de l'agriculture, des pecheries et de l'alimentation et par le Secretaire d'Etat pour l'Ecosse. Les risques dus a la contamination des animaux et des plantes aquatiques relevent du Departement des pecheries; avant d'accorder des autorisations d'evacuer des dechets liquides, le Departement a evalue lui-meme les quantites dont l'evacuation pourrait etre admise, en se fondant sur des etudes approfondies qui sont faites dans ses bateaux de recherche et son laboratoire

  15. A Review of Radioactive Waste Disposal to the Ground at Hanford; Etude sur l'Elimination dans le Sol des Dechets Radioactifs a Hanford; 041e 0411 0417 0414 ; Evacuacion de Desechos Radiactivos en el Subsuelo de Hanford

    Energy Technology Data Exchange (ETDEWEB)

    Pearce, D. W.; Lindbroth, C. E.; Nelson, J. L.; Ames, Jr., L. L. [Hanford Laboratories, Hanford Atomic Products Operation, General Electric Company, Richland WA (United States)

    1960-07-01

    The disposal of radioactive wastes to the ground from the Hanford separations plants is summarized ; volumes of wastes and contained curies discharged to swamps, trenches, and cribs are presented. Significant literature on ion- exchange studies using Hanford soils is reviewed. A field experiment with a model crib is described; preliminary findings indicate that spreading a waste solution below a disposal facility may be of greater benefit in disposal operations than previously assumed. Further studies with the calcite-phosphate reaction are reported; significant variables which affect Sr{sup +2} removal are calcite surface area, pH of the influent, flow rate, temperature and phosphate ion concentration. Bone-seeking radioisotopes are also removed from F- solutions when contact is made with calcite. The zeolite clinoptilolite shows high selectivity for Cs{sup +} even in the presence of increased Na{sup +} concentration. The effect of the large-scale ground disposal operation at Hanford is described by means of a map and geological cross-sections showing areas and volumes of ground and ground water contamination. (author) [French] Les auteurs donnent un apercu de l'elimination dans le sol des dechets radioactifs des usines de separation des isotopes de Hanford ; ils indiquent les quantites de dechets - et de curies - qui sont evacuees dans des marecages, des tranchees et des coffres. Ils passent en revue des etudes importantes qui ont ete publiees sur les proprietes d'echangeurs d'ions des sols de Hanford. Ils decrivent une experience pratique faite avec un coffre modele; il ressort des resultats preliminaires que le fait de repandre une solution de dechets au-dessous d'une installation d'evacuation pourrait etre beaucoup plus avantageux pour les operations d'evacuation que l'on n'avait cru precedemment. Les auteurs signalent d'autres etudes fondees sur la reaction calcite-phosphate ; parmi les variables importantes qui influent sur l'elimination du Sr{sup ++}, il

  16. The Public Health Problems of Nuclear Waste Disposal; L'Elimination des Dechets Radioactifs et la Sante Publique; 041f 0420 041e 0414 ; Problemas que Presenta para la Salud Publica la Evacuacion de Desechos Radiactivos

    Energy Technology Data Exchange (ETDEWEB)

    Dunster, H. J. [United Kingdom Atomic Energy Authority, Health and Safety Branch (United Kingdom)

    1960-07-01

    The fundamental bases of the control of public health problems in connexion with the disposal of radioactive wastes are the Recommendations of the International Commission on Radiological Protection. These Recommendations cannot be applied directly to the disposal of waste because the released radioactivity rarely reaches man in a direct manner. The setting of maximum permissible discharge rates, therefore, involves a knowledge not only of man's utilization of his environment but also of the diverse processes which govern the behaviour of radioactive materials in that environment. As an example of the way in which the United Kingdom has dealt with these problems the paper discusses the discharge of low-activity liquid wastes into the sea, and refers briefly to the similar problems of assessing discharges into rivers and disposal into the ground or the deep sea. The paper concludes that it is possible to demonstrate without difficulty the safety of most proposed waste-disposal operations but that meticulous investigation and control are necessary whenever substantial amounts of radioactivity are to be released to man's environment. (author) [French] Les donnees de base relatives aux mesure de sante publique touchant l'elimination des dechets radioactifs sont fournies par les recommandations de la Commission internationale de protection radiologique. Mais ces recommandations ne peuvent pas etre directement appliquees a l'elimination des dechets, car il est rare que l'homme se trouve directement expose aux radiations emises. Pour pouvoir fixer, en matiere d'elimination de dechets, un taux maximum admissible, il faut donc connaitre non seulement le comportement de l'homme dans le milieu considere, mais aussi les processus suivant lesquels les matieres radioactives agissent sur ce milieu. Prenant comme exemple ce qui est fait au Royaume-Uni, l'auteur etudie la question de l'evacuation dans la mer de dechets liquides de faible radioactivite et il donne un apercu des

  17. New instruments and methods for measuring the concentration of radioactive products in the atmosphere; Appareils recents et methodes nouvelles pour la mesure de la concentration des produits radioactifs dans l'atmosphere

    Energy Technology Data Exchange (ETDEWEB)

    Jehanno, C; Blanc, A; Lallemant, C; Roux, G [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1959-07-01

    ) [French] Differents enregistreurs pour aerosols radioactifs ont ete realises pour mesurer la pollution de l'atmosphere des laboratoires ou l'atmosphere exterieure. EAR 600. - Permet de mesurer en continu instantanement et 3 a 10 heures apres le prelevement des concentrations d'aerosols emetteurs {alpha} ou {beta} allant de quelques 10{sup -11} a quelques 10{sup -8} curies par metre cube d'air. EAR 800. - Permet de mesurer en continu des concentrations d'aerosols emetteurs {alpha} allant de 10{sup -11} a 10{sup -5} curie par metre cube d'air, et des concentrations d'aerosols emetteurs {beta} allant de 10{sup -11} a 10{sup -1} curie par metre cube d'air. EAR PLUTONIUM. - Permet de detecter en quelques minutes 1000 DMP (2.10{sup -9} curie par metre cube) et en 8 heures 1 DMP (2.10{sup -12} curie par metre cube). Deux methodes sont utilisees pour separer l'activite due au plutonium de celle due aux derives du radon et du thoron: a) par discrimination d'amplitude, b) par les coincidences (a,b) RaC' et ThC-ThC'. SP 4. - Monte sur jeep, cet ensemble permet la mesure de l'irradiation produite au sol par le panache des piles. La sensibilite est de 5{mu}R/h. A.D.I.R. - Cet appareil autonome et portatif est destine a la mesure instantanee des teneurs en radon de l'atmosphere des mines. Il permet de mesurer des teneurs de l'air variant entre 0,4 et 400.10{sup -10} curie par litre d'air (0,4 et 400 DPM). La mesure des retombees radioactives est faite apres collection de cette activite par un pluviometre special comportant une surface adhesive et une cartouche de resines echangeuses d'ions. La radioactivite des retombees varie entre quelques 10{sup -9} et quelques 10{sup -7} curie par metre carre et par mois. La mesure des concentrations de l'atmosphere en produits de fission est faite apres collection sur papier filtre. Les concentrations mesurees dans l'air au niveau du sol varient entre 10{sup -13} et 10{sup -12} curie par metre cube. (auteur)

  18. Treatment of Radioactive Waste at Japan's Atomic Energy Research Institute; Traitement des Dechets Radioactifs a l'Institut Japonais de Recherches sur l'Energie Atomique; 041e 0411 0420 0410 0411 041e 0422 041a 0410 0420 0410 0414 ; Tratamiento de los Desechos Radiactivos en el Instituto de Investigaciones sobre Energia Atomica del Japon

    Energy Technology Data Exchange (ETDEWEB)

    Yamamoto, Yutaka [University of Toyko (Japan); Japan Atomic Energy Research Institute (Japan); Ito, Masukuni F.; Ishihara, Takehiko; Mitsuishi, Nobuo [Sadahiro Sakata, Japan Atomic Energy Research Institute (Japan)

    1960-07-01

    The paper describes the origin, nature and treatment of the radioactive wastes. The very low-level liquid waste is diluted and released to the sea, while the low- and medium-level liquid waste is treated by flocculation, evaporation and ion-exchange methods. The solid waste is collected and the combustible waste incinerated. (author) [French] Le present memoire decrit l'origine, la nature et le traitement des dechets radioactifs. Les dechets liquides de tres faible activite sont dilues et evacues dans la mer, tandis que les dechets liquides d'activite faible et moyenne sont traites par des methodes de floculation, d'evaporation et d'echange d'ions. Les dechets solides sont rassembles et les dechets combustibles sont incineres. (author) [Spanish] Los aiutores describen el origen y la naturaleza de los desechos radiactivos, asi como los metodos seguidos para su tratamiento. Los desechos liquidos de muy bajo nivel de actividad se diluyen primero y luego se descargan en el mar, en tanto que los desechos liquidos de bajo y mediano nivel se tratan mediante procedimientos de floculacion, evaporacion e intercambio ionico. Los residuos solidos se acopian y los residuos combustibles se incineran. (author) [Russian] V dokumente opisyvajutsja priroda i harakter radioaktivnyh othodov i metody ih obrabotki. Zhidkie othody ochen' nizkoj aktivnosti razbavljajutsja i otvodjatsja v morja, a zhidkie othody nizkoj i srednej aktivnosti obrabatyvajutsja metodami flokkuljacii, vyparivanija i ionnogo obmena. Tverdye othody sobirajutsja i po vozmozhnosti szhigajutsja. (author)

  19. Disposal of Low-Activity Liquid Effluents by Dilution; Elimination par Dilution d'Effluents Liquides Faiblement Radioactifs; 0423 0414 0410 041b 0414 ; Eliminacion de Efluentes Liquidos de Baja Radiactividad por Dilucion

    Energy Technology Data Exchange (ETDEWEB)

    Bovard, P.; Candillon, C. [Service de Controle des Radiations et de Genie Radioactif, Commissariat a l' Energie Atomique, Saclay (France)

    1960-07-01

    obtenus Nous avons commence en 1957 une etude evolutive de l'incidence des installations nucleaires. Cette etude embrasse la determination des niveaux - de radioactivite naturelle - de contamination artificielle afin d'en degager la part revenant aux Centres Nucleaires. Des exemples sont cites faisant appel a des zones de reference. La plus grande partie de la radioactivite artificielle semble due aux retombees radioactives; ceci n'est pas surprenant si on examine les quantites d'isotopes radioactifs rejetees jusqu'a present en France. Un certain nombre d'essais de laboratoire ont ete effectues. Ils ont contribue a preciser certains mecanismes, ont accru notre connaissance de la pollution des sites et nous ont permis d'ameliorer nos methodes de prelevement. II. Essais de laboratoire Ils ont porte: 1. sur des 'phenomenes d'adsorption analogues a ceux produits dans les rivieres au cours de la dilution des effluents: fixation sur mineraux tres divises: mica, quartz. Des radioisotopes tels que {sup 90}Sr, {sup 137}Cs, {sup 90}Y semblent se comporter fort differemment: dans les conditions moyennes de rejet, le {sup 90}Sr serait le moins adsorbe. : 2. sur la contamination du sol et des vegetaux par l'emploi de colonnes et de cubes de sol en place. Ceci nous a conduit a standardiser nos prelevements, afin de faciliter les analyses ulterieures et de comparer utilement les resultats. III. Choix du site et modalites des rejets De ce faisceau de resultats et d'etudes encore incomplets, nous essayons de degager quelques principes quant au choix des sites. Le site une fois defini, l'experience acquise permet de tirer le meilleur parti des possibilites naturelles. (author) [Spanish] Con los resultados obtenidos en Francia vigilando la radiactividad en las proximidades de las instalaciones nucleares se pueden extraer determinadas conclusiones acerca de la eleccion de los procedimientos de evacuacion. I. Resultados obtenidos Los autores iniciaron en 1957 un estudio evolutivo de las

  20. U-Th-Ra disequilibria at the Masaya (Nicaragua); Desequilibres U-Th-Ra au Masaya (Nicaragua)

    Energy Technology Data Exchange (ETDEWEB)

    Sigmarsson, O; Condomines, M [Centre de Recherches Volcanologiques, CNRS URA-10, 63 - Clermont Ferrand (France)

    1997-12-31

    {sup 238}U-{sup 230}Th-{sup 226}Ra radioactive disequilibria were measured in several basalt samples of the post-caldera flows of the Masaya volcano (Nicaragua). {sup 230}Th/{sup 232}Th ratios are from the highest known in the world (about 2.53) with {sup 230}Th/{sup 238}U ratios close to 1. These exceptionally high isotopic thorium ratios from the Masaya and other neighboring volcanoes (Conception, Cerro Negro, Momotombo) are followed by very high {sup 10}Be/{sup 9}Be ratios (60 10{sup -11} for the 1722 flow). These geochemical characteristics with {delta}{sup 18}O of typical mantle origin (5.55) suggest an influence of the subducted sediments fluids in the magma source. The age of the metasomatism ranges from 10 to 0.3 Ma. Initial {sup 226}Ra/{sup 230}Th ratios measured in four historical flows vary from 1.3 to 1.4 and are anti-correlated with the Th content. These variations are probably linked to the fractionated crystallisation of plagioclase minerals. The initial {sup 226}Ra/Ba ratio remains constant and suggests the existence of a huge stationary magmatic reservoir. This hypothesis is also confirmed by the disproportion between the SO{sub 2} quantity emitted by the volcano and by the degassing of lavas on the ground. The {sup 226}Ra excess observed in the Masaya lavas can be the result of a second stage of metasomatism which occurred less than 8000 years B.P. during partial fusion. Abstract only. (J.S.).

  1. U-Th-Ra disequilibria at the Masaya (Nicaragua); Desequilibres U-Th-Ra au Masaya (Nicaragua)

    Energy Technology Data Exchange (ETDEWEB)

    Sigmarsson, O.; Condomines, M. [Centre de Recherches Volcanologiques, CNRS URA-10, 63 - Clermont Ferrand (France)

    1996-12-31

    {sup 238}U-{sup 230}Th-{sup 226}Ra radioactive disequilibria were measured in several basalt samples of the post-caldera flows of the Masaya volcano (Nicaragua). {sup 230}Th/{sup 232}Th ratios are from the highest known in the world (about 2.53) with {sup 230}Th/{sup 238}U ratios close to 1. These exceptionally high isotopic thorium ratios from the Masaya and other neighboring volcanoes (Conception, Cerro Negro, Momotombo) are followed by very high {sup 10}Be/{sup 9}Be ratios (60 10{sup -11} for the 1722 flow). These geochemical characteristics with {delta}{sup 18}O of typical mantle origin (5.55) suggest an influence of the subducted sediments fluids in the magma source. The age of the metasomatism ranges from 10 to 0.3 Ma. Initial {sup 226}Ra/{sup 230}Th ratios measured in four historical flows vary from 1.3 to 1.4 and are anti-correlated with the Th content. These variations are probably linked to the fractionated crystallisation of plagioclase minerals. The initial {sup 226}Ra/Ba ratio remains constant and suggests the existence of a huge stationary magmatic reservoir. This hypothesis is also confirmed by the disproportion between the SO{sub 2} quantity emitted by the volcano and by the degassing of lavas on the ground. The {sup 226}Ra excess observed in the Masaya lavas can be the result of a second stage of metasomatism which occurred less than 8000 years B.P. during partial fusion. Abstract only. (J.S.).

  2. Sorption Regularities in Behaviour of Fission-Product Elements during Filtration of their Solutions through Ground; Lois de l'Absorption des Elements Radioactifs Lors du Filtrage des Solutions a Travers les Terrains; 0417 0410 041a 041e 041d 0414 ; Leyes de la Absorcion de los Elementos Radiactivos Cuando se Filtran Soluciones a Traves de las Formaciones Geologicas

    Energy Technology Data Exchange (ETDEWEB)

    Spitsyn, V. I.; Balukova, V. D.; Gromov, V. V.; Zakharov, S. I.; Zhagin, B. P.; Spiridonov, F. M.

    1960-07-01

    Research on the sorption of radioisotopes under natural conditions employing the controlled filtration process was performed. Radioisotopes were introduced into the solution as soon as filtration had become steady and the process continued for four months. Soil samples were then taken by drilling at different depths and analysed to determine their radioisotope content. Diffusion of radioisotopes was observed at depths of up to 10 m; two distinct boundaries of soil-activity decrease were ascertained: at the surface of the site and at the depth of the solution filtration front. In addition, the radiostrontium absorption by natural sorbents, principally pure minerals widely distributed in soils and subsoils, was investigated separately. The presence of calcium ions, even in small quantities, sharply reduces the degree of radiostrontium sorption. However, other conditions being equal, strontium may be absorbed to a greater extent than calcium, according to the composition of the sorbent. The field investigations of radiostrontium sorption and migration showed that when filtering radioactive solutions two possible variants have to be taken into account. In the first case the solutions are discharged into soil unaffected by any flow of ground water. In this situation the radiostrontium is retained by the soil. In the second case, the radioisotopes proceed directly into the water-bearing horizon. The radiostrontium will then migrate with the ground water flow and through the soil and this migration will be further affected by the sorption and desorption processes occurring. The experiments performed demonstrate the ease with which long-lived radioisotopes migrate under natural conditions and call attention to the need for thorough study of ground water problems in connexion with various methods of disposing of radioactive waste into ground. (author) [French] En declenchant un processus de filtration, il a ete possible d'etudier l'absorption des elements radioactifs dans

  3. Disposal of Radioactive Waste in the Subsurface of the Federal Republic of Germany: Geological and Hydro-Geological Problems; Elimination des Dechets Radioactifs dans le Sous-Sol de la Republique Federale d'Allemagne: Problemes Geologiques et Hydrogeologiques; 041f 041e 0414 ; Evacuacion de Desechos Radiactivos en el Subsuelo de la Republica Federal de Alemania Problemas Geologicos e Hidrogeologicos

    Energy Technology Data Exchange (ETDEWEB)

    Wagner, R.; Richter, W. [Bundesanstalt fuer Bodenforschung, Hannover (Germany)

    1960-07-01

    The geological and hydrogeological problems related to the subsurface disposal of radioactive wastes in the Federal Republic of Germany are outlined. Special consideration is given to the possibility of storing solid and liquid wastes in the salt-domes widespread in the north-west, and of injecting liquid waste into deep reservoirs containing briny water and located in favourable geologic structures. (author) [French] Les auteurs decrivent les problemes geologiques et hydrogeologiques que pose, dans la Republique federale d'Allemagne, l'elimination des dechets radioactifs dans le sous-sol. Ils examinent notamment la possibilite d'emmagasiner des dechets solides et liquides dans les salines, qui abondent dans la partie nord-ouest et d'injecter des dechets liquides dans de profonds reservoirs d'eau saline, situes dans des formations geologiques presentant des conditions favorables. (author) [Spanish] Los autores exponen los problemas geologicos e hidrogeologicos que plantea la evacuacion de desechos radiactivos en el subsuelo de la Republica Federal de Alemania. Examinan sobre todo la posibilidad de almacenar desechos solidos y liquidos en los domos de sal, muy abundantes en el noroeste del pais, y de inyectar desechos liquidos en depositos profundos de agua salobre situados en estructuras geologicas que presentan condiciones favorables. (author) [Russian] Privoditsja opisanie geologicheskih i gidrogeologicheskih problem, svjazannyh s podzemnym udaleniem radioaktivnyh othodov v Federal'noj Respublike Germanii. Osoboe vnimanie udeljaetsja vozmozhnosti skladirovanija tverdyh i zhidkih othodov v soljanyh kupolah, imejushhihsja v bol'shom kolichestve v severo- zapadnoj chasti Germanii, i zahoronenija zhidkih othodov v glubokie rezervuary, soderzhashhie solenye vody i raspolozhennye v podhodjashhih geologicheskih strukturah. (author)

  4. Measurement of the wear rate of cast grinding balls using radioactive tracers; Evaluation de l'usure des boulets pour concasseurs, au moyen des indicateurs radioactifs; Izmerenie skorosti iznosa litykh drobil'nykh sharov pri pomoshchi mechenykh atomov; Medicion de la velocidad de desgaste de bolas trituradoras de acero colado con ayuda de indicadores radiactivos

    Energy Technology Data Exchange (ETDEWEB)

    Keys, J D; Eichholz, G G [Department of Mines and Technical Surveys, Ottawa, ON (Canada)

    1962-01-15

    The wear rate of grinding balls used in ball mills is usually hard to determine under operational conditions and little is known-about the factors determining ball life. Radioactive tracers have been used successfully to mark cast steel balls to obtain information on their life under various operating conditions for comparison with balls of different type or composition. A batch of marked steel balls has been followed through a milling operation over several weeks and statistics on wear and loss of weight have been obtained. In the test runs cobalt-60 was added to the molten metal before casting and the balls were then observed in use at an iron mine. The radioactive batch was added to a ball mill with a normal charge of about 75 tons and the mill charge was sampled at weekly intervals to pick out active balls. These balls were inspected and weighed, and the wear rate has been calculated. This procedure has proved to be a practical way of investigating wear properties under plant operating conditions. (author) [French] Il est en general difficile de determiner le taux d'usure des boulets de broyeurs dans des conditions normales d'utilisation et l'on ne sait pas grand-chose des facteurs qui determinent la longevite des boulets. Les auteurs ont employe avec succes des indicateurs radioactifs pour marquer des boulets d'acier moule, en vue d'obtenir des indications sur leur duree dans diverses conditions de. fonctionnement et de faire une comparaison entre des boulets de type different ou de. composition differente. Ils ont suivi un lot de boulets, d'acier ainsi marques pendant une operation de broyage qui a dirre plusieurs semaines, ce qui a permis de recueillir des donnees statistiques sur leur usure et leur perte de poids. Au cours des essais, du cobalt-60 a ete ajoute au metal fondu avant le moulage des boulets. Ceux-ci ont ete ensuite maintenus en observation pendant leur emploi dans une mine de fer et une mine d'or. Le lot radioactif a ete introduit danfe un

  5. Containment of Radioactive Waste for Sea Disposal and Fisheries Off the Canadian Pacific Coast; La Mise en Recipients des Dechets Radioactifs en Vue de leur Elimination dans la Mer et la Protection des Pecheries Operant au Large de la Cote Canadienne de l'Ocean Pacifique; 0423 0414 0414 ; Confinamiento de Desechos Radiactivos para su Evacuacion en el Mar, en Relacion con las Pesquerias de la Costa Canadiense del Pacifico

    Energy Technology Data Exchange (ETDEWEB)

    Waldichuk, Michael [Fisheries Research Board of Canada Biological Station, Nanaimo, BC (Canada)

    1960-07-01

    Low-level radioactive waste consists largely of contaminated laboratory trash, larger items of equipment, animal carcasses from biological tracer experiments, active liquids, and some reactor-irradiated materials. A total of 16,288 55-gallon drums of low-level waste has been dumped off the coast of California from 1946 to 1957, inclusive. The major objectives of the criteria for US sea disposal operations have been (1) safety in handling between waste originator and disposal site, and (2) adequate sinking of wastes in the sea. There has been no requirement for integrity of container or contents at depth. Other techniques used or previously suggested for radioactive waste containment, such as canning, adsorption on clay, and integration into glass are described. In order to render a radioactive waste harmless to fish and other aquatic organisms, it must be either (1) isolated from the environment, or (2) dispersed to levels of permissible concentrations. A spherical vault of suitable engineering design, hermetically sealed and able to withstand high pressures, is proposed for low-level and intermediate-level solid waste disposal, as a means of isolating the waste from the environment. Fish may be affected by radioactive waste in their environment through: (1) direct radiation from the disposed radioactive material; (2) ingestion of food organisms containing concentrated radioisotopes; (3) irradiation by water containing radioactive ions or particles; and (4) contamination by bottom materials rich in precipitated radioisotopes. Research necessary before widespread marine disposal of radioactive waste should be permitted is suggested. (author) [French] Les dechets de faible radioactivite sont constitues surtout par des detritus contamines provenant des laboratoires, des accessoires d'assez grande dimension, des carcasses d'animaux ayant servi a des experiences biologiques avec traceurs, des liquides radioactifs et certains materiaux irradies provenant de reacteurs. De

  6. Study of the Fixation and Migration of Radioactive Cations in a Natural Ion Exchanger; Etude de la Fixation et de la Migration de Cations Radioactifs dans un Echangeur d'Ions Naturel; 0418 0417 0423 0427 0415 0414 ; Estudio de la Fijacion y de la Migracion de Cationes Radiactivos en un Cambiador Natural de Iones

    Energy Technology Data Exchange (ETDEWEB)

    Baetsle, L. [Centre d' Etudes de l' Energie Nucleaire, Mol (Belgium)

    1960-07-01

    With a view to utilizing lignite as a natural ion exchanger in the treatment of radioactive waste, a study was made of its physical and physico-chemical properties with reference to ion exchange. The distribution of Sr{sup 90} and Cs{sup 137} ions in the presence of Ca, Na and H was first examined and the equilibrium constants calculated. The kinetics and fixation of ions were then studied, and various parameters required for the calculation of ion-exchange beds were established. Study of the complex phenomenon of radioactive ion migration in the soil was started by the separate investigation of each component ionic equilibrium. (author) [French] Afin d'utiliser le lignite comme echangeur d'ions naturel dans le traitement d'eaux residuaires radioactives, uene etude a ete faite de ses proprietes physiques et physiochimiques, ayant trait a l'echange d'ions. En premier lieu on a etudie la distribution des ions {sup 90}Sr et {sup 137}Cs en presence de Ca, Na et H, et calcule les constantes d'equilibre. En second heu on a traite la cinetique de la fixation des ions, et etabli quelques parametres necessaires au calcul de hts d'echangeurs d'ions. L'etude du phenomene complexe de la migration des ions radioactifs dans le sol a ete abordee par l 'investigation separee de chacun des equilibres ioniques composants. (author) [Spanish] Con objeto de utilizar el lignito como cambiador natural de iones en el tratamiento de aguas residuales radiactivas, se han estudiado sus propiedades fisicas y fisicoquimicas en relacion con el intercambio de iones. En primer lugar, el autor ha estudiado la distribucion de los iones {sup 90}Sr y {sup 137}Cs en presencia de Ca, Na y H, y ha calculado las constantes de equilibrio. En segundo lugar ha estudiado la cinetica de la fijacion de iones y ha establecido algunos parametros necesarios para calcular los lechos de cambiadores de iones. El autor ha abordado el estudio del complejo fenomeno de la migracion de iones radiactivos en el suelo

  7. Management of Waste from the Use of Radioisotopes; Divers Aspects Resultant de l'Utilisation des Isotopes Radioactifs; 0423 0414 0410 041b 0415 041d 0418 0415 041e 0422 0425 041e 0414 ; Diversos Aspectos Relacionados con los Desechos Procedentes del Empleo de Radioisotopos

    Energy Technology Data Exchange (ETDEWEB)

    Rogers, Lester R. [Radiation Safety Branch, Division of Licensing and Regulation, United States Atomic Energy Commission (United States)

    1960-07-01

    The author examines the origin and nature of radioactive waste generated in the use of radioisotopes in industry, medicine, agriculture and research and studies the relationship between types, quantities and uses of radioisotopes and disposal of the radioactive waste generated in their use. He also discusses the methods used for the disposal of such waste under the licensing controls of the United States Atomic Energy Commission. These methods include: 1. The controlled discharge of low concentrations of effluents into streams and into the atmosphere; 2. Controlled release of small quantities of soluble or readily dispersible waste products into sanitary sewage systems; 3. Burial, under controlled conditions, of small quantities of waste in the soil ; 4. Return to AEC installations of radioactive waste for storage or land burial ; 5. Treatment by incineration; and 6. Disposal of packaged waste at sea. The paper reviews the criteria and regulatory requirements applicable to cach method of disposal to accomplish the objective of preventing the waste from entering the food chain of man in hazardous quantities, or of adversely affecting the use of the environment by man. It goes on to discuss the limitations on the types, quantities, and methods of disposal for which private concerns can be licensed due to long-term responsibility for maintenance of burial grounds or storage facilities. (author) [French] L'auteur se propose d'examiner l'origine et la nature des dechets radioactifs resultant de l'utflisation des radioisotopes dans l'industrie, la medecine, l'agriculture et dans les laboratoires de recherche, et d'etudier les rapports qui existent entre les types, les quantites et les utilisations des radioisotopes, d'une part, et les dechets de leur production, d'autre part. Il etudie aussi les methodes utilisees pour l'elimination de ces dechets conformement aux mesures de controle appliquees par la Commission de l'energie atomique des Etats-Unis. Les methodes

  8. The Hydrographical Features of the Baltic Sea and the Disposal of Radioactive Wastes; L'Hydrographie de la Mer Baltique et l'Evacuation des Dechets Radioactifs; 0413 0418 0414 0420 041e 0413 0420 0414 ; Caracteristicas Hidrograficas del Mar Baltico en Relacion con la Evacuacion de Desechos Radiactivos

    Energy Technology Data Exchange (ETDEWEB)

    Hela, Ilmo [Institute of Marine Research Helsinki (Finland)

    1960-07-01

    The purpose of the paper is to point out a few hydrographical features of the Baltic Sea, which make this sea, in reference to the disposal of radioactive wastes, different from any oceanic region. The seas can be divided, in reference to the practical problem of the disposal of radionuclides, into the following zones: (1) harbours, (2) fairways leading into harbours, (3) outer continental shelf and (4) the open sea. There, is no open sea, in the above sense, in the Baltic Sea. In addition, the validity of the rules recommended for the above zones, must be carefully checked through further hydrographical studies, since: (1) the whole Baltic is, in a sense, an estuary, with a sill-depth of only 18 metres in the Danish Sounds, (2) the mixing in the Baltic Sea is much more restricted than in the oceans, since the Baltic is rich in islands, brackish, heavily stratified, practically tideless, in winter partly covered with ice, and has a limited fetch of wind and only slowly moving permanent currents. In the paper reference is made to all these factors which diminish the turbulent diffusion, both vertical and horizontal. For the evaluation of the advection and turbulent (eddy) diffusion, both in the upper water layers and at the bottom, synoptic observations of current velocity and salinity at a number of points in several regions of the Baltic Sea and under different weather conditions are needed. (author) [French] Le memoire a pour but d'exposer certains traits de l'hydrographie de la mer Baltique qui, du point de vue de l'evacuation des dechets radioactifs, la distinguent de toute region oceanique. Pour l'etude des problemes pratiques poses par l'evacuation des dechets radioactifs, on peut repartir la mer en quatre zones: 1) les ports, 2) les chenaux d'acces aux ports, 3) le plateau continental, 4) la haute mer. Dans ce sens, il n'y a pas de haute mer dans la Baltique. En outre, la validite des reglements recommandes pour les zones precitees doit faire l'objet d

  9. New Research Required in Support of Radioactive Waste Disposal; Recherches Nouvelles Necessitees par le Probleme de l'Elimination des Dechets Radioactifs; 041d 0415 041e 0411 0425 041e 0414 ; Nuevas Investigaciones Necesarias para la Evacuacion de Desechos Radiactivos

    Energy Technology Data Exchange (ETDEWEB)

    Schaefer, Milner B. [Inter-American Tropical Tuna Commission, Scripps Institution of Oceanography, La Jolla, CA (United States)

    1960-07-01

    foraines typiques, sur les processus de diffusion et de sedimentation dans les eaux proches du rivage et sur le passage des elements radioactifs tout le long de la chaine alimentaire dans cette partie de la mer. Il faut entreprendre des recherches pour delimiter les zones de peche presentes et eventuelles et les zones ou la peche ne se fait pas, en procedant a des etudes fondamentales sur la productivite biologique ou en recourant a d'autres moyens. Des etudes sont egalement necessaires pour determiner les taux de transfert de matieres radioactives entre les diverses zones par amenee hori-zontale et par diffusion turbulente, les taux de dilution par diffusion, sedimentation et transport vertical, et les taux d'entrainement et de transfert par les organismes. Une recherche s'impose en ce qui concerne les moyens efficaces de controle des zones d'evacuation des dechets. Certains organismes sont capables de concentrer selectivement des elements determines ;1 cette capacite constitue une base economique eventuelle pour le controle des dechets radioactifs existant dans la mer a des concentrations extremement faibles. Des propositions precises de recherche ont ete recemment mises au point par plusieurs groupes d'oceanographes aux Etats-Unis. Ces propositions ont ete resumees en meme temps que les estimations de. depenses y afferentes. (author) [Spanish] Numerosos son los procesos fisicos, quimicos y biologicos que influyen en la forma en que las sustancias radiactivas se distribuyen y vuelven al hombre. Entre ellos figuran la conveccion vertical y horizontal; la difusion turbulenta; la precipitacion y sedimentacion; la captacion, concentracion y transporte de los materiales radiactivos por organismos, y su paso al hombre por ingestion de alimentos de origen marino. Hay que estudiar urgentemente las caracteristicas del flujo y reflujo de las aguas en puertos tipicos, estuarios y aguas costeras abiertas ; los procesos de difusion y sedimentacion en las aguas costeras, y el paso de

  10. Use of radioactive tracers in studying the transport of solids in watercourses; Emploi de traceurs radioactifs pour l'etude du transport solide dans les cours d'eau; Ispol'zovanie radioaktivnykh indikatorov dlya izucheniya peremeshcheniya tverdykh chastits v vodnykh potokakh; Empleo de indicadores radiactivos para el estudio del transporte de solidos en las corrientes de agua

    Energy Technology Data Exchange (ETDEWEB)

    Courtois, G [Centre d' Etudes Nucleaires de Saclay (France); Jaeery, P; Heuzel, M [Laboratoire National d' Hydraulique de Chatou (France)

    1962-01-15

    The National Hydraulics Laboratory which, in collaboration with the Saclay Nuclear Research Centre, has for several years been devising equipment and techniques for the study of sediment movements by the radioactive tracer method, is now endeavouring to develop a really quantitative method of research. Two river experiments were recently made, the first a study of shingle drifting in the Rhone, the second a study of sand movement in the Niger. The latter experiment was matched by identical experiments carried out on a scale model of the River Niger which the Chatou Laboratory has at its disposal. The experiments used Mn{sup 56} and Na{sup 24} radiation obtained by direct activation of crushed apricot stone, this representing in the scale model the natural sediment of the Niger bed. The Chatou Laboratory and the Saclay Nuclear Study Centre are at present both devoting attention to the application of radioactive tracers in studies with scale models, with the twin aims of: (a) Obtaining a single research tool for use under natural conditions and with scale models in order to gauge the trustworthiness of the model, in the calibration testing stage; (b) Taking advantage of the facilities for direct observation and measurement offered by scale models in order to study prospects of improving the tracer method, with a view particularly to securing quantitative data. (author) [French] Le Laboratoire national d'hydraulique, qui depuis quelques annees a developpe, en collaboration avec le Centre d'etudes nucleaires de Saclay, les appareillages et les techniques d'etudes des mouvements de sediments par la methode des traceurs radioactifs, s'efforce actuellement de mettre au point un moyen d'investigation veritablement quantitatif. Deux experiences ont ete effectuees recemment en riviere, la premiere a ete consacree a l'etude du charriage des galets dans le Rhone, l'autre a l'etude des transports de sables dans le Niger. Cette derniere experience a ete doublee d

  11. Disposal of the radioactive effluents at the 'Commissariat a l'Energie Atomique'. Treatment leading to evacuation into a river; Probleme du rejet des residus radioactifs liquides au CEA. Traitements aboutissant a des rejets en riviere

    Energy Technology Data Exchange (ETDEWEB)

    Duhamel; Menoux; Candillon [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    to find out in loaded water, 10) Impot elements other than Sr{sup 90} are also studied. (author) [French] Le probleme du traitement des residus radioactifs liquides au CEA est envisage sous l'angle du rejet ultime en riviere dans des conditions optima permettant de satisfaire aux Normes de la protection. 2) A Saclay, ou l'on ne dispose que d'un etang ou l'eau ne se renouvelle pas, les liquides epures sont envoyes par camion citerne a Fontenay-aux-Roses, ou ils sont deverses provisoirement - dans les egouts - en attendant qu'un point de rejet en Seine ait ete determine. 3) Au Bouchet, les eaux residuaires de l'Usine de traitement de minerais d'urano-thorianite devront etre traitees en deux temps de facon a separer le radium dans une premiere phase, ce qui facilitera l'epuration au cours de la deuxieme phase. 4) En vue des futurs rejets a Marcoule, une etude a ete conduite a Saclay, sur des effluents synthetiques - type Marcoule - ayant pour but de mettre au point des procedes d'elimination selective du Sr d'une part, du Cs d'autre part, par coprecipitation. 5) Dans le cas general du rejet ultime en riviere, les problemes suivants sont successivement envisages: - predilution entre les bassins de stockage des eaux epurees et le fleuve; - mode d'injection dans le fleuve; - dilution dans le fleuve (etude prealable par traceurs); - evolution de l'activite dans les eaux du fleuve (adsorption par les organismes inertes ou vivants, contamination des berges); - incidence sur le choix d'un site; - dilution isotopique. 6) Ce dernier probleme est specialement detaille. 7) La teneur de l'eau en un element donne conditionne la dilution isotopique de son isotope radioactif. L'analyse decelant une carence, il est possible d'y suppleer par des rejets d'isotope stable. 8) Cette methode conduit en certains cas a des analyses delicates (en particulier dans le cas du {sup 90}Sr), la teneur en isotope

  12. Biological Aspects of Disposal of Radioactive Wastes in Marine Environments; Aspects Biologiques de l'Elimination des Dechets Radioactifs dans le Milieu Marin; 0411 0418 041e 041b 041e 0413 0418 0427 0414 ; Aspectos Biologicos de la Evacuacion de Desechos Radiactivos en Medios Marinos

    Energy Technology Data Exchange (ETDEWEB)

    Chipman, Walter A. [United States Bureau of Commercial Fisheries (United States)

    1960-07-01

    Disposal of radioactive wastes in marine waters allows for an accumulation of radioactivity by marine life. Such an accumulation by seafood organisms might affect their utilization or availability. Laboratory studies of accumulation of important radionuclides present in different wastes by marine plankton, benthic invertebrates and various species of marine fish and of the biological effects of accumulated radioactivity on these forms are being conducted at Beaufort, North Carolina, as a co-operative activity of the US Atomic Energy Commission and the US Bureau of Commercial Fisheries. These investigations help provide essential information for the formulation of waste disposal practices and the safe operation of nuclear-powered ships in coastal waters. They are useful also in the development of monitoring programmes designed to detect and evaluate hazards from accidental pollution of inshore waters. (author) [French] L'elimination des dechets radioactifs dans la mer fait la part d'une accumulation d'activite dans les organismes vivant dans ce milieu. Cette accumulation dans les produits comestibles de la mer peut nuire a leur utilisation ou a leur abondance. A Beaufort (Caroline du Nord), les laboratoires du Bureau des pecheries commerciales des Etats-Unis font, en collaboration avec la Commission de l'energie atomique des Etats-Unis, des etudes sur l'accumulation de radionuclides importants provenant de differents dechets, dans le plancton marin, les invertebres benthiques et les differentes especes de poissons, ainsi que sur les effets biologiques de la radioactivite ainsi accumulee. Ces recherches permettent d'obtenir des donnees de base pour l'elaboration de methodes d'elimination des dechets et l'exploitation en toute securite des navires a propulsion nucleaire dans les eaux cotieres. Ces etudes sont egalemeut utiles pour l'etablissement de programmes de controle ayant pour objet la detection et l'evaluation des dangers que presente la pollution accidentelle

  13. Technical and Administrative Considerations in the Management of Radioactive Wastes; Considerations Techniques et Administratives Relatives au Traitement des Dechets Radioactifs; 0422 0415 0425 041d 0418 0427 0415 0421 041a 0414 ; Aspectos Tecnicos y Administrativos de la Manipulacion de Desechos Radiactivos

    Energy Technology Data Exchange (ETDEWEB)

    Wolman, Abel [Johns Hopkins University, Baltimore, MD (United States); Division of Reactor Development, U.S. Atomic Energy Commission, Washington, DC (United States); Lieberman, Joseph A. [Environmental and Sanitary Engineering Branch, Division of Reactor Development, U.S. Atomic Energy Commission, Washington, DC (United States)

    1960-07-01

    administratifs du traitement des dechets en rattachant cette analyse aux mesures qu'il pourrait etre necessaire de prendre dans l'avenir pour assurer un traitement et un controle efficaces, sur le plan administratif et juridique, des effluents radioactifs resultant de la production d'energie atomique. Les auteurs repartissent tout d'abord en de larges categories les differentes sortes de dechets pour bien souligner que le probleme de leur traitement presente de multiples aspects et qu'on ne saurait en donner une solution unique. Ils examinent rapidement le role des differents milieux dans le choix des methodes de traitement des dechets et definissent les procedes fondamentaux de controle (dilution et dispersion, concentration et confinement). Les auteurs distinguent entre les normes fondamentales de protection radiologique et les criteres de fonctionnement qui doivent etre fixes pour realiser le controle des effluents de facon a veiller a ce que les normes fondamentales soient respectees. Les auteurs examinent les progres realises en matiere de normes et criteres ainsi que l'application de ceux-ci dans l'etablissement de reglements de sante et de securite et la mise au point de procedures administratives et juridiques. A cet egard, ils signalent les avantages que presente, du point de vue de l'opinion publique et du travail administratif, l'utilisation la plus large des textes legislatifs et des procedures administratives dans les services deja crees aux divers echelons de l'autorite. Malgre l'importance des depenses qu'entrainent le traitement et l'elimination des dechets radioactifs, le cout par unite d'energie electrique produite ne represente qu'une partie relativement restreinte du cout total par unite d'energie. Les auteurs indiquent d'autres facteurs economiques qui jouent un role dans la manipulation et l'elimination des dechets, notamment en fonction de l'emplacement de l'usine et du point d'evacuation. En outre, ils examinent d'autres aspects du traitement des dechets

  14. The Permanent Disposal of Highly Radioactive Wastes by Incorporation into Glass; Elimination Permanente de Dechets Hautement Radioactifs par Incorporation dans le Verre; 041e 041a 041e 041d 0427 0414 ; La Evacuacion Permanente de Desechos de Elevada Radiactividad Incorporandolos en Vidrio

    Energy Technology Data Exchange (ETDEWEB)

    Watson, L. C.; Aikin, A. M.; Bancroft, A. I. [Atomic Energy of Canada Ltd. (Canada)

    1960-07-01

    Development of a process for the incorporation of the high-level wastes from chemical processing operations into glass for permanent disposal has continued at Chalk River. The process has been demonstrated by making glass containing up to 50 curies of five- to six-year old mixed fission products per kg. The operation was batch wise, on a scale of four kg per batch. These operations showed that the fission products could be incorporated into glass safely and conveniently. Consideration of the many problems involved in the permanent storage or disposal of the highly radioactive glass has resulted in the conclusion that it should be buried in the ground or stored in artificial vaults. In such conditions, the disposal may always be-subjected to further control if required. If disposal is made directly to the ground, the principal method by which fission products can be released to the environment is by leaching from the glass into water. It is therefore considered important to know the rate at which fission products will be dispersed by this mechanism. Considerable data on leaching by water have been obtained in the laboratory. It has been found that the rates of release depend on the composition of the glass. For all the compositions tested the measurements showed that the rate of leaching of fission products from the glass decreased with time. After several months in water the rate of release of several compositions was about 10{sup -4} per cent per year from a two kg hemisphere of glass. The data obtained have been used to estimate the release of fission products from glass containing the large quantities of fission products which will accumulate from operation of power reactors. (author) [French] On poursuit a Chalk River les travaux de mise au point d'un procede permettant d'incorporer dans le verre, pour elimination permanente, des dechets hautement radioactifs provenant d'operations de traitement chimique! Aux fins de demonstration du procede, on a fabrique du

  15. The use of radioactive inserts in the study of metal deformation during tube-making processes; Emploi de fils metalliques radioactifs pour l'etude des deformations des metaux pendant la fabrication de tubes; Ispol'zovanie radioaktivnykh vtulok dlya izucheniya deformatsii metallov pri protsesse izgotovleniya trub; Empleo de insertos radiactivos en el estudio de la deformacion de los metales durante la fabricacion de tubos

    Energy Technology Data Exchange (ETDEWEB)

    Davison, W H.T. [Tube Investments Research Laboratories, Cambridge (United Kingdom)

    1962-01-15

    This paper reports on the use of radioactive inserts in studying the deformation of steel in hot rotary piercing for tube making. Iron or steel wires are activated in the pile, inserted in tubes drilled in iron or steel billets, which are then processed under normal production conditions. Careful monitoring shows that the radiation exposures and contamination of the plant are quite negligible. On cooling, the billets are scanned in the laboratory, using a collimated scintillationcounter mounted normal to the surface of the pierced billet, and isodose curves show the shape of the deformed insert normal to the tube surface. A similar scan of a section normal to the axis of the tube gives a second plot; from a combination of the two plots, a three-dimensional picture is obtained. Some results are quoted, but the main emphasis of the paper is on the experimental technique, which has quite general applicability to metal deformation studies. The insert must be located within a millimeter or thereabouts, for which a higher resolution is required than is normal in medical scanning techniques. The problems of achieving this are discussed in terms of {gamma}-energy, collimator design and energy discrimination. (author) [French] Le present memoire traite de l'emploi de fils metalliques radioactifs pour l'etude de la deformation de l'acier durant le forage rotatif a chaud en vue de la fabrication des tubes. Des fils de fer ou d'acier sont actives dans un reacteur et places dans des cavites tabulaires menagees a l'interieur de billettes de fer ou d'acier que l'on transforme ensuite dans les conditions de fabrication normales. Un controle radiologique minutieux montre que les dangers d'irradiation et de contamination dans l'usine sont pratiquement negligeables. Apres refroidissement, les billettes sont examinees en laboratoire au moyen d'un compteur a scintillations avec collimateur de faible ouverture, monte de facon que l'axe soit perpendiculaire a la surface de la billette

  16. Contributions of Geology to the Problem of Radioactive Waste Disposal; Contributions de la Geologie au Probleme de l'Elimination des Dechets Radioactifs; 0412 041a 041b 0410 0414 0413 0415 041e 0414 ; Contribucion de la Geologia a la Resolucion de los Problemas que Plantea la Evacuacion de Desechos Radiactivos

    Energy Technology Data Exchange (ETDEWEB)

    Nace, R. L. [Water Resources Division, Geological Survey, Washington 25, DC (United States)

    1960-07-01

    aimed directly at waste disposal problems. (author) [French] La terre est l'objet des etudes geologiques; or, les dechets radioactifs ne peuvent etre disperses ou entreposes que dans ou sur la terre. En ce sens, les problemes relatifs a l'elimination des dechets radioactifs sont avant tout d'ordre geologique. Les Etats-Unis ont applique largement les connaissances geologiques accumulees et certains principes bien etablis aux problemes de l'elimination; le caractere exceptionnel de ces problemes a necessite des recherches qui ont permis d'approfondir considerablement nos connaissances dans des domaines particuliers de la geologie. De nombreux travaux ont porte sur l'etude d'emplacements pour installations nucleaires. Cette etude comporte l'analyse et l'evaluation de facteurs geologiques, topographiques, hydrologiques, geochimiques et sismiques. On a analyse aussi par region les caracteristiques d'ensemble des grandes divisions naturelles des Etats-Unis et les incidences de ces caracteristiques sur l'entreposage et l'elimination des dechets. Parmi les problemes speciaux, on etudie comment se comportent ou pourraient se comporter des dechets ordinaires dans des milieux geologiques determines. D'autres etudes portent sur l'utilisation eventuelle de cavites syncli- nales, de failles stratigraphiques, de bancs de sel et de domes de sel pour l'entreposage et l'isolement des dechets de haute activite. De nombreuses etudes generales et quelques etudes de detail ont ete entreprises sur la radiometrie du milieu ambiant. L'eau naturelle est le facteur critique dans l'elimination des dechets ; on a donc etudie certains processus naturels par lesquels on peut purifier l'eau ou en modifier la composition chimique. Les etudes consacrees aux problemes suivants ont donne des resultats interessants : processus de dispersion et de diffusion dans les eaux souterraines et dans les eaux de surface ; vitesse de circulation des contaminants dans les cours d'eau ; mecanisme d'ecoulement des eaux

  17. Contribution to the geochemical knowledge of the uranium-radium and thorium families in the southern Vosges. Applications of some results in the prospecting of uranium deposits; Contribution a la connaissance geochimique des familles uranium-radium et du thorium dans les Vosges meridionales. Application de certains resultats en prospection des gisements d'uranium

    Energy Technology Data Exchange (ETDEWEB)

    Jurain, G [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1962-07-01

    This work's aim is to lead to a more accurate knowledge of the geochemistry of the Uranium-Radium and Thorium families in the Southern Vosges and to apply some of the results to the prospecting of uraniferous deposits: It has been showed: a bond between Calcium-Magnesium and Uranium-Thorium in the calco-alkaline granites. The host minerals of Uranium and Thorium are hornblende, biotite, titanite and epidote. a concentration of Uranium, at present time with secular disequilibrium in a thermal zone where the satellite mineralizations form an epithermal paragenesis. a disequilibrium of the Uranium-Radium family in the supergene minerals of the lead (phosphate and vanadate) showing the present circulations of Uranium. a bond between the radon grade of the spring waters and Uranium-Radium of the rocks. Such a relation allow to realize a prospecting method based on the determination of radioactive gases from the cold spring-waters of a common country. (author) [French] L'etude presentee ici a pour but de conduire a une connaissance plus precise de la geochimie des familles Uranium-Radium et Thorium dans les Vosges meridionales et d'appliquer certains resultats a la prospection des gites uraniferes. Il a ete mis en evidence: une liaison Calcium-Magnesium et Uranium-Thorium dans des granites calco-alcalins. Les mineraux hotes de l'Uranium et du Thorium sont: la hornblende, la biotite, le sphene, l'epidote. une concentration actuelle de l'Uranium en desequilibre seculaire dans une zone thermale ou les mineralisations satellites constituent une paragenese epithermale. un desequilibre de la famille Uranium-Radium dans des mineraux supergenes du plomb (phosphates et vanadates) prouvant les circulations actuelles de l'Uranium. une liaison entre la teneur en Radon des eaux de sources et celle en Uranium-Radium des roches. Une telle liaison permet de realiser une methode de prospection fondee sur le dosage du gaz radioactif des eaux de sources froides d'une region quelconque

  18. Geochemical behaviour of uranium in the cycle of alteration; Comportement geochimique de l'uranium dans le cycle d'alteration

    Energy Technology Data Exchange (ETDEWEB)

    Chervet, J; Coulomb, R [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires; Soudan, P [Centre d' Etude de Lalumine, Compagnie Pechiney (France)

    1958-07-01

    examinons l'influence de la presence de gisements d'uranium sur la composition de ces eaux. d) Nous observons l'amplitude des phenomenes qui limitent les dispersions: fixations, precipitations, etc., et le comportement de la vegetation dans les zones uraniferes. e) Enfin, l'antagonisme: alteration chimique - equilibre radioactif provoque un profond desequilibre dans les materiaux alteres. Nous essayons d'utiliser la mesure de ce desequilibre pour l'explication de mecanismes geochimiques. (auteur)

  19. Contribution to the geochemical knowledge of the uranium-radium and thorium families in the southern Vosges. Applications of some results in the prospecting of uranium deposits; Contribution a la connaissance geochimique des familles uranium-radium et du thorium dans les Vosges meridionales. Application de certains resultats en prospection des gisements d'uranium

    Energy Technology Data Exchange (ETDEWEB)

    Jurain, G. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1962-07-01

    This work's aim is to lead to a more accurate knowledge of the geochemistry of the Uranium-Radium and Thorium families in the Southern Vosges and to apply some of the results to the prospecting of uraniferous deposits: It has been showed: a bond between Calcium-Magnesium and Uranium-Thorium in the calco-alkaline granites. The host minerals of Uranium and Thorium are hornblende, biotite, titanite and epidote. a concentration of Uranium, at present time with secular disequilibrium in a thermal zone where the satellite mineralizations form an epithermal paragenesis. a disequilibrium of the Uranium-Radium family in the supergene minerals of the lead (phosphate and vanadate) showing the present circulations of Uranium. a bond between the radon grade of the spring waters and Uranium-Radium of the rocks. Such a relation allow to realize a prospecting method based on the determination of radioactive gases from the cold spring-waters of a common country. (author) [French] L'etude presentee ici a pour but de conduire a une connaissance plus precise de la geochimie des familles Uranium-Radium et Thorium dans les Vosges meridionales et d'appliquer certains resultats a la prospection des gites uraniferes. Il a ete mis en evidence: une liaison Calcium-Magnesium et Uranium-Thorium dans des granites calco-alcalins. Les mineraux hotes de l'Uranium et du Thorium sont: la hornblende, la biotite, le sphene, l'epidote. une concentration actuelle de l'Uranium en desequilibre seculaire dans une zone thermale ou les mineralisations satellites constituent une paragenese epithermale. un desequilibre de la famille Uranium-Radium dans des mineraux supergenes du plomb (phosphates et vanadates) prouvant les circulations actuelles de l'Uranium. une liaison entre la teneur en Radon des eaux de sources et celle en Uranium-Radium des roches. Une telle liaison permet de realiser une methode de prospection fondee sur le dosage du gaz radioactif des eaux de sources

  20. Modeling and numerical analysis of non-equilibrium two-phase flows; Modelisation et analyse numerique des ecoulements diphasiques en desequilibre

    Energy Technology Data Exchange (ETDEWEB)

    Rascle, P.; El Amine, K. [Electricite de France (EDF), Direction des Etudes et Recherches, 92 - Clamart (France)

    1997-12-31

    We are interested in the numerical approximation of two-fluid models of nonequilibrium two-phase flows described by six balance equations. We introduce an original splitting technique of the system of equations. This technique is derived in a way such that single phase Riemann solvers may be used: moreover, it allows a straightforward extension to various and detailed exchange source terms. The properties of the fluids are first approached by state equations of ideal gas type and then extended to real fluids. For the construction of numerical schemes , the hyperbolicity of the full system is not necessary. When based on suitable kinetic unwind schemes, the algorithm can compute flow regimes evolving from mixture to single phase flows and vice versa. The whole scheme preserves the physical features of all the variables which remain in the set of physical states. Several stiff numerical tests, such as phase separation and phase transition are displayed in order to highlight the efficiency of the proposed method. The document is a PhD thesis divided in 6 chapters and two annexes. They are entitled: 1. - Introduction (in French), 2. - Two-phase flow, modelling and hyperbolicity (in French), 3. - A numerical method using upwind schemes for the resolution of two-phase flows without exchange terms (in English), 4. - A numerical scheme for one-phase flow of real fluids (in English), 5. - An upwind numerical for non-equilibrium two-phase flows (in English), 6. - The treatment of boundary conditions (in English), A.1. The Perthame scheme (in English) and A.2. The Roe scheme (in English). 136 refs. This document represents a PhD thesis in the speciality Applied Mathematics presented par Khalid El Amine to the Universite Paris 6.

  1. Management of radioactive wastes; Gestion des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    The law from December 30, 1991, precisely defines 3 axes of researches for the management of high level and long-lived radioactive wastes: separation/transmutation, surface storage and underground disposal. A global evaluation report about these researches is to be supplied in 2006 by the French government to the Parliament. A first synthesis of the knowledge gained after 14 years of research has led the national commission of the public debate (CNDP) to organize a national debate about the general options of management of high-level and long-lived radioactive wastes before the 2006 date line. The debate comprises 4 public hearings (September 2005: Bar-le-Duc, Saint-Dizier, Pont-du-Gard, Cherbourg), 12 round-tables (October and November 2005: Paris, Joinville, Caen, Nancy, Marseille), a synthesis meeting (December 2005, Dunkerque) and a closing meeting (January 2006, Lyon). This document is the synthesis of the round table debates which took place at Joinville, i.e. in the same area as the Bure underground laboratory of Meuse/Haute-Marne. Therefore, the discussion focuses more on the local impacts of the setting up of a waste disposal facility (environmental aspects, employment, economic development). (J.S.)

  2. Exotic nuclei and radioactive beams; Noyaux exotiques et faisceaux radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Chomaz, P.

    1996-12-31

    The Nuclei called exotic are all the nuclei that it is necessary to recreate in laboratory to study them. Their life time is too short -in relation to earth age- for it remains enough on earth. The researchers are going to have at their s disposal at GANIL (Caen) with the S.P.I.R.A.L. project, exotic nuclei beams and will study new kinds of nuclear reactions to better understand the atom nucleus. (N.C.). 2 refs., 9 figs.

  3. National inventory of radioactive wastes; Inventaire national des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-31

    There are in France 1064 sites corresponding to radioactive waste holders that appear in this radioactive waste inventory. We find the eighteen sites of E.D.F. nuclear power plants, The Cogema mine sites, the Cogema reprocessing plants, The Cea storages, the different factories and enterprises of nuclear industry, the sites of non nuclear industry, the Andra centers, decommissioned installations, disposals with low level radioactive wastes, sealed sources distributors, national defence. (N.C.). 16 refs.

  4. National inventory of radioactive wastes; Inventaire national des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-12-31

    There are in France 1064 sites corresponding to radioactive waste holders that appear in this radioactive waste inventory. We find the eighteen sites of E.D.F. nuclear power plants, The Cogema mine sites, the Cogema reprocessing plants, The Cea storages, the different factories and enterprises of nuclear industry, the sites of non nuclear industry, the Andra centers, decommissioned installations, disposals with low level radioactive wastes, sealed sources distributors, national defence. (N.C.). 16 refs.

  5. The management of radioactive wastes; La gestion des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-12-31

    This educative booklet describes the role and missions of the ANDRA, the French national agency for the management of radioactive wastes, and the different aspects of the management of radioactive wastes: goal, national inventory, classification, transport (organisation, regulation, safety), drumming, labelling, surface storage of short life wastes, environmental control, management of long life wastes (composition, research, legal aspects) and the underground research laboratories (description, public information, projects, schedules). (J.S.)

  6. Solidification of Radioactive Waste Solutions; Solidification des Effluents Radioactifs; 041e 0422 0412 0415 0420 0416 0414 0415 041d 0418 0415 0420 0410 0414 0418 041e 0410 041a 0422 0418 0412 041d 042b 0425 0421 0411 0420 041e 0421 041d 042b 0425 0420 0410 0421 0422 0412 041e 0420 041e 0412 ; Solidificacion de Efluentes Radiactivos

    Energy Technology Data Exchange (ETDEWEB)

    Brezhneva, N. E.; Golovanov, Ju. N.; Oziraner, S. N.; Eremin, A. A.; Rozanova, V. N.

    1963-02-15

    This paper sets out the results of experimental development of a method for the solidifaction of radioactive waste solutions, based on the drying and vitrification of precipitates of iron-hydroxide obtained by settling from radioactive solutions. The solidification system is based on the principle of maximum reduction of the waste off-gases after removal of the aerosols and volatile radioactive components. The authors established optimum conditions to obtain a chemically stable glass and succeeded in lowering the temperature for the melting of the glass by modifying the fluxes added. An appreciable drop in the chemical stability of the glass was noted when it was stored for a long time at temperatures above 300 Degree-Sign - 350 Degree-Sign C. The authors studied the leachability of radiocaesium from the glass. They also investigated the volatility of radiocaesium and radio ruthenium in the course of drying and melting and showed that in an atmosphere of carbonic acid gas the volatility of ruthenium completely disappears. Hie volatility of radiocaesium in appreciable quantities becomes noticeable at temperatures above 700 Degree-Sign C and increases as the temperature rises. It is shown that radiocaesium condenses in the drainage tubes at temperatures below 400 Degree-Sign C and is easily washed off by weak solutions of nitric acid and water. Calculations of the heat release from radioactive glass show that the radius of globular glass castings from high-activity materials (10 c/g) must not exceed 25 cm. The paper includes the flowsheet for a process for the drying and vitrification of radioactive sludge by means of a gas- and heat-remover, together with details of the apparatus required. (author) [French] Les auteurs exposent les resultats des recherches qu'ils ont faites, dans leur laboratoire, pour mettre au point une methode de solidification des effluents radioactifs, fondee sur la dessiccation et la vitrification de l'hydroxyde de fer, obtenu par

  7. The Practice of Waste Disposal in the United Kingdom Atomic Energy Authority; Methodes Employees par l'Atomic Energy Authority du Royaume-Uni pour Eliminer les Dechets Radioactifs; 041f 041e 0420 042f 0414 041e 041a 0423 0414 ; Sistemas de Evacuacion de Desechos en la United Kingdom Atomic Energy Authority

    Energy Technology Data Exchange (ETDEWEB)

    Dunster, H. J.; Wix, L. F.U. [United Kingdom Atomic Energy Authority, Health and Safety Branch (United Kingdom)

    1960-07-01

    The United Kingdom Atomic Energy Authority operates establishments in locations ranging from the South of England to the North coast of Scotland. The functions of these establishments include the production and processing of nuclear fuels, the production of electricity and isotopes for commercial sale, the development of new types of reactors and the conduct of research in all the associated fields. The Authority therefore has a wide variety of wastes to deal with and they arise in a number of different places. The main high-activity wastes, both liquid and solid, are stored in special tanks and containers, while the low-activity large-volume liquid wastes are released in carefully controlled amounts to the sea or to rivers. Low-and medium- activity solid wastes are buried in selected areas where there will be no interference with water supplies, or sunk on to the sea bed. The paper summarizes the methods in use and gives typical quantities of liquid and solid waste arising annually for disposal by the various methods. (author) [French] Les divers etablissements de VAtomic Energy Authority du Royaume-Uni sont echelonnes entre le sud de l'Angleterre et la cote septentrionale de l'Ecosse. Ces etablissements sont notamment charges de la fabrication et du traitement des combustibles nucleaires, de la production d'electricite et de la production d'isotopes a des fins commerciales, de la mise au point de nouveaux modeles de reacteurs et des recherches effectuees dans tous les domaines connexes. L' Atomic Energy Authority doit donc proceder, en plusieurs points du territoire, a l'elimination de toute une serie de dechets radioactifs d'origines diverses. Les principaux dechets, liquides et solides, a radioactivite elevee sont enfermes dans des reservoirs et recipients speciaux, tandis que les volumineux dechets liquides a faible radioactivite sont evacues, par quantites soigneusement controlees, dans la mer ou les cours d'eau. Les dechets solides, de radioactivite faible

  8. The Application of Existing Oceanographic Knowledge to the Problem of Radioactive Waste Disposal into the Sea; Applicationdes Connaissances Oceanographiques Actuelles au Probleme de l'Elimination de Dechets Radioactifs dans la Mer; 0418 0421 041f 0414 ; Aplicacion de los Conocimientos Oceanograficos Actuales al Problema de la Evacuacion de Desechos Radiactivos en el Mar

    Energy Technology Data Exchange (ETDEWEB)

    Pritchard, D. W. [Johns Hopkins University, Baltimore, MD (United States)

    1960-07-01

    quantites assez importantes de dechets emballes (de l'ordre de plusieurs megacuries par an) sans compromettre l'utilisation par l'homme des produits de la mer. On pourrait eliminer sans danger sur le plateau continental des dechets emballes de faible activite, de l'ordre de plusieurs centaines de curies par an et par lieu d'evacuation. Les navires a propulsion nucleaire peuvent decharger sans trop de risques dans les couches superficielles de la haute mer plusieurs centaines de curies avec les matieres echangeuses d'ions usees. L'auteur etudie en particulier J'influence que peut avoir sur les milieux voisins des rivages et des estuaires l'exploitation de navires a propulsion nucleaire. La troisieme partie du memoire contient l'expose succinct de certaines recherches oceanographiques faites actuellement aux Etats-Unis, et qui peuvent eclairer le probleme de l'elimination des dechets radioactifs. (author) [Spanish] La memoria se divide en tres partes principales. En la primera, el autor expone los criterios seguidos para abordar el problema general de la evacuacion de sustancias radiactivas en el mar. Indica aquellos sectores en los que se requieren conocimientos oceanograficos y estudia sucintamente el estado de nuestros conocimientos actuales en estos sectores. En la segunda parte, los conocimientos oceanograficos existentes se aplican a los problemas de evacuacion de desechos, inclusive sus aspectos fisicos, quimicos y biologicos. El autor demuestra que, sobre la base de los conocimientos oceanograficos actuales, la evacuacion en las profundidades del mar de grandes cantidades (del orden de los megacuries por ano) de desechos envasados puede hacerse sin comprometer la utilizacion del mar y de sus productos por el hombre. Los desechos envasados de baja actividad, en cantidades del orden de varios centenares de curies por ano y por lugar de eliminacion, podran evacuarse en la plataforma continental. Asimismo, podra permitirse la evacuacion en las capas superficiales de la

  9. Radioactive Waste Facilities at the Australian Atomic Energy Commission Research Establishment; Installations pour le Traitement des Dechets Radioactifs au Centre de Recherche de la Commission Australienne a l'Energie Atomique; 0423 0421 0422 0414 ; Dispositivos para Evacuacion de Desechos Radiactivos en el Centro de Investigaciones de la Australian Atomic Energy Commission

    Energy Technology Data Exchange (ETDEWEB)

    Berglin, C. L.W.; Keher, L. H.; Miles, G. L.; Wilson, A. R.W. [Australian Atomic Energy Commission Research Establishment, Lucas Heights, Sydney, NSW (Australia)

    1960-07-01

    This paper describes the facilities,which are being provided for the collection, treatment and disposal of radioactive wastes at Lucas Heights in relation to the estimated arisings. Low-activity effluent is divided into three types: (a) Sewage; (b) Trades waste, arising from reactor cooling tower blow-down and engineering workshops and other inactive areas; and (c) Effluent arising from laboratories and other active areas. The effluent treatment plant for the latter type of effluent consists essentially of mixing and alkali dosing tanks, a sludge-blanket clarifier (using a calcium- iron-phosphate process) and holding tanks. Methods of concentrating the sludge and of secondary treatment are at present being investigated and are discussed. The discharge formula and the expected dilution obtained in the Woronora river are discussed, together with a dilution experiment carried out in the tidal waters. It is proposed to bury all low-activity solid waste after baling where appropriate and the choice and location of the disposal area is discussed. A facility for the storage and disposal of highly active solid waste is discussed. It is proposed to evaporate and store the medium- and high-activity liquid waste. Details are given of the capital and operating costs of the Effluent Treatment Plant and other waste handling facilities. (author) [French] Le memoire decrit les installations que le Centre de Lucas Heights cree a l'heure actuelle, eu egard au developpement envisage'en matiere de rassemblement, de traitement et d'elimination des dechets radioactifs. Les' effluents de faible activite se divisent en trois categories: a) Eaux d'egout; b) Dechets industriels provenant de la tour de refroidissement du reacteur, des ateliers et d'autres zones non-actives; c) Effluents provenant des laboratoires et d'autres zones actives. L'usine affectee au traitement du dernier type d'effluents se compose essentiellement de malaxeurs, de bacs de dosage d'alcalis, d'un clarificateur d

  10. Radioactive Waste Control at the United Kingdom Atomic Energy Research Establishment, Harwell; Traitement des Dechets Radioactifs au Centre de Recherche sur l'Energie Atomique de Harwell; 041a 041e 041d 0422 0420 041e 041b 042c 0417 0410 0423 0414 ; Control de Desechos Radiactivos en el A.E.R.E., Harwell

    Energy Technology Data Exchange (ETDEWEB)

    Burns, R. H. [United Kingdom Atomic Energy Authority (United Kingdom)

    1960-07-01

    The paper outlines the present practices in the control and treatment of radioactive wastes at Harwell. The large-volume, low-level active liquid effluent is treated by phosphate coagulation methods and, eventually, discharged to the River Thames. The medium-level wastes are segregated and undergo a two-stage chemical treatment followed by passage through columns of Vermiculite. The latter process has been found to be effective in removing radoicaesium, which is not dealt with efficiently by the precipitation methods used. Liquid wastes with a high- activity content are stored and a new plant, incorporating chemical treatment, ion exchange and evaporation, is being installed. The chemical sludges formed in the treatment processes are dumped at sea after de-watering by filtration. The contaminated solid waste is either stored or disposed of at sea. It is important to reduce the volume as much as possible and the methods employed include pressure baling, melting and incineration of combustible matter. Small quantities of activity are discharged to the atmosphere through exhaust stacks. The cleaning of this discharge air is commonly achieved by the use of high-efficiency filters or liquid scrubbing systems. Regular stack monitoring is carried out and this is backed up by a comprehensive district sampling programme. (author) [French] L'auteur decrit les methodes de controle et de traitement des dechets radioactifs qui sont appliquees au Centre de Harwell. Le volume considerable des effluents liquides de faible activite est traite par des methodes de coagulation au moyen des phosphates, puis evacue dans la Tamise. Apres separation, les dechets d'activite moyenne sont soumis a un traitement chimique en deux temps, avant de traverser des colonnes de Vermiculite. On a constate que ce dernier processus eliminait le radio- cesium, ce que les methodes de precipitation utilisees ne permettent pas de faire de maniere efficace. Les dechets liquides d'activite intense sont

  11. Soil contamination. part 1. changes in the humidity of non saturated soils after reject in a limited space. part 2. movements of radioactive ions in non saturated soils after reject in a limited space; Contamination des sols (1. partie). Evolution de l'humidite dans les sols non satures apres rejets sur une surface limitee. (2. partie). Comportement des ions radioactifs dans les sols non satures apres rejets d'eau sur une surface limitee

    Energy Technology Data Exchange (ETDEWEB)

    Rancon, D [Commissariat a l' Energie Atomique, Cadarache (France). Centre d' Etudes Nucleaires

    1972-07-01

    upon the counting rate of radioactivity. This method which have allowed to get various results about {sup 131}I and {sup 85}Sr can be generalized to other radioisotopes and other soils. They are applicable to radiological safety of sites studies : Testing storage plants, estimate of accidents hazards and protection of subterranean waters. (author) [French] II est important, dans les etudes de surete radiologique de sites, de connaitre les mouvements d'eau dans les terrains non satures surmontant la nappe aquifere, cette tranche de terrain aere pouvant servir de protection contre la contamination de la nappe. L'utilisation d'humidimetres a neutrons a permis de construire graphiquement les coupes des etats hydriques du terrain et les evolutions dans le temps du volume du sol mouille a partir d'un rejet affectant une superficie restreinte. On mesure aussi les gradients d'humidite, les cinetiques d'assechement, la capacite de retention du sol et la teneur en eau gravifique suspendue en en equilibre avec la charge d'eau. L'etat hydrique initial influence la vitesse d'infiltration et non la vitesse d'avancement du front d'humectation, on peut donc calculer la quantite d'eau accumulable par le terrain. Apres l'arret du rejet, le volume de sol mouille evolue jusqu'a un etat d'equilibre limite par le front d'humectation, les redistributions d'humidite s'effectuant seulement au sein de ce volume; ainsi, en cas de rejet de liquide radioactif, les ions contaminants resteront confines dans un volume mesurable limite par le front d'humectation. Partie 2. Pour faire suite au rapport sur les mouvements d'eau dans les sols non satures apres rejet sur une surface limitee - CEA R 3635 (1) - on etudie les mouvements des ions radioactifs dans ces sols en utilisant un anion et un cathion caracteristiques: l'iode 131 et le strontium 85. La methode est basee sur la mesure simultanee des fronts d'humidite et d'activite au moyen d'humidimetre a neutrons et d'une sonde d'activite specialement

  12. Environmental Implications of Radioactive Waste Disposal as Related to Stream Environments; Incidences du Milieu sur l'Elimination des Dechets Radioactifs dans le Voisinage des Cours d'Eau; 0412 041b 0418 042f 0414 ; Efectos de la Evacuacion de Desechos Radiactivos en las Corrientes Fluviales

    Energy Technology Data Exchange (ETDEWEB)

    Straub, Conrad P.; Goldin, Abraham S.; Friend, Albert G.; Taft, Robert A. [Sanitary Engineering Center, US Department of Health, Education and Welfare, Cincinnati, OH (United States)

    1960-07-01

    Increasing volumes of radioactive waste materials are being introduced into streams annually. These originate from the many laboratories in which radioactive materials are used for beneficial purposes, as well as from existing atomic energy facilities. To these amounts introduced directly into the river under essentially controlled conditions must be added those radioactive materials originating from fall-out and feeding into the stream through run-off or direct deposition. Since these same streams may serve a multiplicity of purposes, as for example, potable and industrial water, recreation, fishing, irrigation, and navigation, the effect of these discharges on each of these activities must be carefully evaluated. Present criteria do not provide a complete basis for determining permissible levels of discharge unless information is available on the amounts of specific radionuclides already present and the fate of these same nuclides in the downstream environment. Permissible levels of discharge will have to be modified in accordance with the above information and particularly in terms of the uses to which the downstream watercourse is put. Where several sources of discharge are to be permitted on a given water-course, allocation of maximum amounts of specific radionuclides must be established in accordance with downstream exposures of populations from all sources. Several suggested approaches to the handling-of this problem of waste management in relation to downstream uses are outlined and some of the difficulties associated with the application of each approach are considered. (author) [French] Chaque annee, des quantites croissantes de dechets radioactifs sont deversees dans les cours d'eau. Ces dechets proviennent des nombreux laboratoires utilisant des substances radioactives a des fins benefiques, ainsi que des installations d'energie atomique. Aux quantites qu'on deverse directement dans les cours d'eau en se conformant aux conditions qui constituent l

  13. The use of radioactive tracers in lubrication and wear research; Emploi des indicateurs radioactifs dans les recherches sur la lubrification et l'usure; Ispol'zovanie mechenykh atomov pri issledovanii voprosov smazki i iznosa; Utilizacion de los indicadores radiactivos en los estudios sobre la lubricacion y el desgaste

    Energy Technology Data Exchange (ETDEWEB)

    Campbell, R B; Grunberg, L; Milne, A A; Wright, K H.R. [Lubrication, Wear and Mechanical Engineering Aspects of Corrosion Division, National Engineering Laboratory, Thorntonhall, Glasgow (United Kingdom)

    1962-01-15

    In many lubrication and wear problems, processes occurring on a very small scale have to be studied and the great sensitivity of radioactive tracer methods has been successfully applied. Several examples of such applications are cited from the work of the Lubrication and Wear Division of the National Engineering Laboratory in the United Kingdom. The quantitative relation between metal transfer and boundary friction is studied as a function of sliding velocity, surface roughness and the presence of lubricants. In order to study the distribution of wear, cast iron plugs containing Ir{sup 192} are inserted in the liners of a Diesel engine and the radioactivity present in oil samples is measured. Radioactive iron and iron oxide particles are used to study then role in the wear process. The reactivity of strained metal surface is studied with the aid of C{sup 14}- labelled stearic acid and of S{sup 35} in solution. The reaction rates of gear oil additive are being studied by passing short electric-current pulses through metal wires immersed in solutions of compounds labelled with S{sup 35} and P{sup 32}. The build-up of anti-wear films on the surface of gear teeth is being studied as a function of lead, speed and running time. A problem encountered in many of these applications is the conversion of the measured activity into absolute quantities of materials present in surface films or in wear debris. Calibration methods have been developed for this purpose. (author) [French] Pour nombre de problemes relatifs a la lubrification et a l'usure, ou l'on doit etudier des processus se produisant a tres petite echelle, la methode des indicateurs radioactifs, qui presente l'avantage d'etre tres sensible, a donne de bons resultats. Le memoire cite plusieurs exemples d'applications de ce genre, tires des travaux de la Division de la lubrification et de l'usure du National Engineering Laboratory (Royaume-Uni). La relation quantitative entre le transfert de metal et la friction de

  14. The Depths of the Ocean and the Question of Radioactive Waste Disposal in Them; Les Grandes Fosses Oceaniques et l'Immersion des Dechets Radioactifs dans ces Eaux Profondes; 0413 041b 0423 0414 ; Cuestiones Relacionadas con la Inmersion de Desechos Radiactivos en las Grandes Fosas

    Energy Technology Data Exchange (ETDEWEB)

    Bogorov, V. G.; Tareev, B. A.; Fedorov, K. N. [Oceanographical Institute of the Academy of Sciences of the USSR, Moscow, USSR (Russian Federation)

    1960-07-01

    . Aucune d'elles ne possede de particularites morphologiques pouvant empecher les eaux profondes d'y penetrer ou de s'ecouler. L'augmentation progressive de la temperature de l'eau a partir de 3.000 a 5.000 metres de profondeur jusqu'au fond de ces fosses provoque des courants verticaux de convexion dans les eaux profondes. Il est theoriquement prouve que malgre l'effet stabilisateur du mouvement de rotation de la terre, il doit exister des courants de convexion alveolaires, meme lorsque les differences de temperature superadiabatiques restent tres petites. La repartition verticale de la teneur en oxygene en fonction de l'augmentation caracteristique du taux de saturation et de concentration en O{sub 2}, qui va en s'accentuant depuis la couche minimum (1.000 metres) jusqu'au fond, permet de presumer l'existence d'un mouvement horizontal et vertical ou bien d'un deplacement horizontal des eaux profondes dans toute leur masse. S'il n'en etait pas ainsi, l'utilisation biochimique de l'oxygene (au moins 0,1 ml par an) entrainerait un epuisement total des reserves de cet element dans les eaux profondes en un laps de temps relativement court (40 a 60 ans). L'existence de courants horizontaux assez rapides (5 a 17 cm/s) a des profondeurs de 1.000 a 3.000 metres a ete demontree par les mesures directes qui ont ete effectuees dans l'Atlantique et le Pacifique. La diffusion des particules dissoutes ou suspendues dans la mer n'est pas uniquement due a la circulation des eaux, au sens physique de ce terme. Le deplacement continu des organismes vivants constitue, en effet, un risque supplementaire de voir les substances radioactives accumulees dans les tissus de ces organismes etre diffusees par ceux-ci ou transmises par les chaines alimentaires a des distances considerables et a une grande vitesse, comme on a pu le constater apres les explosions experimentales qui ont eu lieu dans l'Ocean Pacifique. Il faut donc admettre qu'il est impossible d'immerger des dechets radioactifs dans les

  15. Desirable New Geologic Research in Support of Radioactive Waste Disposal as Indicated by Hanford Experience; Nouvelles Recherches Geologiques Souhaitables au Sujet de l'Elimination des Dechets Radioactifs, Selon les Indications Fournies par l'Experience de Hanford; 041f 0420 041e 0412 0415 0414 ; Nuevas Investigaciones Geologicas que Convendria Hacer para Facilitar la Evacuacion de Desechos Radiactivos Siguiendo las Indicaciones Proporcionadas por las Experiencias Efectuadas en Hanford

    Energy Technology Data Exchange (ETDEWEB)

    Brown, Randall E. [Hanford Laboratories, Hanford Atomic Products Operation, General Electric Company, Richland, WA (United States)

    1960-07-01

    All disposal of radioactive wastes to land relies on the geologic environment. Disposal to that environment is not ultimate, however, for no material is impermeable, unleachable or non-corrodable when we consider geologic time. Hanford's disposal interjects a maximum of geologic features between disposal sites and the point of nearest public exposure. This is the concept named by Simpson the ''delay-and-decay'' concept. Problems involved in disposal at Hanford include 1) the quantitative inexactness of geology, (2) the lack of isotropic, homogeneous earth materials, 3) determination of the quantitative importance of deviation of geologic and hydrologie features from an average, and (4) determination and measurement of the parameters of interest. Cases at Hanford are cited to illustrate the above points. Wells totalling 557 in number and 33,000 m in depth have been drilled, but provide data that must be cautiously used. Standard aquifer performance tests are limited in value, for unit and directional permeabilities are integrated into average values. Ion-exchange studies provide quantitative values of direct interest, helping to interpret geologic features. Hydrologie studies, correlated to the soil chemistry work and the geologic data, result in logically explainable geologic controls to ground water movement. Disposal to ground of radioactive wastes is neither a cure-all nor something to be feared. The integration of data from studies by geologists, hydrologiste, geochemists and mathematicians has gone far to assure the safe disposal of wastes to ground at Hanford. A great amount of work remains to be done, however. (author) [French] Pour toute elimination de dechets radioactifs dans le sol, on doit tenir compte du milieu geologique. Mais les produits ainsi elimines ne restent pas definitivement dans le milieu ambiant: a la longue, aucune matiere n'apparait impermeable, ni capable de faire obstacle au filtrage ou de resister a la corrosion. Le procede utilise a

  16. Circulations in the Bay of Bengal and the Arabian Sea with Reference to Safe Disposal of Radioactive Wastes Near the Indian Coasts; Les Circulations dans les Eaux du Golfe du Bengale et de la Mer d'Oman et l'Elimination sans Danger des Dechets Radioactifs pres des Cotes Indiennes; 0426 0418 0420 0414 ; Circulaciones en el Golfo de Bengala e en el Mar Arabico con Relacion a la Evacuacion sin Riesgos de Desechos Radiactivos Frente al Litoral Indio

    Energy Technology Data Exchange (ETDEWEB)

    Rama Sastry, A. A. [Meteorological Office, Poona 5 (India)

    1960-07-01

    admixture of the Indian Central water, Indian deep water and the Antarctic bottom water. The distribution of these water masses and the deep water circulation north of the equator are given. During the past 60 years, the Antarctic bottom water seems to be advancing further north of the equator both into the Bay of Bengal and the Arabian Sea. Consequently, lowering of salinity is recorded both in the Bay and the Arabian Sea. Finally, a programme of further oceanographic work in connexion with the safe disposal of radioactive wastes, particularly into the Arabian Sea, is suggested. (author) [French] L'auteur passe rapidement en revue les connaissances generales acquises sur l'oceanographie du golfe du Bengale et de la mer d'Oman. Sur la base des etudes effectuees depuis quelques annees par les nombreuses stations oceanographiques qui fonctionnent Je long des cotes indiennes, l'auteur etudie les conditions oceanographiques du point de vue de l'elimination sans danger des dechets radioactifs. Il s'est egalement servi des donnees reunies par differentes expeditions dans l'ocean Indien pour etudier l'oceanographie physique de la region situee au nord de l'Equateur. Jusqu'a 200 m au-dessous de la surface, les masses d'eau du golfe du Bengale et de la mer d'Oman se repartissent en trois categories au moins. Dans le golfe du Bengale, etant donne le taux de dilution tres eleve, les eaux de surface pourraient etre divisees en un plus grand nombre de categories. Compte tenu de la valeur de differents parametres oceanographiques sur divers plans horizontaux, ou a calcule la circulation le long des cotes indiennes a plusieurs niveaux jusqu'a 150 m de profondeur; a partir de sections verticales, on a deduit la circulation jusqu'a une profondeur de 500 m. La profondeur a laquelle il n'y a pas de mouvements parait bien inferieure a 500 m; elle varie dans l'espace et dans le temps. Le taux de melange des eaux est calcule a partir des rapports espace-temps. L'auteur indique les saisons au

  17. Summary of Current Geological Research in the United States of America Pertinent to Radioactive Waste Disposal on Land; Bilan des Recherches Geologiques Actuelles aux Etats-Unis, du Point de Vue de l'Elimination des Dechets Radioactifs dans le Sol; 041a 0420 0414 ; Resena de las Investigaciones Geologicas que Actualmente se Efectuan en los Estados Unidos Sobre la Evacuacion de Desechos Radiactivos en el Subsuelo

    Energy Technology Data Exchange (ETDEWEB)

    Simpson, E. S. [Geologist, US Geological Survey, Washington, DC (United States)

    1960-07-01

    'isolement qui doit etre assure aux dechets pour respecter les normes de sante et de securite generalement admises. I. Les structures assurant un isolement maximum doivent retenir pendant des siecles ou des millenaires pratiquement tous les dechets qui y sont deposes. Les recherches portent sur deux types generaux: les depots salins et les formations permeables profondes. Dans les deux cas, on procede a des experiences en laboratoire pour etudier l'interaction des dechets en solution et des matieres constituant le terrain considere; pour les depots salins, une experience sur le terrain est en cours, dans laquelle on utilise des dechets simules de. haute activite, qui, en realite, ne sont pas radioactifs. II. Les structures assurant un isolement moyen doivent ralentir notablement la mobilite des dechets pour que ceux-ci aient le temps de se desintegrer au point de vue radioactif avant de venir en contact avec l'homme ou la chaine alimentaire. Comme exemple d'isolement moyen, on peut citer l'enfouissement a faible profondeur de dechets emballes et le deversement de dechets liquides en vrac dans des couloirs d'infiltration. Des recherches sont en cours pour etudier la maniere dont se combinent le transport des radionuclides par les eaux souterraines et la retention des radionuclides fixes par sorption dans les matieres constituant le terrain. III. Les structures n'assurant aucun isolement sont celles ou les radionuclides viennent directement en contact avec l'homme ou l'un des elements vivants de la chaine alimentaire. Des recherches sont en cours a la fois pour determiner la capacite de differentes structures a recevoir de tels dechets sans que la sante et la securite en soient affectees et pour ameliorer les techniques employees a cette fin. Les recherches actuelles portent sur les points suivants : a) Classification des terrains eu egard aux problemes d'elimination des dechets; b) Etude des caracteristiques de diffusion des courants; c) Action sur la concentration de la

  18. The use of radiotracer techniques to study lubrication and wear in large diesel engines; Emploi des indicateurs radioactifs pour l'etude de la lubrification et de l'usure dans les moteurs diesel de grande puissance; Ispol'zovanie metodov radioaktivnykh indikatorov dlya izucheniya smazki i iznosa bol'shikh dizel'nykh motorov; Aplicacion de los indicadores radiactivos al estudio de la lubricacion y desgaste de los motores diesel de gran potencia

    Energy Technology Data Exchange (ETDEWEB)

    Howes, Jr, J E; Braun, W J; Sunderman, D N [Battelle Memorial Institute, Columbus, OH (United States)

    1962-01-15

    Radiotracer techniques have been applied to the study of lubrication and wear in large diesel engines on a scale not before considered practical, with perfect safety and with unique technological results. Both lubricating-oil consumption and cylinderliner wear have been evaluated as a function of operating conditions on diesel engines in the 1000 HP range. Techniques were developed for tapping 200 gal (US) of lubricating oil with 60 mc of zinc-65 and determining oil consumption by sampling exhaust gas during operation under a variety of conditions. Measurement of the rate of lubeoil consumption could be made in 10 min rather than the 24 to 48 h previously required. Irradiation techniques were developed for neutron activation of the lower cylinder portion of a 48-in long, 8-in diam. cylinder liner. Suitable thermal-neutron shielding allowed production of 300-d manganese-54 which resulted in extending the useful life of the liner for wear studies by a factor of six to eight over that of a comparable liner thermally activated to produce iron-59. The fact that studies with such large quantities of radioactive material can be carried out in standard research facilities in the diesel engine field opens an entirely new area to tracer applications. Selective activation and judicious use of thermalneutron shielding increases the versatility of the tracer technique in localizing measurement to areas of interest, reducing the total quantity of radioactive material required in wear studies of large parts, and facilitating simultaneous wear-measurement on engine parts of identical chemical composition. (author) [French] On s'est servi d'indicateurs radioactifs pour l'etude de la lubrification et de l'usure des moteurs diesel de grande puissance, et cela a une echelle qui jusqu'a present n'etait pas consideree comme pratiquement realisable, avec m e securite parfaite et des resultats technologiques sans precedent. La consommation de l'huile de graissage et l'usure des chemises

  19. Where are the radioactive wastes in France? 2006 geographic inventory of radioactive wastes; Ou sont les dechets radioactifs en France? Inventaire geographique 2006 des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    This document presents, by region, the localization of existing radioactive wastes in France at the date of December 31, 2004. In addition to the geographic situation, this inventory is presented by site and by category of waste producer or owner. The collection of these data is based on the free declaration made by waste owners or producers. The gathered information has been reformatted and homogenized and is reported in a synthetic way in the form of tables and files. Thus, 899 sites have been indexed, among which 159 are presented in the form of a detailed file. For each region, a table details the registered sites by category of producer/owner and the location of the main ones is reported on a regional map. The registered waste producers are radionuclide users belonging to 4 specific domains: medical, research, industry and national defense. The corresponding wastes are in general modest both in quantity and activity. The sites polluted by radioactive substances are also mentioned, even if they are already decontaminated or not. (J.S.)

  20. Present and Future Programmes in the Treatment and Ultimate Disposal of High-Level Radioactive Wastes in the United States of America; Programmes Actuels et Futurs de Traitement et d'Elimination Definitive des Dechets Radioactifs de Haute Activite aux Etats-Unis; 0422 0415 041a 0423 0429 0410 042f 0418 0411 0423 0414 ; Programas Estadounidenses Actuales y Futuros para el Tratamiento y Evacuacion Definitiva de Desechos de Elevada Radiactividad

    Energy Technology Data Exchange (ETDEWEB)

    Belter, W. G. [United States Atomic Energy Commission, Washington, DC (United States)

    1963-02-15

    du premier cycle dans le sol rocheux sous-jacent; il indique les resultats preliminaires obtenus. L'auteur evoque les etudes techniques a long terme qui se poursuivent ,aOak Ridge et qui ont pour objet d'evaluer les risques et les aspects economiques des diverses methodes de manipulation, de stockage et d'elimination definitive de dechets liquides et solides hautement radioactifs. Il examine le role de ces evaluations techniques dans l'elaboration des futurs programmes de gestion des dechets. (author) [Spanish] Las desventajas inherentes al almacenamiento de desechos de elevada radiactividad en tanques, tales como el riesgo de escape y la perspectiva de tener que proceder durante tiempos muy largos al transporte de desechos liquidos han inducido a preparar en los Estados Unidos un programa intensivo de estudios y mejoras encaminado a establecer sistemas practicos de evacuacion definitiva de aquellos materiales. El autor describe el programa de la Division de Desarrollo de reactores de la Comision de Energia Atomica de dicho pais en la medida en que se relaciona con la evolucion futura de la energia nucleoelectrica en sus aspectos economicos. Asimismo, presenta una sintesis de los programas a largo plazo para el tratamiento y la evacuacion de los desechos radiactivos en los centros de produccion de plutonio, en Hanford y Savannah River, senalando los requisitos impuestos por sus ubicaciones respectivas. Se estan llevando a cabo estudios sobre diversos metodos de {sup c}onversion en solidos', incluyendo el empleo de lechos fluidizados, crisoles, columnas de vaporizacion de calor radiante, hornos rotatorios y esponjas de material ceramico. Tambien se examina el metodo basado en la adicion de materiales vitrificantes a los desechos, a fin de obtener un producto mas estable. El autor senala las ventajas e inconvenientes inherentes a cada uno de esos metodos. Resume el estado actual de los mencionados proyectos y expone los planes propuestos para los futuros programas. El

  1. Fixation of Radioactive Waste in Glass. Part I. Pilot-Plant Experience at Harwell; Fixation des Dechets Radioactifs dans le Verre, Premiere Partie: L'Usine Pilote de Harwell; 0424 0418 041a 0421 0410 0426 0418 042f 0420 0410 0414 0418 041e 0410 041a 0422 0418 0412 041d 042b 0425 041e 0422 0425 041e 0414 041e 0412 0412 0421 0422 0415 041a 041b 0415 ; Fijacion de Desechos Radiactivos en Vidrio. Parte I: Experiencia Adquirida en la Instalacion Piloto de Harwell

    Energy Technology Data Exchange (ETDEWEB)

    Elliot, M. N.; Gayler, R.; Grover, J. R.; Hardwick, W. H. [Atomic Energy Research Establishment, Harwell (United Kingdom)

    1963-02-15

    The reasons for incorporating fission-product wastes into glass for long-term storage are outlined. The flow-sheet and operating cycle of the fixation process which has been developed at Harwell are described. Two years of operation of an inactive pilot plant are surveyed to show how the present operating conditions have been evolved. Full-length runs under these conditions have confirmed the reliability and reproducibility of the process. Engineering components suitable for an active plant have been developed and tested and the layout of die 1000-c pilot plant being commissioned at Harwell is illustrated in sketch form. Factors that affect the scale-up of the process are discussed in relation to the needs of the developing United Kingdom power programme. (author) [French] Les auteurs exposent les raisons pour lesquelles on incorpore les dechets de produits de fission dans le verre en vue d'un stockage de longue duree. Ils donnent le diagramme d'operations et le cycle du procede de fixation mis au point a Harwell. Ils decrivent les deux annees de fonctionnment de l'usine pilote, sans produits radioactifs, pour montrer comment les conditions actuelles d'operations ont ete mises au point. Des cycles complets realises dans ces conditions ont confirme la securite et la reproductibilite du processus. L'appareillage approprie pour une usine de haute activite a ete mis au point et essaye; les auteurs de crivent les grandes lignes de l'usine pilote (activite de 1000 c) en construction a Harwell. Les auteurs discutent les facteurs qui peuvent affecter le developpement de ce processus a plus grande echelle, eu egard aux besoins du programme energetique du Royaume-Uni. (author) [Spanish] Los autores exponen las razones que aconsejan incorporar los desechos y productos de fision a materiales vitreos para almacenarlos por tiempo largo. Describen el diagrama de circu- lacion y el ciclo de operaciones que integran el proceso de fijacion perfeccionado en Harwell. Examinan luego

  2. Mechanical disequilibria in two-phase flow models: approaches by relaxation and by a reduced model; Modelisation des desequilibres mecaniques dans les ecoulements diphasiques: approches par relaxation et par modele reduit

    Energy Technology Data Exchange (ETDEWEB)

    Labois, M

    2008-10-15

    This thesis deals with hyperbolic models for the simulation of compressible two-phase flows, to find alternatives to the classical bi-fluid model. We first establish a hierarchy of two-phase flow models, obtained according to equilibrium hypothesis between the physical variables of each phase. The use of Chapman-Enskog expansions enables us to link the different existing models to each other. Moreover, models that take into account small physical unbalances are obtained by means of expansion to the order one. The second part of this thesis focuses on the simulation of flows featuring velocity unbalances and pressure balances, in two different ways. First, a two-velocity two-pressure model is used, where non-instantaneous velocity and pressure relaxations are applied so that a balancing of these variables is obtained. A new one-velocity one-pressure dissipative model is then proposed, where the arising of second-order terms enables us to take into account unbalances between the phase velocities. We develop a numerical method based on a fractional step approach for this model. (author)

  3. Calcination of Radioactive Waste in Molten Sulphur; Calcination de Dechets Radioactifs dans le Soufre Fondu; 041a 0410 041b 042c 0426 0418 041d 0418 0420 041e 0412 0410 041d 0418 0415 0420 0410 0414 0418 041e 0410 041a 0422 0418 0412 041d 042b 0425 041e 0422 0425 041e 0414 041e 0412 0412 0420 0410 0421 041f 041b 0410 0412 041b 0415 041d 041d 041e 0419 0421 0415 0420 0415 ; Calcinacion de Desechos Radiactivos en Azufre Fundido

    Energy Technology Data Exchange (ETDEWEB)

    Winsche, W. E.; Davis, Jr., M. W.; Goodlett, Jr., C. B.; Occhipinti, E. S.; Webster, D. S. [E.I. Du Pont de Nemours and Co., Aiken, SC (United States)

    1963-02-15

    . Leaching rates are calculated as, though there is complete removal of material from a surface layer. Rates of 10 to 20 mil/yr, or less, have been observed after an initial period of 6 to 8 weeks at moderately higher rates. (author) [French] Le Laboratoire de Savannah River met actuellement au point une methode nouvelle fondee sur les proprietes exceptionnelles du soufre qui permettent de transformer des dechets radioactifs en solides peu solubles, en vue de proceder a leur elimination definitive. Selon cette methode, on fait reagir les dechets liquides acides avec du soufre fondu a 150 Degree-Sign C: l'eau et les acides volatiles sont chasses, puis les composes chimiques presents dans les dechets sont calcines et/ou reduits chimiquement. La suspension soufre-dechets ainsi obtenue est alors chauffee pendant une duree de 1 a 5h aune temperature de 400 a 444 Degree-Sign C afin de chasser l'acide sulfurique et l'eau residuelle et de poursuivre la calcination et/ou la reduction des composes chimiques dans la suspension soufre-dechets. Au cour de ces operations, ie soufre fondu sert de milieu caloporteur, empeche l'entrainement des solides radioactifs dans la vapeur et les gaz de la reaction et previent la volatilisation du radioruthenium en empechant la formation du tetraoxyde. Des essais en laboratoire avec des dechets concentres de haute activite (1.3 x 10{sup 9} {gamma} c/(min)(ml), 2.0M Al(N0{sub 3}){sub 3}, et 1.5M HNO{sub 3}) ont montre qu'environ un cent-millieme seulement de l'activite presente dans la matiere premiere est emporte par le gaz qui se degage au cours de ces operations. Une fois termine le traitement a haute temperature, on laisse refroidir la suspension soufre-dechets jusqu'a 150 ou 120 Degree-Sign C et on la transvase ensuite dans le milieu d'isolement final, ou on la laisse se solidifier. Bien que les auteurs aient l'intention de proteger le milieu d'isolement contre l'action de l'eau, ils ont etudie la resistance de la suspension solidifiee soufre

  4. Destructive textures around radioactive minerals; Les textures destructives autour des mineraux radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Montel, J.M. [ENSG-G2R, CNRS-Nancy-Universite, 54 - Vandoeuvre-les-Nancy (France); Seydoux-Guillaume, A.M. [LMTG, CNRS-UPS-IRD, Universite de Toulouse, OMP, 31 - Toulouse (France)

    2009-07-01

    In most of the rocks, natural uranium and thorium are concentrated in some minerals which provide favourable crystallographic sites. These minerals are thus submitted to an intense auto-irradiation which may transform them. Using conventional investigation methods (petrographic or scanning electronic microscopy, electronic micro-probe) and less conventional ones (transmission electronic microscopy), the authors studied the interfaces between radioactive minerals and their host minerals. They comment the possible mechanical and structural aspects of this interaction by irradiation, and the influence of geological events

  5. Public debate on radioactive wastes; Le debat public sur les dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    The definition and implementation of safe and perennial solutions for the management of radioactive wastes is a necessity from the point of view of both the nuclear industrialists and the public authorities, but also of the overall French citizens. For the low- or medium-level or short living radioactive wastes, some solutions have been defined are are already implemented. On the other hand, no decision has been taken so far for the long living medium to high-level radioactive wastes. Researches are in progress in this domain according to 3 ways of research defined by the law from December 30, 1991: separation-transmutation, disposal in deep underground, and long duration surface or sub-surface storage. This paper presents in a digest way, the principle, the results obtained so far, and the perspectives of each of the three solutions under study. (J.S.)

  6. Science for safety in nuclear waste handling; Aspects scientifiques de la surete des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Bonin, B. [CEA Saclay, Dir. de l' Energie Nucleaire (DEN), 91 - Gif sur Yvette (France)

    2005-05-01

    A facility for disposing of nuclear waste has the objective of protecting mankind. It is shown how nuclear safety is taken into account in the definition of the facilities, particularly through the use of the multi-barriers concept. Elements on safety assessment are provided, with emphasis on the scenario (normal or altered approach; examples of research programs required by these assessment tasks, particularly by means of underground laboratories are given. (author)

  7. Radioactive residues. Current and prospective problems. Les residus radioactifs. Problems actuels et perspectives

    Energy Technology Data Exchange (ETDEWEB)

    Gauvenet, A.

    1975-07-01

    After having described the principal characteristics of radioactive residues, the author examined the current problems posed by liquid and gaseous effluents and stressed that nuclear installations are definitely much less polluting, with an identical power output, than conventional power stations. Research programs have been undertaken in the face of the predictable increase in activity. The gist of the matter is to maintain the absorbed doses at their present level and to study the problem of compounds with a long lifetime, the accumulation of which would create considerable danger on a world scale. With respect to the stockpiling of wastes, the author described the various techniques currently used and cited studies in progress, some of which--such as vitrification--have already come into the first stages of application. After having noted that the waste problem undoubtedly constitutes a technical difficulty and perhaps even more so on the psychological plane, the author defined in conclusion the conditions that should be established so that this problem does not hinder the short- and long-term development of nuclear energy.

  8. Management of radioactive wastes. Closing meeting; Gestion des dechets radioactifs. Reunion de cloture

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    The law from December 30, 1991, precisely defines 3 axes of researches for the management of high level and long-lived radioactive wastes: separation/transmutation, surface storage and underground disposal. A global evaluation report about these researches is to be supplied in 2006 by the French government to the Parliament. A first synthesis of the knowledge gained after 14 years of research has led the national commission of the public debate (CNDP) to organize a national debate about the general options of management of high-level and long-lived radioactive wastes before the 2006 date line. The debate comprised 4 public hearings (September 2005: Bar-le-Duc, Saint-Dizier, Pont-du-Gard, Cherbourg), 12 round-tables (October and November 2005: Paris, Joinville, Caen, Nancy, Marseille), a synthesis meeting (December 2005, Dunkerque) and a closing meeting (January 2006, Lyon). This document is the proceedings of this closing meeting. The aim of this meeting is to make a status of the different public hearings and round-tables and to stress on some particular points of the nuclear waste management debate. Some points concern the social and democratic dimension of this debate which can be summarized in few words like: public information, decision making, secrecy, confidence, transparency, acceptability, ethics. Some other points concern the scientific and technical dimensions of nuclear waste management and refer to the advantages and drawbacks of the different options of the 1991 law (transmutation, deep geologic disposal, and subsurface storage). (J.S.)

  9. Detection systems for radioactive ion beams; Systeme de detection en ions radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Savajols, H

    2002-07-01

    Two main methods are used to produce radioactive ion beams: -) the ISOL method (isotope separation on-line) in which the stable beam interacts with a thick target, the reaction products diffuse outside the target and are transferred to a source where they are ionized, a mass separator and a post-accelerator drive the selected radioactive ions to the right energy; -) the in-flight fragmentation method in which the stable beam interacts with a thin target, the reaction products are emitted from the target with a restricted angular distribution and a velocity close to that of the incident beam, the experimenter has to take advantage from the reaction kinetics to get the right particle beam. Characteristic time is far longer with the ISOL method but the beam intensity is much better because of the use of a post-accelerator. In both cases, the beam intensity is lower by several orders of magnitude than in the case of a stable beam. This article presents all the constraints imposed by radioactive beams to the detection systems of the reaction products and gives new technical solutions according to the type of nuclear reaction studied. (A.C.)

  10. Radioactive indicators in biology and their medical applications; Indicateurs radioactifs en biologie et leurs applications medicales

    Energy Technology Data Exchange (ETDEWEB)

    Morel, F

    1950-12-01

    This talk was given at the society of promotion of the national industry on December 1, 1949. The report is a pre-print of an article published in L'Industrie Nationale no.2 (1950). It presents the state-of-the-art of the use of artificial radioisotopes in biology and medicine: 1 - definitions (isotopes, decay, radiation emission); 2 - modalities of the use of radioisotopes in biology: basic instrumentation (Geiger-Mueller counter, counting techniques, photography, auto-histo-radiography); 3 - applications in physiology (digestive absorption, excretion, vascular exchanges, tracer techniques) and biochemistry (metabolism, thyroxine synthesis and fixation indicators, tracer techniques for drugs); 4 - radiotherapy, internal and external irradiation. (J.S.)

  11. Conditioning of solid radioactive wastes (1960); Conditionnement des dechets radioactifs solides (1960)

    Energy Technology Data Exchange (ETDEWEB)

    Cerre, P [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1960-07-01

    Since solid radioactive wastes are of varied forms, dimensions and volumes, the C.E.A. first reduces the volume by breaking up and compacting. Since these wastes cannot be temporarily stored without contamination risk, an effective packing process has been devised and carried through. This consists in burying the wastes in a specially planned concrete with the following characteristics: - high mechanical resistance; - maximum insolubility; - resistance to corrosion; - maximum imperviousness; - providing protection against radiation. It is then possible to store the blocks safely, with a view to eventual definitive rejection. (author) [French] Les dechets actifs solides etant de formes, de dimensions et de volumes varies, le C.E.A. procede en premier lieu a une reduction de volume par fractionnement et compactage. L'emmagasinage provisoire de tels dechets ne pouvant se concevoir sans risques de contamination, un procede efficace d'emballage a ete etudie et realise. Il consiste a noyer les dechets dans un beton specialement etudie qui presente les caracteristiques suivantes: - forte resistance mecanique; - insolubilite maximum; - resistance a la corrosion; - etancheite maximum; - protection contre le rayonnement. Il est alors possible de conserver sans danger les blocs formes en vue d'un rejet definitif ulterieur. (auteur)

  12. Half-life distribution table of radioactive nuclei; Table de distribution des periodes des noyaux radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Gugenberger, P [Commissariat a l' Energie Atomique, Saclay(France). Centre d' Etudes Nucleaires

    1954-07-01

    This table allows to identify an element if its period is known. Data for this table were taken from the half-life values adopted by Hollander, PERLMAN and SEABORG (Rev. mod. Phys., 1953, 22 number 2). Moreover for each nucleus, the mass number, the charge number and the type of decay are given in the table. (author) [French] Cette table permet l'identification d'un element dont la periode est connue. Elle a ete etablie en utilisant les valeurs des periodes donnees par HOLLANDER, PERLMAN et SEABORG dans Rev. mod. Phys., 1953, 25 numero 2. On y trouve en outre, pour chaque nuclide, les caracteristiques suivantes: Z, A, modes de desintegration. (auteur)

  13. Public debate - radioactive wastes management; Debat public - gestion des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    Between September 2005 and January 2006 a national debate has been organized on the radioactive wastes management. This debate aimed to inform the public and to allow him to give his opinion. This document presents, the reasons of this debate, the operating, the synthesis of the results and technical documents to bring information in the domain of radioactive wastes management. (A.L.B.)

  14. Radioactive wastes management: what is the situation?; Gestion des dechets radioactifs: ou en est-on?

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-01

    This presentation takes stock on the situation of the radioactive wastes management in France. It gives information on the deep underground disposal, the public information, the management of the radioactive wastes in France, the researches in the framework of the law of the 30 december 1991, the underground laboratory of Meuse/Haute-Marne, the national agency for the radioactive wastes management (ANDRA) and its sites. (A.L.B.)

  15. The radiation protection and the radioactive wastes management; La radioprotection et la gestion des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Servais, F. [CHR Hopital de Warquignies, Service de Medecine Nucleaire (Belgium); Woiche, Ch. [Universite Libre de Bruxelles, Service Interne et de Prevention et Protection (Belgium); Hunin, Ch. [Agence Federale de Controle Nucleaire, Service Controle Etablissements Classes, Brexelles (Belgium)] [and others

    2003-07-01

    This chapter concerns the radiation protection in relation with the radioactive waste management. Three articles make the matter of this file, the management of radioactive medical waste into hospitals, a new concept of waste storage on site, the protection devices on the long term with some lessons for the radioactive waste management. (N.C.)

  16. Neutronic measurements of radioactive waste; Les mesures neutroniques des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Perot, B

    1997-12-31

    This document presents the general matters involved in the radioactive waste management and the different non destructive assays of radioactivity. The neutronic measurements used in the characterization of waste drums containing emitters are described with more details, especially the active neutronic interrogation assays with prompt or delayed neutron detection: physical principle, signal processing and evaluation of the detection limit. (author).

  17. Device for recovering radioactive waste; Dispositif de recuperation d'effluents radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Mas, R [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1965-07-01

    The previous system which consisted in the use of metallic reservoirs placed in a concrete-lined pit gave rise to certain incidents due to corrosion or overflowing followed by contamination with serious consequences. The new system presented consists essentially of a standard 3 m{sup 3} reservoir of stainless steel which is fixed in a concrete-lined well, is tubed with stainless steel. Each reservoir has a standard lid on which are placed all the accessory devices, themselves standardized. The new reservoirs offer thus a great degree of security, and are interchangeable; the wells are easy to decontaminate and it is possible to work in a well without any danger of the personnel being irradiated by neighbouring reservoirs. (author) [French] L'ancien systeme de cuves metalliques disposees dans une fosse betonnee a donne lieu a des incidents par corrosion ou debordements suivis de contamination ayant de grosses consequences. Le nouveau systeme presente comporte essentiellement une cuve standard de 7 m{sup 3} en acier inoxydable mise en place et ancree dans un puits betonne et cuvele en acier inoxydable. Chaque cuve comporte un couvercle standard sur lequel sont rassembles tous les dispositifs annexes standardises eux aussi. Les nouvelles cuves sont donc sures, interchangeables, les puits sont faciles a decontaminer et le travail dans un puits est possible sans crainte d'irradiation du personnel par les cuves voisines. (auteur)

  18. Radioactive waste disposal; Le stockage des dechets radioactifs (aspects non techniques)

    Energy Technology Data Exchange (ETDEWEB)

    Petit, J.C

    1998-04-01

    A deep gap, reflecting a persisting fear, separates the viewpoints of the experts and that of the public on the issue of the disposal of nuclear WASTES. The history of this field is that of the proliferation with time of spokesmen who pretend to speak in the name of the both humans and non humans involved. Three periods can be distinguished: 1940-1970, an era of contestation and confusion when the experts alone represents the interest of all; 1970-1990, an era of contestation and confusion when spokespersons multiply themselves, generating the controversy and the slowing down of most technological projects; 1990-, an era of negotiation, when viewpoints, both technical and non technical, tend to get closer and, let us be optimistic, leading to the overcome of the crisis. We show that, despite major differences, the options and concepts developed by the different actors are base on two categories of resources, namely Nature and Society, and that the consensus is built up through their `hydridation`. we show in this part that the perception of nuclear power and, in particular of the underground disposal of nuclear wastes, involves a very deep psychological substrate. Trying to change mentalities in the domain by purely scientific and technical arguments is thus in vain. The practically instinctive fear of radioactivity, far from being due only to lack of information (and education), as often postulated by scientists and engineers, is rooted in archetypical structures. These were, without doubt, reactivated in the 40 s by the traumatizing experience of the atomic bomb. In addition, anthropological-linked considerations allow us to conclude that he underground disposal of wastes is seen as a `rape` and soiling of Mother Earth. This contributes to explaining, beyond any rationality, the refusal of this technical option by some persons. However, it would naturally be simplistic and counter-productive to limit all controversy in this domain to these psychological aspects. (author)

  19. The cobalt radioactive isotopes in environment; Les isotopes radioactifs du cobalt dans l'environnement

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    For the year 1993 the total activity released in cobalt is 69 GBq for the whole of nuclear power plants. The part of activity in cobalt for La Hague in 1993 is 8 GBq of {sup 58}Co and 2 GBq of {sup 60}Co. The radioactive isotopes released by nuclear power plants or the reprocessing plant of La Hague under liquid effluents are shared by half between {sup 58}Co and {sup 60}Co. The exposure to sealed sources is the most important risk for the cobalt. The risk of acute exposure can associate a local irradiation of several decades of grays inducing a radiological burns, deep burn to treat in surgery by resection or graft even amputation. A global irradiation of organism for several grays induces an acute irradiation syndrome, often serious. At long term the stochastic effects are represented by leukemia and radio-induced cancers. The increase of probability of their occurrence is 1% by sievert. We must remind that the natural spontaneous probability is 25%. (N.C.)

  20. Half-life distribution table of radioactive nuclei; Table de distribution des periodes des noyaux radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Gugenberger, P. [Commissariat a l' Energie Atomique, Saclay(France). Centre d' Etudes Nucleaires

    1954-07-01

    This table allows to identify an element if its period is known. Data for this table were taken from the half-life values adopted by Hollander, PERLMAN and SEABORG (Rev. mod. Phys., 1953, 22 number 2). Moreover for each nucleus, the mass number, the charge number and the type of decay are given in the table. (author) [French] Cette table permet l'identification d'un element dont la periode est connue. Elle a ete etablie en utilisant les valeurs des periodes donnees par HOLLANDER, PERLMAN et SEABORG dans Rev. mod. Phys., 1953, 25 numero 2. On y trouve en outre, pour chaque nuclide, les caracteristiques suivantes: Z, A, modes de desintegration. (auteur)

  1. The management of radioactive wastes from small producers; La gestion des dechets radioactifs des petits producteurs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-01-01

    Medicine, research and industry generate various type of radioactive wastes which have to be managed by the ANDRA, the French agency for the management of radioactive wastes. This educative booklet explains the missions of the ANDRA with respect to these small producers: collection, selection, conditioning, control and storage of wastes. (J.S.)

  2. Le nouvel anneau du CERN rendra le sous-sol genevois radioactif

    CERN Multimedia

    Merckling, Nicolas

    2007-01-01

    As of next spring, the undergrounds in Geneva and Pays de Gex will radioactive around the biggest particle physics laboratory in the world. No danger for the population, say the scientists. (1/2 page)

  3. Descriptive catalogue of radioactive waste families; Catalogue descriptif des familles de dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    This document describes the different types of radioactive wastes produced in France or which are expected to be produced in the future. The wastes have been shared into different families having similar characteristics. A description is made for each family: general presentation, photos, position of the family in the French classification, industrial origin, status of production. Some informations about the raw waste and its conditioning process are also given. The qualitative description is completed by some numerical data like: the quantity produced in the past and to be produced in the future, the evaluation of the radioactivity in 2002 and 2020, and the evaluation of the thermal power when it exists. Finally, some informations are given about the risk of toxicity of some chemical species or compounds. (J.S.)

  4. The electrical charging of inactive aerosols in high ionised atmosphere, the electrical charging of artificial beta radioactive aerosols; Le processus de charge electrique: des aerosols non radioactifs en milieu fortement ionise, des aerosols radioactifs artificiels emetteurs beta

    Energy Technology Data Exchange (ETDEWEB)

    Gensdarmes, F

    2000-07-01

    The electrical properties of aerosols greatly influence their transport and deposition in a containment. In a bipolar ionic atmosphere, a neutral electric charge on aerosols is commonly assumed. However, many studies report a different charge distribution in some situations, like highly ionised atmosphere or in the case of radioactive aerosols. Such situations could arise from a hypothetical accident in a nuclear power plant. Within the framework of safety studies which are carried out at IPSN, our aims were the study of electrical properties of aerosols in highly ionised atmosphere, and the study of artificial radioactive aerosols, in order to suggest experimental validation of available theories. For this purpose, we designed an experimental device that allows us to measure non-radioactive aerosol charge distribution under high gamma irradiation, up to 10{sup 4} Gy/h. With our experimental device we also studied the properties of small ions in the medium. Our results show a variation of the charge distribution in highly ionised atmosphere. The charge increases with the dose of gamma ray. We have related this variation with the one of the small ions in the gases, according to theoretical prediction. However, the model overestimates slightly our experimental results. In the case of the radioactive aerosols, we have designed an original experimental device, which allows us to study the charge distribution of a {sup 137}Cs aerosol. Our results show that the electric charging of such aerosols is strongly dependent on evolution parameters in a containment. So, our results underline a great enhancement of self-charging of particles which are sampled in a confined medium. Our results are qualitatively in agreement with the theoretical model; nevertheless the latter underestimates appreciably the self-charging, owing to the fact that wall effects are not taken into account. (author)

  5. National inventory of radioactive wastes and recoverable materials 2006. Descriptive catalogue of radioactive waste families; Inventaire national des dechets radioactifs et des matieres valorisables 2006. Catalogue descriptif des familles de dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    Real comprehensive overview of radioactive wastes, the national inventory of radioactive wastes and recoverable materials describes the situation in France of the wastes that can be conditioned (in their definitive form) or not. It presents also the waste production quantities foreseen for 2010, 2020 and beyond. This document is a complement to the synthesis report and to the geographic inventory of radioactive wastes in France and details the classification of wastes by families (wastes with similar characteristics). For each family of wastes, the description comprises a general presentation and some photos. It comprises also some data such as the position of the family in the French classification, the industrial activity at the origin of the waste, the production situation of the waste in concern (finished, in progress, not started). Some information about the raw waste are given and the conditioning process used is described. Some figures complete the description, like: the past and future production quantities, the evaluation of the radioactivity of the waste family in 2004 and 2020, and the evaluation of the thermal power when available. Finally, some information are given about the presence of compounds with a specific risk of toxicity. (J.S.)

  6. For a national reference inventory of of radioactive wastes; Pour un inventaire national de reference des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-05-01

    This document is the second volume of the report concerning the mission of the ANDRA on the radioactive wastes inventory methodology. It presents the annexes of the mission management, the main channels of wastes production, the existing inventories, the foreign experiments, a first version of the specification of the inventories data management united system, the management system of reprocessing wastes for foreigner customers, order of magnitude, bibliography and glossary. (A.L.B.)

  7. Bio-corrosion for underground disposal of radioactive waste; Biocorrosion en conditions de stockage geologique de dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Libert, M.; Esnault, L. [CEA, DEN/DTN/SMTM/LMTE, 13108 St Paul lez Durance, (France); Esnault, L. [ECOGEOSAFE, Technopole environnement Arbois-Mediterranee, avenue Louis Philibert, 13545 Aix-en-Provence Cedex, (France); Feron, D. [CEA, DEN/DANS/DPC, 91191 Gif-sur-Yvette, (France)

    2011-07-01

    The safety disposal of high level nuclear waste (HLNW) is the major breakthrough allowing socially acceptable development of nuclear energy over the coming decades. The French concept for geological disposal of HLNW is based on a multi-barrier system made by metallic containers confined in natural clay. The main alteration parameter is water arriving on waste after the corrosion of metallic components. The anoxic aqueous corrosion phenomena are studied in order to evaluate the confinement capacity of metallic barriers. The discover of active micro-organisms in deep clayey environments raises the question of the impact of micro-organisms on corrosion parameters due to processes such as 'biologically induced corrosion'. Despite of extreme conditions in deep nuclear geological disposal (redox conditions, high pressure and temperature, irradiation), bacterial activity will adapt and survive in these environments. Anoxic corrosion of nuclear waste containers and radiolysis will produce H{sub 2}, which represents a new energetic source for bacterial development, especially in this environment that contains a low amount of biodegradable organic matter. Besides, the formation of Fe(III)-bearing minerals such as magnetite (Fe{sub 3}O{sub 4}) as corrosion products will provide electron acceptors favouring the development of bacteria. Bio-corrosion studies of nuclear waste disposal need to investigate the activity of hydrogenotrophic bacteria able to reduce iron oxides (passivation layer) or sulfates (iron reducing bacteria and sulfate reducing bacteria) in order to evaluate their impact on the long-term stability of metallic compounds involved in multi-barrier system for high-level nuclear waste containment. (authors)

  8. Intermediate, low, and very low level waste management at ANDRA (agence nationale pour la gestion des dechets radioactifs) in France

    International Nuclear Information System (INIS)

    Senoo, Muneaki

    2005-01-01

    On 28th September in 2004, RANDEC invited Mr. Jean-Louis Tison from ANDRA as a lecturer of the special session of the 16th RANDEC Annual Symposium. An ANDRA-RANDEC technical meeting was held on the next day, where Mr. Vincent Carlier invited from ANDRA, too participated. Here, present status of intermediate, low, and very low level waste management in France is reviewed based on the information which were obtained from the special session of the 16th RANDEC Annual Symposium and the ANDRA-RANDEC technical meeting. In France, ANDRA is implementing radioactive waste management under the following policy; 'Intermediate, low, and very-low-level (ILVLL) waste is managed in order to establish as soon as possible a final disposal system, the temporary or long term storage option being considered only for the high-level waste (HLW) such as the vitrified fission products or particular materials such as some sealed sources for which no final disposal solution still exists.' The Agency is financed on the basis of the 'polluter-pays' principle and contracts its services directly with waste owners. (author)

  9. The high level and long lived radioactive wastes; Les dechets radioactifs a haute activite et a vie longue

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    This report presents the main conclusions of 15 years of researches managed by the CEA. This report is the preliminary version of the 2005 final report. It presents the main conclusions of the actions on the axis 1 and 3 of the law of the 30 December 1991. The synthesis report on the axis 1 concerns results obtained on the long lived radionuclides separation and transmutation in high level and long lived radioactive wastes. the synthesis report on the axis 3 presents results obtained by the processes of conditioning and of ground and underground long term storage. (A.L.B.)

  10. Radioactive waste storage: historical outlook and socio technical analysis; Le stockage des dechets radioactifs: perspective historique et analyse sociotechnique

    Energy Technology Data Exchange (ETDEWEB)

    Petit, J C

    1993-07-01

    The radioactive waste storage remains, in most of the industrialized concerned countries, one extremely debated question. This problem may, if an acceptable socially answer is not found, to create obstacles to the whole nuclear path. This study aim was to analyze the controversy in an historical outlook. The large technological plans have always economical, political, sociological, psychological and so on aspects, that the experts may be inclined to neglect. ``Escape of radioactivity is unlikely, as long as surveillance of the waste is maintained, that is, as long as someone is present to check for leaks or corrosion or malfunctioning of and to take action, if any of these occur. 444 refs., 32 figs.

  11. Contribution to the selection of radioactive tracers for hydrogeology; Contribution a la selection de traceurs radioactifs pour l'hydrogeologie

    Energy Technology Data Exchange (ETDEWEB)

    Lallemand, A [Bureau de recherches geologiques et minieres (BRGM), Paris (France); Grison, G [Commission des Communautes europeennes, Brussels (Belgium)

    1970-09-15

    A systematic study was made of a number of anionic and cationic tracers in different terrains with distinct petrographic characteristics, allowance being made for the various physical and chemical parameters of the environment. The behaviour of 12 tracers ({sup 51}Cr, {sup 59}Fe, {sup 45}Ca, {sup 110}Ag, {sup 24}Na, {sup 137}Cs, {sup 3}H, {sup 32}P, {sup 35}S, {sup 14}C, {sup 131}I, {sup 82}Br) was studied in six types of argillaceous rock (illite, vermiculite, interstratified illite-vermiculite, montmorillonite, attapulgite and kaolinite) and three sand types (siliceous, calcareous and dolomitic) in the presence of three types of water (demineralized, sea-water and various spring waters). On the basis of the results obtained from 5000 tests and measurements made during this study it is possible to select the tracer most suited to the characteristics of the terrain and the type of groundwater. (author) [French] Les travaux effectues ont pour objectif l'etude systematique d'un certain nombre de traceurs anioniques et cationiques sur une serie de terrains a caracteristiques petrographiques bien determinees, compte tenu d'un certain nombre de parametres physiques et chimiques du milieu. Le comportement de douze traceurs ({sup 51}Cr, {sup 59}Fe, {sup 45}Ca, {sup 110}Ag, {sup 24}Na, {sup 137}Cs, {sup 3}H, {sup 32}P, {sup 35}S, {sup 14}C, {sup 131}I et {sup 82}Br) a ete etudie dans six roches argileuses (illite, vermiculite, interstratifie illite-vermiculite, montmorillonite, attapulgite, kaolinite) et trois sables (siliceux, calcaire, dolomitique) en presence de trois types d'eau (demineralisee, eau de mer et diverses eaux de source). Les resultats des 5000 essais et mesures effectues au cours de cette etude permettent de selectionner le traceur repondant le mieux aux caracteristiques du terrain et du type d'eau de la nappe. (author)

  12. Contribution to the Selection of Radioactive Tracers for Hydrogeology; Contribution a la Selection de Traceurs Radioactifs pour l'Hydrogeologie

    Energy Technology Data Exchange (ETDEWEB)

    Lallemand, Andree [Bureau de Recherches Geologiques et Minieres (BRGM), Paris (France); Grison, G. [Commission des Communautes Europeennes, Bruxelles (Belgium)

    1970-09-15

    A systematic study was made of a number of anionic and cationic tracers in different terrains with distinct petrographic characteristics, allowance being made for the various physical and chemical parameters of the environment. The behaviour of 12 tracers ({sup 51}Cr, {sup 59}Fe, {sup 45}Ca, {sup 110}Ag, {sup 24}Na, {sup 137}Cs, {sup 3}H, {sup 32}P, {sup 35}S, {sup 14}C, {sup 131}I, {sup 82}Br) was studied in six types of argillaceous rock (illite, vermiculite, interstratified illite-vermiculite, montmorillonite, attapulgite and kaolinite) and three sand types (siliceous, calcareous and dolomitic) in the presence of three types of water (demineralized, sea-water and various spring waters). On the basis of the results obtained from 5000 tests and measurements made during this study it is possible to select the tracer most suited to the characteristics of the terrain and the type of groundwater. (author) [French] Les travaux effectues ont pour objectif l'etude systematique d'un certain nombre de traceurs anioniques et cationiques sur une serie de terrains a caracteristiques petrographiques bien determinees, compte tenu d'un certain nombre de parametres physiques et- chimiques du milieu. Le comportement de douze traceurs ({sup 51}Cr, {sup 59}Fe, {sup 45}Ca, {sup 110}Ag, {sup 24}Na, {sup 137}Cs, {sup 3}H, {sup 32}P, {sup 35}S, {sup 14}C, {sup 131}I et {sup 82}Br) a ete etudie dans six roches argileuses (illite, vermiculite, interstratifie illite-vermiculite, montmorillonite, attapulgite, kaolinite) et trois sables (siliceux, calcaire, dolomitique) en presence de trois types d'eau (demineralisee, eau de mer et diverses eaux de source). Les resultats des 5000 essais et mesures effectues au cours de cette etude permettent de selectionner le traceur repondant le mieux aux caracteristiques du terrain et du type d'eau de la nappe. (author)

  13. 1 Étude des marées océaniques et environnementale radioactif de ...

    African Journals Online (AJOL)

    ASIMANANA

    Etude oceanic tide end environment radioactive the bay the diego-suarez. Post analysis of three samples taken in the Bay of Diego Suarez specifically in the English pool, we find or we notice that fortunately the Bay of Diego Suarez is unpolluted and we must continue the conquest to convince people not to throw waste in ...

  14. Radioactive waste: the poisoned legacy of the nuclear industry; Dechets radioactifs: l'heritage empoisonne du nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Rousselet, Y. [Campagne Climat/Energie - Greenpeace (France)

    2011-02-15

    The nuclear industry produces a huge amount of radioactive waste from one end to the other of the nuclear cycle: i.e. from mining uranium to uranium enrichment through reactor operating, waste reprocessing and dismantling nuclear power plants. Nuclear power is now being 'sold' to political leaders and citizens as an effective way to deal with climate change and ensure security of energy supplies. Nonetheless, nuclear energy is not a viable solution and is thus a major obstacle to the development of clean energy for the future. In addition to safety and security issues, the nuclear industry is, above all, faced with the huge problem of how to deal with the waste it produces and for which it has no solution. This ought to put a brake on the nuclear industry, but instead, against all expectations, its development continues to gather pace. (author)

  15. Where are the radioactive wastes in France? Brochure no 1; Ou sont les dechets radioactifs en France? Brochure no 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    This document is one of the 6 regional brochures which make the geographical inventory of radioactive wastes in France. For each region, a table lists the recorded sites and a regional map localizes those having a detailed descriptive file. These files mention the most important waste owners (medical, research, nuclear and military industries), the type of waste and the type of management. The polluted sites are also mentioned, even if they are already decontaminated. The volume no 1 concerns the Ile-de-France region (Paris region). (J.S.)

  16. A very high energy imaging for radioactive wastes processing; Une imagerie haute energie pour la gestion des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Moulin, V. [CEA Grenoble, Lab. d' Electronique et de Technologie de l' Informatique (DRT/DSIS/SSBS/LETI), 38 (France); Pettier, J.L. [CEA Cadarache, Dir. de l' Energie Nucleaire (DEN/DTN/SMTM), 13 - Saint-Paul-lez-Durance (France)

    2004-07-01

    The X imaging occurs at a lot of steps of the radioactive wastes processing: selection for conditioning, physical characterization with a view to radiological characterization, quality control of the product before storage, transport or disposal. Size and volume of the objects considered here necessitate to work with very high energy systems. Here is shown, through some examples, in which conditions this X imaging is carried out as well as the contribution of the obtained images. (O.M.)

  17. Étude des effets d'irradiation dans les montmorillonites. Application au stockage des déchets radioactifs.

    OpenAIRE

    Sorieul , Stéphanie

    2003-01-01

    Smectite is a major component of bentonite, a material considered for engineered barriers in high level nuclear wastes repositories (HLNWR). In order to predict the long-term performance of the bentonite, various physical and chemical factors such as, e.g., thermal gradient, redox potential or mechanical stresses are currently considered. By contrast, little is known about radiation effects in smectite, although it might affect the properties of this mineral through cumulative radiation damag...

  18. Industrial radioactive wastes: what are we talking about?; Les dechets radioactifs industriels: de quoi s'agit-il?

    Energy Technology Data Exchange (ETDEWEB)

    Le Bars, Y. [Agence Nationale pour la Gestion des Dechets Radioactifs ANDRA, 92 - Chatenay Malabry (France)

    2001-07-01

    The subject of radioactive wastes is developed through their origin, their classification, their scale of size. The different storage centers are given and the new channels of radioactive wastes management are tackled. The particular case of high level and long term radioactive wastes is detailed. (N.C.)

  19. Where are the radioactive wastes in France? Brochure no 3; Ou sont les dechets radioactifs en France? Brochure no 3

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    This document is one of the 6 regional brochures which make the geographical inventory of radioactive wastes in France. For each region, a table lists the recorded sites and a regional map localizes those having a detailed descriptive file. These files mention the most important waste owners (medical, research, nuclear and military industries), the type of waste and the type of management. The polluted sites are also mentioned, even if they are already decontaminated. The volume no 3 concerns the Nord-Pas-de-Calais, Picardie, Champagne-Ardenne, Bourgogne, Alsace, Lorraine, Franche-Comte regions. (J.S.)

  20. The radioactive wastes management of the little nuclear industry; La gestion des dechets radioactifs du nucleaire diffus

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    Among the ANDRA customers, more than one million are little producers: hospital, research centers and industries. They are called little producers because of the low volume of produced wastes. Meanwhile these wastes management need an appropriate technology which is presented in this document. (A.L.B.)

  1. Radioactive wastes management. The consequences of the public debate; Gestion des dechets radioactifs. Les suites du debat public

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    The French law from December 30, 1991 has defined an ambitious 15 years program of researches in order to explore the different possible paths for the long-term management of long-lived high and intermediate level radioactive wastes. The law foresees also that at the end of the 15 years research program, in 2006, a project of law will be prepared by the French government and transmitted to the European parliament. A public debate has been organized and emceed in 2005 in order dialogue with the general public and to gather its questions, remarks and fears. This document presents the decisions that the government wishes to take according to the different points discussed during the debate: implementing a national waste management policy for the overall radioactive materials and wastes, reinforcing the tools of this national policy, confirming the prohibition of storing foreign wastes, broadening ANDRA's missions, continuing and reinforcing researches evaluation, creating an independent nuclear safety authority, securing the financing of nuclear charges, sharing information with the public, reinforcing the role of the local information and follow-up committee, institutionalizing the local information commissions, reinforcing nuclear transparency, defining a waste disposal reference solution (long-duration reversible storage), continuing the researches along the three paths defined, defining a decision process, implementing a progressive and monitored disposal solution, sustaining economically the regions which have endorsed the setting up of a nuclear facility in their territory. Some pedagogical files about the research programs, the inventory of wastes, the separation-transmutation, the underground disposal and the sub-surface storage are attached at the end of the document. (J.S.)

  2. Where are the radioactive wastes in France? Brochure no 2; Ou sont les dechets radioactifs en France? Brochure no 2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    This document is one of the 6 regional brochures which make the geographical inventory of radioactive wastes in France. For each region, a table lists the recorded sites and a regional map localizes those having a detailed descriptive file. These files mention the most important waste owners (medical, research, nuclear and military industries), the type of waste and the type of management. The polluted sites are also mentioned, even if they are already decontaminated. The volume no 2 concerns the Bretagne (Brittany), Pays de la Loire, Haute-Normandie, Basse-Normandie and Centre regions. (J.S.)

  3. A rapid method of dosing plutonium in radioactive effluents; Methode de dosage rapide du plutonium dans les effluents radioactifs (1961)

    Energy Technology Data Exchange (ETDEWEB)

    Scheidhauer, J; Messainguiral, L [Commissariat a l' Energie Atomique, Centre de Production de Plutonium, Marcoule (France). Centre d' Etudes Nucleaires

    1961-07-01

    The plutonium is first separated by a lanthanum fluoride precipitation. The precipitated fluorides are dissolved in normal nitric acid solution in the presence of aluminium nitrate. The plutonium transformed to the tetravalent state is then extracted with thenoyltrifluoroacetone and returned to the aqueous phase with 10 N nitric acid. After evaporation on a watch glass the residue is calcined on a Meker burner and counted using a counting system fitted with a zinc sulphide scintillator. When necessary, the calcium is eliminated at the beginning of the dosage by a fluoride precipitation, the plutonium being oxidised to the valency IV. (authors) [French] Le plutonium est d'abord separe par entrainement au fluorure de lanthane. Le precipite des fluorures est remis en solution en milieu acide nitrique normal, en presence de nitrate d'aluminium. Le plutonium amene a la valence IV est alors extrait par la thenoyltrifluoroacetone et remis en phase aqueuse dans l'acide nitrique 10 N. Apres evaporation sur verre de montre, le residu est calcine sur bec Meker et compte sur un ensemble de comptage equipe d'un scintillateur au sulfure de zinc. Lorsque cela est necessaire, le calcium est elimine, au debut du dosage, par precipitation du fluorure, le plutonium etant oxyde a la valence VI. (auteurs)

  4. Where are the radioactive wastes in France? Brochure no 5; Ou sont les dechets radioactifs en France? Brochure no 5

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    This document is one of the 6 regional brochures which make the geographical inventory of radioactive wastes in France. For each region, a table lists the recorded sites and a regional map localizes those having a detailed descriptive file. These files mention the most important waste owners (medical, research, nuclear and military industries), the type of waste and the type of management. The polluted sites are also mentioned, even if they are already decontaminated. The volume no 5 concerns the Languedoc-Roussillon and Provence-Alpes-Cote d'Azur regions, Corsica, and the overseas departements and territories. (J.S.)

  5. National inventory of the radioactive wastes and the recycling materials; Inventaire national des dechets radioactifs et des matieres valorisables

    Energy Technology Data Exchange (ETDEWEB)

    Dupuis, M.C

    2006-07-01

    This synthesis report presents the 2006 inventory of the radioactive wastes and recycling materials, in France. It contains 9 chapters: a general introduction, the radioactive wastes (definition, classification, origins and management), the inventory methodology (organization, accounting and prospecting, exhaustiveness and control tools), main results (stocks, prevision for the period 2005-2020, perspectives after 2020), the inventory for producers or owners (front end fuel cycle, electric power plants, back end fuel cycle, wastes processing and maintenance facilities, researches centers, medical activities, industrial activities, non nuclear industries using nuclear materials, defense center, storage and disposal), the polluted sites, examples of foreign inventories, conclusion and annexes. (A.L.B.)

  6. Where are the radioactive wastes in France? Brochure no 6; Ou sont les dechets radioactifs en France? Brochure no 6

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    This document is one of the 6 regional brochures which make the geographical inventory of radioactive wastes in France. For each region, a table lists the recorded sites and a regional map localizes those having a detailed descriptive file. These files mention the most important waste owners (medical, research, nuclear and military industries), the type of waste and the type of management. The polluted sites are also mentioned, even if they are already decontaminated. The volume no 6 concerns the Aquitaine, Limousin, Midi-Pyrenees and Poitou-Charentes regions. (J.S.)

  7. Where are the radioactive wastes in France? Brochure no 4; Ou sont les dechets radioactifs en France? Brochure no 4

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    This document is one of the 6 regional brochures which make the geographical inventory of radioactive wastes in France. For each region, a table lists the recorded sites and a regional map localizes those having a detailed descriptive file. These files mention the most important waste owners (medical, research, nuclear and military industries), the type of waste and the type of management. The polluted sites are also mentioned, even if they are already decontaminated. The volume no 4 concerns the Auvergne and Rhone-Alpes regions. (J.S.)

  8. Origin of the {sup 238}U-{sup 230}Th disequilibrium in magmas from subduction zones: the Arenal example; Origine du desequilibre {sup 238}U-{sup 230}TH dans les magmas des zones de subduction: exemple de l`Arenal

    Energy Technology Data Exchange (ETDEWEB)

    Villemant, B [Paris-6 Univ., 75 (France)

    1997-12-31

    The existence in some volcanic products of strong excess of {sup 238}U with respect to {sup 230}Th is one of the characteristics of volcanic arc magmas. These excesses are generally attributed to fluid additions inside mantellic sources before magma segregation, differentiation and eruption. These fluids should be linked to the dehydration of the subducted rocks. These hypotheses are essentially based on correlations between {sup 10}Be, {sup 87}Sr anomalies, Ba/La ratios and on the distribution of volcanic centers with respect to the subduction zone. Recent studies suggest an evolution of the composition of volcanic sources in Central America from a depleted mantle type (MORB) in the North (Nicaragua) to a less transformed enriched type (OIB) in the South (Costa Rica). The Arenal volcano belongs to a transition zone between these two types. The preliminary study of trace elements and {sup 238}U-{sup 230}Th disequilibria in recent volcanic products (1968-1993) indicates a more complex situation. At least two different mantle sources were successively involved characterized by different Th/La and La/Yb ratios and very different to the OIB type. Also most lavas are in equilibrium with {sup 238}U/{sup 232}Th ratios of about 1.2 to 1.3. However, in eruptive cycle, some lavas are characterized by a strong {sup 238}U excess with respect to {sup 230}Th with cannot be linked to the sources, even when modified by fluids in depth. These results are interpreted in terms of heterogeneities of mantle sources and low depths late interactions with hydrothermal fluids during eruptions. Abstract only. (J.S.). 2 refs.

  9. Uranium series geochemistry in aquifers: quantification of transport mechanisms of uranium and daughter products: the chalk aquifer (Champagne, France); Desequilibres des series de l'uranium dans les aquiferes: quantification des mecanismes de transport de l'uranium et de ses descendants: cas de l'aquifere de la craie (Champagne, France)

    Energy Technology Data Exchange (ETDEWEB)

    Hubert, A

    2005-09-15

    With the increase of contaminant flux of radionuclides in surface environment (soil, river, aquifer...), there is a need to understand and model the processes that control the distribution of uranium and its daughter products during transport within aquifers. We have used U-series disequilibria as an analogue for the transport of uranium and its daughter products in aquifer to understand such mechanisms. The measurements of uranium ({sup 234}U et {sup 238}U), thorium ({sup 230}Th et {sup 232}Th), {sup 226}Ra and {sup 222}Rn isotopes in the solid and liquid phases of the chalk aquifer in Champagne (East of France) allows us to understand the processes responsible for fractionation within the uranium decay chain. Fractionations are induced by physical and chemical properties of the elements (leaching, adsorption) but also by radioactive properties (recoil effect during {alpha}-decay). For the first time a comprehensive sampling of the solid phase has been performed, allowing quantifying mechanisms responsible for the long term evolution of the aquifer. A non steady state 1D model has been developed which takes into account leaching, adsorption processes as well as radioactive filiation and {alpha}-recoil effect. Retardation coefficients have been calculated for uranium, thorium and radium. The aquifer is characterised by a double porosity, and the contribution of fracture and matrix porosity on the water/rock interaction processes has been estimated. (author)

  10. Origin of the {sup 238}U-{sup 230}Th disequilibrium in magmas from subduction zones: the Arenal example; Origine du desequilibre {sup 238}U-{sup 230}TH dans les magmas des zones de subduction: exemple de l`Arenal

    Energy Technology Data Exchange (ETDEWEB)

    Villemant, B. [Paris-6 Univ., 75 (France)

    1996-12-31

    The existence in some volcanic products of strong excess of {sup 238}U with respect to {sup 230}Th is one of the characteristics of volcanic arc magmas. These excesses are generally attributed to fluid additions inside mantellic sources before magma segregation, differentiation and eruption. These fluids should be linked to the dehydration of the subducted rocks. These hypotheses are essentially based on correlations between {sup 10}Be, {sup 87}Sr anomalies, Ba/La ratios and on the distribution of volcanic centers with respect to the subduction zone. Recent studies suggest an evolution of the composition of volcanic sources in Central America from a depleted mantle type (MORB) in the North (Nicaragua) to a less transformed enriched type (OIB) in the South (Costa Rica). The Arenal volcano belongs to a transition zone between these two types. The preliminary study of trace elements and {sup 238}U-{sup 230}Th disequilibria in recent volcanic products (1968-1993) indicates a more complex situation. At least two different mantle sources were successively involved characterized by different Th/La and La/Yb ratios and very different to the OIB type. Also most lavas are in equilibrium with {sup 238}U/{sup 232}Th ratios of about 1.2 to 1.3. However, in eruptive cycle, some lavas are characterized by a strong {sup 238}U excess with respect to {sup 230}Th with cannot be linked to the sources, even when modified by fluids in depth. These results are interpreted in terms of heterogeneities of mantle sources and low depths late interactions with hydrothermal fluids during eruptions. Abstract only. (J.S.). 2 refs.

  11. National plan for the radioactive and recyclable wastes management of the national inventory of the radioactive and recyclable wastes to an account and a prospective outlook of the pathways of long dated management of radioactive wastes in France; Plan national de gestion des dechets radioactifs et des matieres valorisables de l'inventaire national des dechets radioactifs et des matieres valorisable a un bilan et une vision prospective des filieres de gestion a long terme des dechets radioactifs en France

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-15

    The introduction recalls the context of the development of the national plan of radioactive and recyclable wastes management (PNGDR-MV), its objectives and its position in the today studies on radioactive wastes. The first part is devoted to the description of existing radioactive wastes management solutions, or engaged by today activities. The second part concerns the radioactive materials of the nuclear industry, which are not considered as wastes, but which can be recyclable because of their high energy potential as fuels for reactors of the future. The third part examines the pathways coherence. The last part is a synthesis of the evaluation, with more attention on the identifies problems. (A.L.B.)

  12. National plan for the radioactive and recyclable wastes management of the national inventory of the radioactive and recyclable wastes to an account and a prospective outlook of the pathways of long dated management of radioactive wastes in France; Plan national de gestion des dechets radioactifs et des matieres valorisables de l'inventaire national des dechets radioactifs et des matieres valorisable a un bilan et une vision prospective des filieres de gestion a long terme des dechets radioactifs en France

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-15

    The introduction recalls the context of the development of the national plan of radioactive and recyclable wastes management (PNGDR-MV), its objectives and its position in the today studies on radioactive wastes. The first part is devoted to the description of existing radioactive wastes management solutions, or engaged by today activities. The second part concerns the radioactive materials of the nuclear industry, which are not considered as wastes, but which can be recyclable because of their high energy potential as fuels for reactors of the future. The third part examines the pathways coherence. The last part is a synthesis of the evaluation, with more attention on the identifies problems. (A.L.B.)

  13. Minerals and design of new waste forms for conditioning nuclear waste; Les mineraux et la formulation de nouvelles matrices de stockage pour les dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Montel, J.M. [G2R, CNRS, Ecole nationale superieure de geologie, Nancy-universite, BP 70239, 54056 Vandoeuvre-les-Nancy (France)

    2011-02-15

    Safe storage of radioactive waste is a major challenge for the nuclear industry. Mineralogy is a good basis for designing ceramics, which could eventually replace nuclear glasses. This requires a new storage concept: separation-conditioning. Basic rules of crystal chemistry allow one to select the most suitable structures and natural occurrences allow assessing the long-term performance of ceramics in a geological environment. Three criteria are of special interest: compatibility with geological environment, resistance to natural fluids, and effects of self-irradiation. If mineralogical information is efficient for predicting the behaviour of common, well-known minerals, such as zircon, monazite or apatite, more research is needed to rationalize the long-term behaviour of uncommon waste form analogs. (author)

  14. The irradiation alterations in non radioactive materials: mineralogic and environmental implications; Les degats d irradiation dans les mineraux non radioactifs: implications mineralogiques et environnementales

    Energy Technology Data Exchange (ETDEWEB)

    Calas, G.; Allard, T.; Morin, G. [Institut de Mineralogie et de Physique des Milieux Condenses, Paris, (France); Balan, E. [IRD, Paris (France)

    2006-07-01

    This work presents an outlook of the results obtained on different types of defects in a wide series of minerals. The trapping of irradiation defects by substituted impurities will be illustrated by natural fluorines and apatites, allowing then to illustrate the use of these data to better know the thermal history of minerals or the role of the trace elements to stabilize these defects on geological period of times. Are also presented the native defects of clayey minerals, in relation to the natural irradiation of their alumino-silicated lattice, as in the case of kaolinite or montmorillonite. Here also, the presence of substituted impurities allows to explain the stability of these centers on geological period of times. (O.M.)

  15. Modelling of nuclear glasses by classical and ab initio molecular dynamics; Modelisation de verres intervenant dans le conditionnement des dechets radioactifs par dynamiques moleculaires classique et ab initio

    Energy Technology Data Exchange (ETDEWEB)

    Ganster, P

    2004-10-15

    A calcium aluminosilicate glass of molar composition 67 % SiO{sub 2} - 12 % Al{sub 2}O{sub 3} - 21 % CaO was modelled by classical and ab initio molecular dynamics. The size effect study in classical MD shows that the systems of 100 atoms are more ordered than the larger ones. These effects are mainly due to the 3-body terms in the empirical potentials. Nevertheless, these effects are small and the structures generated are in agreement with experimental data. In such kind of glass, we denote an aluminium avoidance and an excess of non bridging oxygens which can be compensated by tri coordinated oxygens. When the dynamics of systems of 100 and 200 atoms is followed by ab initio MD, some local arrangements occurs (bond length, angular distributions). Thus, more realistic vibrational properties are obtained in ab initio MD. The modelling of thin films shows that aluminium atoms extend to the most external part of the surface and they are all tri-coordinated. Calcium atoms are set in the sub layer part of the surface and they produce a depolymerization of the network. In classical MD, tri-coordinated aluminium atoms produce an important electric field above the surface. With non bridging oxygens, they constitute attractive sites for single water molecules. (author)

  16. Development of new non destructive methods for bituminized radioactive waste drums characterization; Developpement de nouvelles methodes de caracterisation non destructive pour des dechets radioactifs enrobes dans du bitume

    Energy Technology Data Exchange (ETDEWEB)

    Pin, P

    2004-10-15

    Radioactive waste constitute a major issue for the nuclear industry. One of the key points is their characterization to optimize their management: treatment and packaging, orientation towards the suited disposal. This thesis proposes an evaluation method of the low-energy photon attenuation, based on the gamma-ray spectra Compton continuum. Effectively, the {sup 241}Am measurement by gamma-ray spectrometry is difficult due to the low energy of its main gamma-ray (59.5 keV). The photon attenuation strongly depends on the bituminous mix composition, which includes very absorbing elements. As the Compton continuum also depends on this absorption, it is possible to link the 59.5 keV line attenuation to the Compton level. Another technique is proposed to characterize uranium thanks to its fluorescence X-rays induced by the gamma emitters already present in the waste. The uranium present in the drums disturbs the neutron measurements and its measurement by self-induced X-ray fluorescence allows to correct this interference. Due to various causes of error, the total uncertainty is around 50 % on the activity of the radioisotope {sup 241}Am, corrected by the peak to Compton technique. The same uncertainty is announced on the uranium mass measured by self induced X-ray fluorescence. As a consequence of these promising results, the two methods were included in the industrial project of the 'Marcoule Sorting Unit'. One major advantage is that they do not imply any additional material because they use information already present in the gamma-ray spectra. (author)

  17. The nuclear installations dismantling and the management of radioactive wastes; Le demantelement des installations nucleaires et la gestion des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-01-15

    As other industrial activities, the nuclear industry causes risks. The risks bound to the dismantling operations are known and controlled. After a presentation of the dismantling and radioactive wastes challenge, this document proposes recommendations based on the first experiences of dismantling and wastes storage. It aims then to answer to the questions relative to the cost and the financing of the operations. Finally it wonders on the public information modalities. (A.L.B.)

  18. Study of radioactive nuclides of very short half-life produced by fast neutrons; Etude de corps radioactifs a vie tres breve produits par neutrons rapides

    Energy Technology Data Exchange (ETDEWEB)

    Monnand, E [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

    1965-07-01

    Several radionuclides, already known, with half-lives ranging from 5 10{sup -5} to 1 second were observed by pulsed irradiations of C - Mg - Al - Y - In - Tl - Pb - Bi with 14.3 MeV neutrons. These radionuclides are: {sup 12}B (20 {+-} 0.4 ms) - {sup 24m}Na (20 {+-} 0.6 ms) - {sup 88m1}Y (0.332 {+-} 0.012 ms) - {sup 88m2}Y (14.6 {+-} 0.4 ms) - {sup 114m}In (43.5 {+-} 2 ms) - {sup 202m}Tl (0.570 {+-} 0.010 ms) - {sup 204m}Tl (0.063 {+-} 0.002 ms) - {sup 205m}Pb (5.5 {+-}0.3 ms) - {sup 206m}Pb (0.126 {+-} 0.006 ms) - {sup 207m}Pb (830 {+-} 30 ms) - {sup 208m}Bi (2.56 {+-} 0.1 ms). Their half-life, the {beta} and {gamma} rays energies and the production cross sections were measured. (author) [French] Plusieurs radionucleides deja connus, de periode comprise entre 5 10{sup -5} et 1 seconde ont ete observes par irradiation pulsee avec des neutrons de 14,3 MeV, des elements suivants: C - Mg - Al - Y - In - Tl - Pb - Bi. Ces radionucleides sont: {sup 12}B (20 {+-} 0.4 ms) - {sup 24m}Na (20 {+-} 0.6 ms) - {sup 88m1}Y (0.332 {+-} 0.012 ms) - {sup 88m2}Y (14.6 {+-} 0.4 ms) - {sup 114m}In (43.5 {+-} 2 ms) - {sup 202m}Tl (0.570 {+-} 0.010 ms) - {sup 204m}Tl (0.063 {+-} 0.002 ms) - {sup 205m}Pb (5.5 {+-}0.3 ms) - {sup 206m}Pb (0.126 {+-} 0.006 ms) - {sup 207m}Pb (830 {+-} 30 ms) - {sup 208m}Bi (2.56 {+-} 0.1 ms). Leur periode, l'energie des rayonnements {beta} et {gamma} emis, et la section efficace de production ont ete mesurees. (auteur)

  19. Production of chemically reactive radioactive ion beams through on-line separation; Production de faisceaux d'ions radioactifs chimiquement reactifs par separation en ligne

    Energy Technology Data Exchange (ETDEWEB)

    Joinet, A

    2003-10-01

    The ISOL (isotope separation on line) allows the production of secondary radioactive ion beams through spallation or fragmentation or fission reactions that take place in a thick target bombarded by a high intensity primary beam. The challenge is to increase the intensity and purity of the radioactive beam. The optimization of the system target/source requires the right choice of material for the target by taking into account the stability of the material, its reactivity and the ionization method used. The target is an essential part of the system because radioactive elements are generated in it and are released more or less quickly. Tests have been made in order to select the best fitted material for the release of S, Se, Te, Ge and Sn. Materials tested as target filling are: ZrO{sub 2}, Nb, Ti, V,TiO{sub 2}, CeO{sub x}, ThO{sub 2}, C, ZrC{sub 4} and VC). Other molecules such as: COSe, COS, SeS, COTe, GeS, SiS, SnS have been studied to ease the extraction of recoil nuclei (Se, S, Te, Ge and Sn) produced inside the target.

  20. Radio-active colloids in the functional exploration of the reticulo-endothelium system; Les colloides radioactifs dans l'exploration fonctionnelle du systeme reticulo-endothelial

    Energy Technology Data Exchange (ETDEWEB)

    Chivot, J.J. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1967-03-01

    A historical review describes the reticulo-endothelial system (R.E.S.) and aims at defining it and at explaining its operation. The methods used for its examination and the colloids utilized are considered. The author has been led to prepare a special type of colloid: an albuminous complex containing radio-iodine, 'C.A. {sup 131}I', whose method of preparation and physical and biological examination are described. A human albumin, having a known optical density in solution, is heated until a change in the optical density indicates that an aggregation of the proteinic molecules has occurred. The denatured protein is iodated with {sup 131}I. Electrophoretic, ultracentrifuge and autoradiographic controls are then carried out. This atoxic and metabolisable preparation of biological origin is compared with the better defined colloidal gold which serves as reference. C.A.{sup 131}I is injected into mice. It is shown by radioactivity measurements, auto-radiographies on sections of the whole animal, and anthropo-gamma-metric detections that a high concentration occurs in the S.R.E. of the liver. These static results are only of limited importance however compared to those obtained from an in vivo study of the phenomenon. The author records the changes in the radioactivity of the blood derived from the carotid artery using a well-scintillator. He obtains directly a curve of the radioactivity of blood having a decreasing exponential form; the mathematical expression describing this curve is given. The biological half-life T 1/2 of the colloid in the blood is a measure of its phagocytosis by the S.R.E. cells. A supplementary check is provided by the direct recording of the hepatic activity using a suitably collimated exterior detector. A curve of increasing-exponential form is obtained and its parameters are corollary to the preceding curve. These tests carried out on guinea-pigs and rats make it possible to give to the S.R.E. a phagocytic index which is characteristic of its state of activity. The phagocytic index K depends also on the diameter of the colloidal particles injected and can be used as biological test for a colloid: this is the percentage of injected colloid which is retained by the S.R.E. per unit time. This index depends on anaesthetics, on the state of inflammation of the organism and on chemical mediators such as histamine. (author) [French] Un rappel historique met en lumiere le systeme reticulo-endothelial S.R.E. et tente d'en preciser l'identite et le fonctionnememt. Les methodes de son exploration et les colloides utilises sont envisages. L'auteur est amene a fabriquer un colloide d'un type particulier: un complexe albuminique radioiode le 'C.A. {sup 131}I' dont il decrit les etapes de la preparation et des essais tant physiques que biologiques. Une albumine humaine, presentant en solution une densite optique definie est portee a la chaleur jusqu'a modification de la densite optique, temoin d'une agregation des molecules proteiques. La proteine denaturee est iodee par {sup 131}I. Des controles d'electrophorese, d'ultracentrifugation et d'autoradiographie sont effectues. Cette preparation d'origine biologique atoxique et metabolisable sera comparee a l'or colloidal mieux defini qui servira de reference. Le C.A.{sup 131}I est injecte a la souris. Des mesures de radioactivite, des autoradiographies de coupe de l'animal entier, des detections de l'anthropogammametre mettent en evidence une concentration importante au niveau du S.R.E. du foie. Mais ces resultats statiques ont une portee limitee en regard de l'exploitation d'une etude cinetique in vivo du phenomene. L'auteur enregistre les variations de la radioactivite du sang derive de la carotide dans un scintillateur a puits. Il obtient directement une courbe de radioactivite sanguine d'allure exponentielle decroissante dont il definit la formule mathematique. La periode biologique T 1/2 du colloide dans le sang est le reflet de sa phagocytose par les cellules du S.R.E. Une verification supplementaire est apportee par l'enregistrement direct de la radioactivite hepatique a l'aide d'un detecteur externe convenablement collimate. Une courbe d'allure exponentielle croissante est obtenue dont les parametres sont corollaires de la courbe precedente. Ces etudes cinetiques effectuees chez le Cobaye et chez le Rat permettent d'attribuer au S.R.F.. un index phagocytaire reflet de son etat d'activite. L'index phagocytaire K depend egalement de la taille des particules colloidales injectees et peut servir de test biologique pour un colloide: c'est le pourcentage de colloide injecte retenu par les cellules du systeme reticulo-endothelial dans l'unite de temps. Cet index est sous la dependance des anesthesiques, de l'etat d'inflammation de l'organisme, et de mediateurs chimiques telle que l'histamine. (auteur)

  1. Underwater behaviour of bitumen coated radioactive wastes: experimental validation of the Colonbo degradation model; Comportement sous eau des dechets radioactifs bitumes: validation experimentale du modele de degradation Colonbo

    Energy Technology Data Exchange (ETDEWEB)

    Gwinner, B

    2004-03-01

    In the release scenario considered for geologic repository, water is thought to be the main aggressive agent with regards to bituminized radioactive waste (composed in general of 60 weight % of bitumen, 40% of soluble/insoluble salts and a few ppm of radionuclides). Since liquid water can diffuse in pure bitumen, leaching of bituminized waste results in the dissolution of the most soluble salts and leads to the development of a more or less concentrated saline solution-filled pore structure (called permeable layer). In consequence of the generation of a porous layer in the bituminized waste, leaching of salts and radionuclides can then take place. Research performed at the Atomic Energy Commission (CEA) aims therefore at understanding the consequences of ground-water immersion on the transport properties and radionuclides leaching of bituminized waste materials. To this end, a constitutive model (called COLONBO) which describes mathematically the leaching of bituminized waste has been developed. The COLONBO model is based on the following assumptions: 1. Water and dissolved salts migrate in the permeable layer according to Fick's first law. The diffusion of water and salts are quantified by effective diffusion coefficients which are unknown. 2. The mechanical properties of the bitumen matrix are not considered during leaching (free swelling). Up to now, the COLONBO model has been used only to model experimental water uptake and salt leach curves, leading (theoretical) estimates of the effective diffusion coefficients of water and salts in the permeable layer. The aim of this work was to validate experimentally the numerical results obtained with the COLONBO model. First, the correspondence between experimental and simulated water uptake and salt leach rates obtained on various bituminized waste materials is checked, leading estimates of the effective diffusion coefficients of water and salts in the permeable layer. Second, the evolution of the thickness and of the morphology of the permeable layer of partially leached bituminized waste samples is studied. The porosity and the pore distribution in the permeable layer are quantified according to a semi-automatic method based on the analysis of Environmental Scanning Electron Microscope images. The obtained experimental porosity profiles are compared successfully to those resulting from simulations performed with the COLONBO model. The effective diffusion coefficients of water and salts in the permeable layer of leached bituminized waste samples are then directly measured by through diffusion experiments. In the experiments, the flow of radioactive tracers (water and salts) through thin membranes of partially leached bituminized waste is followed in time. Due to the evolution of the bitumen specimen during the tests (continuous leaching), a specific method of analysis had to be developed to obtain reliable effective diffusion coefficients. The results show that the diffusion coefficients of water and salts increase with the porosity of the permeable layer, as expected from the COLONBO model. Overall, the direct characterization of the transport properties of the permeable layer and of the pore distribution in the permeable layer validate quantitatively the results obtained with the COLONBO model and the underlying hypotheses. Finally, constitutive models describing the leaching of elements from polymer matrices immersed in water have been applied to bituminized waste materials. With respect to COLONBO, these models account for the effect of mechanical properties of polymers on swelling and leach rates. (author)

  2. Law project of program relative to the management of radioactive materials and wastes; Projet de Loi, de programme relatif a la gestion des matieres et des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Villepin, D. de; Breton, T

    2006-03-15

    The law of the 30 December 1991 defined three axis of researches and fixed a the legal aspects of the researches programs management. Based on these researches results a law project has been defined. The first part of the document presents the objectives of the law project and discusses the different articles. The second part is devoted to the text of the law project. (A.L.B.)

  3. {gamma}-spectroscopy and radioactive beams: search for highly deformed exotic nuclei; Detection {gamma} et faisceaux radioactifs: recherche de noyaux exotiques tres deformes

    Energy Technology Data Exchange (ETDEWEB)

    Rosse, B

    2006-07-15

    This work is devoted to the search for highly deformed nuclei under extreme conditions of isospin, located near the proton drip-line, around A {approx} 130. The experiment was performed at GANIL (Caen) with the SPIRAL radioactive beam facility. The nuclei of interest were produced by fusion-evaporation reactions induced by the neutron deficient Kr{sup 76} radioactive beam (T1/2 = 14.8 h). {gamma}-rays were detected by the EXOGAM array, composed of 11 segmented germanium clover detectors, for which a new segment calibration method has been developed. To extract fusion-evaporation events of a overwhelming background due to the radioactivity of the beam, the EXOGAM array was coupled with the light charged particle detector DIAMANT and the high acceptance VAMOS spectrometer. The latter was used for the first time to detect fusion-evaporation residues. The detailed data analysis allowed us to demonstrate that the EXOGAM + DIAMANT + VAMOS coupling is operational and essential to investigate the structure of these nuclei. Furthermore, the first {gamma} transition was observed in the very exotic odd-odd Pm{sup 130} nucleus. The results have been interpreted with static and dynamic self-consistent microscopic calculations in collaboration with the Theoretical Physicists of the IPN Lyon. (author)

  4. Law proposition aiming to organize the sustainable management of radioactive wastes; Proposition de loi tendant a organiser la gestion durable des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Bataille, Ch.; Ayrault, J.M.; Hollande, F.; Dose, F.; Dumont, J.L.; Brottes, F.; Le Deaut, J.Y

    2006-02-15

    In 1991 the France decided to intensify its researches in the high activity radioactive wastes management domain. The law of the 30 December 1991 relative to the radioactive wastes management, decided that a period of 15 years would be devoted to the research of very long dated solutions. This law proposition takes into account these researches results and aims to define a policy of radioactive wastes management in the framework of a sustainable development. The authors present and discuss the different articles of the law proposition. (A.L.B.)

  5. Geological storage of radioactive wastes: governance and practical implementation of the reversibility concept; Stockage geologique de dechets radioactifs: gouvernance et mise en oeuvre pratique du concept de reversibilite

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    2011-01-15

    This document comments the different issues associated with the concept of reversibility in the case of geological disposal of radioactive wastes: adopted approach for investigations on the practical implementation of reversibility, decision and assessment process related to the practical implementation of reversibility, role of local actors in decision and monitoring process on a middle and long term, control and vigilance during the reversibility period, memory preservation and its inter-generational transmission, modalities of financing reversibility and the radioactive waste management system, development of a citizen ability and expertise sharing, and perspectives

  6. Quantitative analysis of strontium 90 in the radioactive wastes by means of thenoyltrifluoroacetone; Dosage du strontium 90 dans les effluents radioactifs par le thenoyltrifluoroacetone

    Energy Technology Data Exchange (ETDEWEB)

    Testemale, G; Leredde, J L [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1970-07-01

    A simple method of analysing the quantity of {sup 90}Sr has been perfected. It consists in a double extraction of it by means of thenoyltrifluoroacetone and tributylphosphate in tetrachloride of carbon followed by eliminating yttrium 90 by means of thenoyltrifluoroacetone in the benzene. Numberings on aliquot parts of wastes make the determination of that element possible. The yield is about 97 per cent. (authors) [French] Une technique simple du dosage du {sup 90}Sr a ete mise au point. Elle consiste en une double extraction par le thenoyltrifluoroacetone et le tributylphosphate dans le tetrachlorure de carbone, suivie de l'elimination de l'yttrium 90 par le thenoyltrifluoroacetone dans le benzene, Des comptages sur des parties aliquotes d'effluents permettent la dermination de cet element. Rendement environ 97 pour cent. (auteurs)

  7. Production of chemically reactive radioactive ion beams through on-line separation; Production de faisceaux d'ions radioactifs chimiquement reactifs par separation en ligne

    Energy Technology Data Exchange (ETDEWEB)

    Joinet, A

    2003-10-01

    The ISOL (isotope separation on line) allows the production of secondary radioactive ion beams through spallation or fragmentation or fission reactions that take place in a thick target bombarded by a high intensity primary beam. The challenge is to increase the intensity and purity of the radioactive beam. The optimization of the system target/source requires the right choice of material for the target by taking into account the stability of the material, its reactivity and the ionization method used. The target is an essential part of the system because radioactive elements are generated in it and are released more or less quickly. Tests have been made in order to select the best fitted material for the release of S, Se, Te, Ge and Sn. Materials tested as target filling are: ZrO{sub 2}, Nb, Ti, V,TiO{sub 2}, CeO{sub x}, ThO{sub 2}, C, ZrC{sub 4} and VC). Other molecules such as: COSe, COS, SeS, COTe, GeS, SiS, SnS have been studied to ease the extraction of recoil nuclei (Se, S, Te, Ge and Sn) produced inside the target.

  8. Radio-active colloids in the functional exploration of the reticulo-endothelium system; Les colloides radioactifs dans l'exploration fonctionnelle du systeme reticulo-endothelial

    Energy Technology Data Exchange (ETDEWEB)

    Chivot, J J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1967-03-01

    A historical review describes the reticulo-endothelial system (R.E.S.) and aims at defining it and at explaining its operation. The methods used for its examination and the colloids utilized are considered. The author has been led to prepare a special type of colloid: an albuminous complex containing radio-iodine, 'C.A. {sup 131}I', whose method of preparation and physical and biological examination are described. A human albumin, having a known optical density in solution, is heated until a change in the optical density indicates that an aggregation of the proteinic molecules has occurred. The denatured protein is iodated with {sup 131}I. Electrophoretic, ultracentrifuge and autoradiographic controls are then carried out. This atoxic and metabolisable preparation of biological origin is compared with the better defined colloidal gold which serves as reference. C.A.{sup 131}I is injected into mice. It is shown by radioactivity measurements, auto-radiographies on sections of the whole animal, and anthropo-gamma-metric detections that a high concentration occurs in the S.R.E. of the liver. These static results are only of limited importance however compared to those obtained from an in vivo study of the phenomenon. The author records the changes in the radioactivity of the blood derived from the carotid artery using a well-scintillator. He obtains directly a curve of the radioactivity of blood having a decreasing exponential form; the mathematical expression describing this curve is given. The biological half-life T 1/2 of the colloid in the blood is a measure of its phagocytosis by the S.R.E. cells. A supplementary check is provided by the direct recording of the hepatic activity using a suitably collimated exterior detector. A curve of increasing-exponential form is obtained and its parameters are corollary to the preceding curve. These tests carried out on guinea-pigs and rats make it possible to give to the S.R.E. a phagocytic index which is characteristic of its state of activity. The phagocytic index K depends also on the diameter of the colloidal particles injected and can be used as biological test for a colloid: this is the percentage of injected colloid which is retained by the S.R.E. per unit time. This index depends on anaesthetics, on the state of inflammation of the organism and on chemical mediators such as histamine. (author) [French] Un rappel historique met en lumiere le systeme reticulo-endothelial S.R.E. et tente d'en preciser l'identite et le fonctionnememt. Les methodes de son exploration et les colloides utilises sont envisages. L'auteur est amene a fabriquer un colloide d'un type particulier: un complexe albuminique radioiode le 'C.A. {sup 131}I' dont il decrit les etapes de la preparation et des essais tant physiques que biologiques. Une albumine humaine, presentant en solution une densite optique definie est portee a la chaleur jusqu'a modification de la densite optique, temoin d'une agregation des molecules proteiques. La proteine denaturee est iodee par {sup 131}I. Des controles d'electrophorese, d'ultracentrifugation et d'autoradiographie sont effectues. Cette preparation d'origine biologique atoxique et metabolisable sera comparee a l'or colloidal mieux defini qui servira de reference. Le C.A.{sup 131}I est injecte a la souris. Des mesures de radioactivite, des autoradiographies de coupe de l'animal entier, des detections de l'anthropogammametre mettent en evidence une concentration importante au niveau du S.R.E. du foie. Mais ces resultats statiques ont une portee limitee en regard de l'exploitation d'une etude cinetique in vivo du phenomene. L'auteur enregistre les variations de la radioactivite du sang derive de la carotide dans un scintillateur a puits. Il obtient directement une courbe de radioactivite sanguine d'allure exponentielle decroissante dont il definit la formule mathematique. La periode biologique T 1/2 du colloide dans le sang est le reflet de sa phagocytose par les cellules du S.R.E. Une verification supplementaire est apportee par l'enregistrement direct de la radioactivite hepatique a l'aide d'un detecteur externe convenablement collimate. Une courbe d'allure exponentielle croissante est obtenue dont les parametres sont corollaires de la courbe precedente. Ces etudes cinetiques effectuees chez le Cobaye et chez le Rat permettent d'attribuer au S.R.F.. un index phagocytaire reflet de son etat d'activite. L'index phagocytaire K depend egalement de la taille des particules colloidales injectees et peut servir de test biologique pour un colloide: c'est le pourcentage de colloide injecte retenu par les cellules du systeme reticulo-endothelial dans l'unite de temps. Cet index est sous la dependance des anesthesiques, de l'etat d'inflammation de l'organisme, et de mediateurs chimiques telle que l'histamine. (auteur)

  9. Research and development for the production of radioactive ions for SPIRAL; Recherche et developpement concernant la production d'ions radioactifs dans le cadre de SPIRAL

    Energy Technology Data Exchange (ETDEWEB)

    Eleon, C

    2007-12-15

    This thesis is related to the research and development program for the production of radioactive ion beams by the ISOL method for SPIRAL at GANIL. Two studies concerning improvements to the performance of SPIRAL target-source system have been made, using a statistical approach to the atoms-to-ions transformation. The first study concerns the transformation time between the production of the radioactive atoms of Ar{sup 35} inside a target and the extraction of the radioactive ions from the source with the TARGISOL set-up (target + ECR source). The goal was to determine the diffusion coefficients of the Ar for the carbon target. The results that are presented illustrate the difficulty of this work. The second study is the application of the statistical approach to the surface ionization source. It allowed one to define and to build a new MonoNaKe set-up for the production of 1{sup +} radioactive alkaline ions. Radioactive ions of K{sup 37,47}, Na{sup 25,26,27,28,30}, Li{sup 8,9} and Al{sup 28,29,30,31} were produced. For the production of the multicharged radioactive alkali ions, the MonoNaKe target/ion-source system was coupled to the ECR source of SPIRAL-1 without a mass separator (1{sup +}/N{sup +} direct method). A first radioactive ion beam of {sup 47}K{sup 5+} was extracted at the SIRa test bench. A surface ionization test source based on the same technical characteristics of MonoNaKe has been built. The goal of this system will be to define a prototype of source adapted to the constraints of SPIRAL-2 (ionization efficiency and lifetime). (author)

  10. Long-term thyroid values after intake of radio-active iodine; Bilans thyroidiens de longue duree apres administration d'iode radioactif

    Energy Technology Data Exchange (ETDEWEB)

    Riviere, R [Institut National de la Sante et de la Recherche Medicale, 75 - Paris (France); Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1965-07-01

    In connection with a compartment theory, a kinetic study of thyroid metabolism in man requires the determination of the specific iodine activity at all accessible levels (plasma, urines, faeces), during periods of over a month; The basic methods required for such a study are therefore the use of iodine-125 as a tracer, the exact determination of iodine-127 using activation analysis and the setting-up of a daily diet of constant iodine content. The results are presented for each particular case and the main parameters of thyroid metabolism are calculated. The discussion includes some special considerations concerning the pathological condition of the subject or a break in the thyroid equilibrium. It shows in particular that constant disagreement exists between the experimental curves for the specific iodine activity and the corresponding theoretical curves for a conventional thyroid process based on 3 compartments; these discrepancies concern both the inorganic iodine and the organic iodine eliminated with the faeces. (author) [French] Dans le cadre d'une theorie a compartiments, l'etude cinetique du metabolisme thyroidien chez l'homme necessite la determination de l'activite specifique de l'iode a tous les niveaux accessibles (plasma, urines, feces), pendant des periodes depassant un mois. Les methodes de base indispensables pour une telle etude sont donc l'utilisation de l'iode 125 comme traceur, le dosage precis de l'iode 127 grace a l'analyse par activation et l'etablissement d'une diete journaliere constante en iode. Les resultats sont presentes pour chaque cas et les principaux parametres du metabolisme thyroidien calcules. La discussion fait part de considerations particulieres liees a l'etat pathologique du sujet ou a une rupture de l'equilibre thyroidien. Elle met surtout en lumiere des desaccords constants entre les courbes experimentales d'activite specifique de l'iode et les courbes theoriques correspondantes conformes au schema thyroidien classique a 3 compartiments; ces discordances concernent d'une part l'iode mineral, d'autre par l'iode organique elimine dans les feces. (auteur)

  11. Development of characterization methods applied to radioactive wastes and waste packages; Le developpement des methodes de caracterisation appliquees aux dechets et colis de dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Guy, C.; Bienvenu, Ph.; Comte, J.; Excoffier, E.; Dodi, A. [CEA Cadarache (DEN/CAD-DEC/SA3C/LARC), 13 - Saint Paul lez Durance (France); Gal, O.; Gmar, M.; Jeanneau, F.; Poumarede, B.; Tola, F. [CEA Saclay (DRT/SAC-DETECS/SSTM/L2MA), 91 - Gif sur Yvette (France); Moulin, V. [CEA Grenoble (DRT/GRE-LETI/DTBS/STD), 38 (France); Jallu, F.; Lyoussi, A.; Ma, J.L.; Oriol, L.; Passard, Ch.; Perot, B.; Pettier, J.L.; Raoux, A.C.; Thierry, R. [CEA Cadarache (DEN/CAD-DTN/SMTM/LMN), 13 - Saint Paul lez Durance (France)

    2004-07-01

    This document is a compilation of R and D studies carried out in the framework of the axis 3 of the December 1991 law about the conditioning and storage of high-level and long lived radioactive wastes and waste packages, and relative to the methods of characterization of these wastes. This R and D work has permitted to implement and qualify new methods (characterization of long-lived radioelements, high energy imaging..) and also to improve the existing methods by lowering detection limits and reducing uncertainties of measured data. This document is the result of the scientific production of several CEA laboratories that use complementary techniques: destructive methods and radiochemical analyses, photo-fission and active photonic interrogation, high energy imaging systems, neutron interrogation, gamma spectroscopy and active and passive imaging techniques. (J.S.)

  12. Is there an ethic of radioactive waste management?; Y a-t-il une ethique de la gestion des dechets radioactifs?

    Energy Technology Data Exchange (ETDEWEB)

    Chouchan, M.; Montremy, J.M. de; Loisel, J.P.; Arnould, J.; Serre, J.L.; Bucaille, A.; Barre, B.; Duvert, L.; Legrand, P.; Engstorm, S.; Pavlovski, D

    2004-07-01

    In France today, radioactive wastes are stored in a secure way, waiting for a political decision concerning their disposal. However, their evolution has to be followed and the future generations will need to be informed to eventually modify the present day choices. Thus, the reversibility is one of the ethical dimension of the question. Today, more than 90% of the radioactive wastes produced in France have found a reliable management solution for each category of wastes. This document compares the point of view of several people from nuclear and non-nuclear domains about the deontological and memory dimensions of radioactive waste management. (J.S.)

  13. Processing and Pre-Treatment of Solid Radioactive Waste; Conditionnement des Dechets Radioactifs Solides; 041e 0411 0420 0414 ; Acondicionamiento de los Desechos Radiactivos Solidos

    Energy Technology Data Exchange (ETDEWEB)

    Cerre, P. [Service de Controle des Radiations et de Genie Radioactif, Commissariat a l' Energie Atomique, Saclay (France)

    1960-07-01

    As solid radioactive waste varies in form, dimensions and volume, the Atomic Energy Commission first of all reduces the volume by breaking up and compressing the waste. Since the temporary storage of such waste is always attended by the risk of contamination, an efficient packing system has been devised and adopted. This consists of embedding the waste in the heart of a specially-designed block of concrete possessing the following characteristics: Great strength Maximum insolubility Resistance to corrosion Maximum imperviousness Protection against radiation. It is thus quite safe to store these blocks with a view to final dumping. (author) [French] Les dechets actifs solides etant de formes, de dimensions et de volumes varies, le C.E.A. procede en premier lieu a une reduction de volume par fractionnement et compactage. L'emmagasinage provisoire de tels dechets ne pouvant se concevoir sans risques de contamination, un procede efficace d'emballage a ete etudie et realise. Il consiste a noyer les dechets dans un beton specialement etudie qui presente les caracteristiques suivantes: - Forte resistance mecanique . - Insolubilite maximum - Resistance a la corrosion - Etancheite maximum - Protection contre le rayonnement Il est alors possible de conserver sans danger les blocs formes en vue d'un rejet definitif ulterieur. (author) [Spanish] Como los desechos radiactivos solidos difieren mucho por su forma, dimension y volumen, el Commissariat efectua en primer lugar una reduccion de volumen desmenuzandolos y comprimiendolos. El almacenamiento provisional de esos desechos presenta siempre riesgos de contaminacion, por lo que se ha estudiado y llevado a la practica un sistema especial de embalaje. Este sistema consiste en empotrar los desechos en un hormigon especialmente estudiado que ofrece las siguientes caracteristicas: - Fuerte resistencia mecanica - Maximum de insolubilidad - Resistencia a la corrosion - Maximum de estanquidad - Proteccion contra las radiaciones De esta manera se pueden conservar sin peligro los bloques de hormigon para mas tarde evacuarlos definitivamente. (author) [Russian] Poskol'ku, tverdye aktivnye othody imejut razlichnuju formu, razmer i obem, Centr jadernyh issledovanij umen'shaet prezhde vsego ih ob'em putem droblenija i uplotnenija jetih tel. Poskol'ku vremennoe skladirovanie takih othodov predstavljaet risk zagrjaznenija, byl izuchen i razrabotan dejstvennyj metod ih upakovki. Jetot metod sostoit v utoplenii othodov v special'no podgotovlennom betone, imejushhem sledujushhie harakteristiki: - sil'noe mehanicheskoe soprotivlenie - maksimal'nuju nerastvorimost - soprotivlenie k korrozii - maksimal'nuju vodonepronecaemost - zashhitu protiv izluchenija Takim obrazom, vozmozhno bezopasno sohranjat obrazovannye bloki s cel'ju ih pozdnejshego okonchatel'nogo zahoronenija. (author)

  14. Dosage of cesium 137 in radioactive wastes by the application of sodium tetraphenylborate; Dosage du cesium 137 dans les effluents radioactifs par le tetraphenylborate de sodium

    Energy Technology Data Exchange (ETDEWEB)

    Testemale, G; Girault, J [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1967-07-01

    A simple technique of the dosage of {sup 137}Cs has been developed. The technique consists in the formation of cesium tetraphenyl borate, followed by a double extraction with isoamyl acetate, and washing of the organic phase. The counting of known parts of the cesium solution assaying of its purity by {gamma} spectrometry enable the determination of the {sup 137}Cs. The yield is about 98 per cent. (authors) [French] Une technique simple du dosage du {sup 137}Cs a ete mise au point. Elle consiste en une double extraction du tetraphenylborate de cesium forme par l'acetate d'isoamyle suivie d'un lavage de la phase organique. Des comptages sur des parties aliquotes de la solution de cesium et un controle de purete par spectrometrie {gamma} permettent la determination de cet element. Rendement: environ 98 pour cent. (auteurs)

  15. Safety guidebook relative to the disposal of radioactive wastes in deep geologic formation; Guide de surete relatif au stockage definitif des dechets radioactifs en formation geologique profonde

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    The French nuclear safety authority (ASN) initiated in 2003 a revision process of the objectives to be considered during the research and work steps of the implementation of a radioactive waste storage facility in deep geologic formations. The purpose of this document is to define the safety objectives that have to be retained at each step of this implementation, from the site characterization to the closure of the facility. This update takes into account the works carried out by the ANDRA (French national agency of radioactive wastes) in the framework of the law from December 30, 1991, and the advices of the permanent experts group about these works. It takes also into consideration the international research works in this domain and the choices defined in the program law no 2006-739 from June 28, 2006 relative to the sustainable management of radioactive materials and wastes. The main modifications concern: the notion of reversibility, the definition of the safety functions of disposal components, the safety goals and the design principles assigned to waste packages, the control of nuclear materials and the monitoring objectives of the facility. The documents treats of the following points: 1 - the objectives of public health and environment protection; 2 - the safety principles and the safety-related design bases of the facility; and 3 - the method used for demonstrating the disposal safety. (J.S.)

  16. Alternatives - talk about energy differently. Radioactive waste a societal issue; Alternatives - parler autrement de l'energie. Dechets radioactifs un enjeu de societe

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    ''Alternatives'' is an information magazine proposed by the Areva Group, a world nuclear energy leader. It is devoted to the public information on topics of the Group activities. This issue deals with the fusion technology, the strengths and weaknesses of interconnected networks, the undersea tidal power farms, the danish paradox which has the highest levels of CO{sub 2} emissions despite the use of wind energy, the international community renewed commitment to renewable energy, the hydrogen, the low speed wind turbines and the future miniature fuel cells. A special interest is given to the radioactive wastes management. (A.L.B.)

  17. Radioactive iodine and environmental and sanitary effects - bibliographic study and quantification; Iodes radioactifs et impacts environnemental et sanitaire - etude bibliographique et quantification

    Energy Technology Data Exchange (ETDEWEB)

    Guetat, Ph.; Armand, P.; Monfort, M.; Fritsch, P. [CEA Bruyeres-le-Chatel, 91 (France); Flury Herard, A. [CEA, Dir. des Sciences du Vivant, 75 - Paris (France); Menetrier, F. [CEA Fontenay-aux-Roses, Dir. des Sciences du Vivant, 92 (France); Bion, L. [CEA Saclay, Dir. de l' Energie Nucleaire (DEN), 91 - Gif sur Yvette (France); Schoech, C.; Masset, S. [Societe EX-IN - Expertise et Ingenierie, 92 - Le Plessis-Robinson (France)

    2004-07-01

    This document is intended to a large public. It reviews the different parameters needed to evaluate the potential act o radioactive releases from the emission to public. Its objectives are to evaluate the importance of different exposure pathways and to assess efficiency of the possible interventions for large public. The main conclusions are summarised hereafter: The radioactive decay chains have to be taken into account to evaluate the iodine source term in the nuclear plants in the case of fission accidents. The physico-chemical forms of iodine are important in order to determine the released activity and deposited activity on the soil. The isotopes to be taken into account are mainly iodine 131 for radiological assessments and also iodine 133 for the nuclear reactor accidents, and the chain Tellurium-Iodine 132 when no particulate filtration exists. Iodine 129 in French reprocessing plant cannot lead to significant accidents. The dominant exposure pathways are related to the consumption of contaminated food products (vegetable, milk) for the inorganic iodine. The iodine transfer to goat and sheep milk is greater than the one to cow milk. The meat production of herbivores at field is the most sensitive. The interest to remove rapidly herbivore from pasture appears relatively clearly. The banning of consumption of local contaminated food products (vegetables and meats) may reduce by about a factor of thirteen the impact due to iodine 131. The youngest the population is, the greatest are the thyroid radiosensitivity and variability within the population. Oral administration of stable iodine limits transfers to maternal milk and foetal thyroid. Ingestion of stable iodine is complementary to consumption banning of local contaminated food products. The earliest the ingestion is, the greatest is the efficiency. 0,1 TBq of 131 iodine released at a low height involves only limited and local actions whereas the release of 10 TBq involves direct and immediate protection of the population and affects an important agricultural zone. (author)

  18. Radioactive secrets of Icelandic volcanoes: Eyjafjoll (March 2010) and Grimsvoetn (May 2011); Les secrets radioactifs des volcans islandais: Eyjafjoll (mars 2010) et Grimsvoetn (mai 2011)

    Energy Technology Data Exchange (ETDEWEB)

    Guiraud-Vitaux, F.; Pradel, J.; Colas-Linhart, N.

    2011-07-15

    This article recalls that volcanoes release huge quantities of radioactive nuclides during their eruption. In March 2010 the Eyjafjoll volcano (Iceland) ejected several hundred million tonnes of dust in the first 72 hours among which 400 tonnes of uranium-238 (20.000 billions Bq) and 1200 tonnes of natural thorium. Polonium-210 was also released in the atmosphere. Most part of the radioactivity fell on Icelandic soil and no sanitary measures were taken by the authorities because the resulting doses were too low to have hazardous effects. (A.C.)

  19. National evaluation commission relative to the researches on the radioactive wastes management; Commission nationale d'evaluation relative aux recherches sur la gestion des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    Implemented in april 1994, the National Evaluation Commission (CNE) continues in this tenth report, its study on the radioactive wastes management following the three axis defined by the 1991 law: separation and transmutation, underground disposal, conditioning and log time storage. This report takes stock on the CNE activity in 2003 as on the researches advances around these three axis. In the framework of the international cooperation, the commission details also the researches and realizations abroad. (A.L.B.)

  20. The fantastic history of radium: when a radioactive element becomes a magic potion; La fantastique histoire du radium: Quand un element radioactif devient potion magique

    Energy Technology Data Exchange (ETDEWEB)

    Cosset, Jean-Marc; Huynh, Renaud

    2011-04-18

    More than a century after its discovery, radium has never lost its symbolic power: the symbol of scientific perseverance with Marie Curie handling quintals of ore to extract this 'fabulous metal', symbol of radiations efficiency against cancer, symbol of eternity and value - like diamond, and many more. The power of such a symbol led some mercantile minds to make radium a panacea capable to cure any illness. Then between the first and the second World war, radium became a society phenomenon: popular book writers held of the magic name to imagine wild stories and the advertisers started to link it to any type of product (beverages, shoe polish, razor blades, cigarettes, cheese, condoms..). This book relates the story of this symbol over more than a century, with its successes, its excesses and sometimes its dramas. (J.S.)

  1. National plan of radioactive wastes and matters 2007-2009; Plan national de gestion des matieres et des dechets radioactifs 2007-2009

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-01-15

    This Plan aims to propose a global framework allowing the management of radioactive wastes, whatever the producers in order to control the safety and the choice of adapted disposal sites. The first part is devoted to the description of solutions of radioactive wastes management for existing or engaged wastes. The second part concerns radioactive materials of the nuclear industry which are not considered as wastes, but as recycling materials for future nuclear reactors. For instance, this part discusses the particular case of the depleted uranium. The third part examines the different channels of the long dated management. The last part brings together the all data and in particular problematic points which must be discussed and analyzed in a logic framework. Propositions and recommendations are provided. (A.L.B.)

  2. Ion exchange in ultramarine blue. Studies using radioactive tracers (1963); Echanges d'ion dans le bleu d'outremer, etudies au moyen des traceurs radioactifs (1963)

    Energy Technology Data Exchange (ETDEWEB)

    Goenvec, H [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1963-05-15

    A study has been made of the exchange reaction between the constituent sodium in ultramarine blue, and silver in the form of a silver nitrate solution; an attempt hat been made to define the influence of the solvent of the silver nitrate on the kinetics of the exchange reaction. Five solvents have been used: water, methanol, ethanol, n-propanol and acetone. The reaction rates are controlled by a diffusion process inside the ultramarine grains, whatever the solvent used. It seems that the solvated ionic radius of the diffusing ion is one of the factors influencing the rate of reaction. Furthermore, the solvated ionic radius varies with temperature; this variation is different for each solvent and should explain the differences observed in the activation energies. (author) [French] Nous avons etudie la reaction d'echange entre le sodium de constitution du bleu d'outremer et l'argent sous forme de nitrate d'argent en solution; nous avons essaye de definir l'influence du solvant du nitrate d'argent sur la cinetique de la reaction d'echange. Nous avons utilise cinq solvant: l'eau, le methanol, l'ethanol, le n-propanol et l'acetone. Les vitesses de reaction sont controlees par un processus de diffusion a l'interieur des grains d'outremer quel que soit le solvant. Il semble que le rayon ionique solvate de l'ion diffusant est l'un des facteurs qui influencent la vitesse de reaction. D'autre part, le rayon ionique solvate varie avec la temperature, cette variation est differente pour chaque solvant et doit pouvoir expliquer les differences d'energie d'activation constatees. (auteur)

  3. Radioactive wastes and valorizable materials in France: summary of the 2004 national inventory; Dechets radioactifs et matieres valorisables en France: resume de l'inventaire national 2004

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    The French national inventory of radioactive wastes is a reference document for professionals and scientists of the nuclear domain and also for any citizen interested in the management of radioactive wastes. This summary document contains: 1 - general introduction; 2 - classification of radioactive wastes: the 5 main categories; 3 - origin of the wastes; 4 - processing and conditioning; 5 - inventory of existing wastes: geographical inventory, inventory per category; 6 - prospective inventory: prospective scenarios, forecasting of waste production; 7 - valorizable radioactive materials; 8 - synthesis and perspective; 9 - glossary. (J.S.)

  4. National inventory of radioactive wastes and valorizable materials. Synthesis report; Inventaire national des dechets radioactifs et des matieres valorisables. Rapport de synthese

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    This national inventory of radioactive wastes is a reference document for professionals and scientists of the nuclear domain and also for any citizen interested in the management of radioactive wastes. It contains: 1 - general introduction; 2 - the radioactive wastes: definition, classification, origin and management; 3 - methodology of the inventory: organization, accounting, prospective, production forecasting, recording of valorizable materials, exhaustiveness, verification tools; 4 - general results: radioactive waste stocks recorded until December 31, 2002, forecasts for the 2003-2020 era, post-2020 prospects: dismantling operations, recording of valorizable materials; 5 - inventory per producer or owner: front-end fuel cycle facilities, power generation nuclear centers, back-end fuel cycle facilities, waste processing or maintenance facilities, civil CEA research centers, non-CEA research centers, medical activities (diagnostics, therapeutics, analyses), various industrial activities (sources fabrication, control, particular devices), military research and experiment centers, storage and disposal facilities; 6 - elements about radioactive polluted sites; 7 - examples of foreign inventories; 8 - conclusion and appendixes. (J.S.)

  5. The processing and management of wastes from atomic reactors; Nouvelles installations industrielles du C.E.A. pour le traitement des dechets radioactifs liquides et solides

    Energy Technology Data Exchange (ETDEWEB)

    Cerre, P; Mestre, E; Bourdrez, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1964-07-01

    The policy concerning radioactive wastes studied by all Atomic Centres has led to various procedures which, while apparently numerous, come under a few standard headings. Whether the wastes are in the liquid or solid state their management depends on their physical and chemical nature. The procedure adopted is governed by three general principles: - determination of the most economical means possible of storage and processing by volume reduction; - conversion to a solid compact form; - complete acceptance of the accepted standards at all places and all times. In this communication all the standard solutions adopted and used by the various Centres of the Commissariat a l'Energie Atomique will be examined bearing in mind the preceding remarks. Particular mention will be made of the following: - For liquids, physical, chemical and physico-chemical processing - For solids, decontamination, volume reduction and long-term conditioning techniques. The different procedures for collecting and storing solid wastes before and after processing are also discussed. The paper ends with a brief review of the studies, both technical and economic, being pursued on this subject. (authors) [French] La gestion des dechets etudies par tous les Centres Atomiques a donne lieu a des solutions qui - bien que nombreuses en apparence - se ramenent a quelques solutions types, peu nombreuses. Qu'il s'agisse de dechets solides ou liquides, la nature physique et chimique des dechets conditionne leur mode de gestion. Celle-ci procede de trois principes generaux: - recherche du mode de stockage et de traitement aussi economique que possible par reduction de volume; - mise sous forme compacte solide; - garantie du respect des normes en tous lieux et en tous temps. Dans cette communication, nous examinons toutes les solutions types, compte tenu des remarques precedentes, qui ont ete adoptees et sont utilisees par les differents Centres du Commissariat a l'Energie Atomique. Nous rappelons en particulier: - Pour les liquides, les traitements par voie physique, chimique et physicochimique. - Pour les solides, les techniques de decontamination, de reduction de volume et de conditionnement de longue duree. Nous developpons egalement dans ce rapport les differents modes de collecte et de stockage avant et apres traitement des dechets solides. La communication se termine par un rapide expose des etudes en cours, tant techniques qu'economiques sur ce sujet. (auteurs)

  6. Study of the mineral absorbent precipitation phenomena used in decontamination of radioactive effluents; Etude des phenomenes de precipitation d'adsorbants mineraux utilises en decontamination d'effluents radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Pacary, V. [Institut National Polytechnique, 54 - Nancy (France)]|[CEA Valrho, Lab. des Procedes Avances de Decontamination (LPAD), 30 - Marcoule (France)

    2006-07-01

    The aim of this work is to determine the optimal conditions of the reactor running (feed rate, reagents concentration..) for which the effluent decontamination is the most efficient. Thus will be in particular studied the coprecipitation mechanisms and the influence of the physico-chemical conditions on these mechanisms. On the other hand, the processes occurred in the coprecipitation phenomenon being complex, the elaboration of a model is indispensable to guide and interpret the experimental work. This model will be based on the knowledge developed in precipitation and will allow to simulate the decontamination in two reactors types: the reactor fed in continuous in reagents and in effluents as the Hague's ones and the closed reactor fed only in reagents as the Marcoule's ones. (O.M.)

  7. On the role of clay minerals in the disposal of radioactive waste in a clay geological formation; Les mineraux argileux. Leur role et importance dans un site de stockage de dechets radioactifs en couche argileuse profonde

    Energy Technology Data Exchange (ETDEWEB)

    Clauer, N. [Centre National de la Recherche Scientifique (CNRS), Centre de Geochimie de la Surface, 67 - Strasbourg (France)

    2005-05-01

    Clay minerals represent appropriate candidates in the search of geological sites and man-made barriers for potential underground storage of nuclear waste, because of their cation-exchange capabilities and swelling properties. However, this statement needs also to take into consideration other aspects such as physical parameters specific (imbrication of the mineral aggregates, occurrence of oxy-hydroxides and/or organic matter), or not of the rocks (temperature, compaction, etc), and the evolutionary history of the target units as they might indirectly modify the above potentials. Alternatively, original micro-discontinuities (micro-fractures) or those induced by the construction of the site do not appear to represent potential drains for fluid escapes, at least over long distances. The few examples presented here emphasize also that one should be careful about generalizing any conclusion, and that analytical data acquisition should be privileged in order to control better the reliability of the results and the potentials of the applied method. (author)

  8. Determination of the free enthalpies of formation of borosilicate glasses; Determination des enthalpies libres de formation des verres borosilicates. Application a l'etude de l'alteration des verres de confinement de dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Linard, Y

    2000-07-01

    This work contributes to the study of the thermochemical properties of nuclear waste glasses. Results are used to discuss mechanisms and parameters integrated in alteration models of conditioning materials. Glass is a disordered material defined thermodynamically as a non-equilibrium state. Taking into account one order parameter to characterise its configurational state, the metastable equilibrium for the glass was considered and the main thermochemical properties were determined. Calorimetric techniques were used to measure heat capacities and formation enthalpies of borosilicate glasses (from 3 to 8 constitutive oxides). Formation Entropies were measured too, using the entropy theory of relaxation processes proposed by Adam and Gibbs (1965). The configurational entropy contribution were determined from viscosity measurements. This set of data has allowed the calculation of Gibb's free energies of dissolution of glasses in pure water. By comparison with leaching experiments, it has been demonstrated that the decreasing of the dissolution rate at high reaction progress cannot be associated to the approach of an equilibrium between the sound glass and the aqueous solution. The composition changes of the reaction area at the glass surface need to be considered too. To achieve a complete description of the thermodynamic stability, the equilibrium between hydrated de-alkalinized glass and/or the gel layer with the aqueous solution should also be evaluated. (author)

  9. Use of electron beams for the production of radioactive nuclei through photo-fission; Utilisation de faisceaux d'electrons pour la production des noyaux radioactifs par photo-fission

    Energy Technology Data Exchange (ETDEWEB)

    M' garrech, Slah

    2004-09-01

    The IPN (institute of nuclear physics) of Orsay decided to build a linear accelerator in order to produce an electron beam of 50 MeV energy and of 10 {mu}A average intensity. It is the ALTO project (Linear Accelerator near the Tandem of Orsay). This project will be dedicated to the production of the radioactive ions using the photo-fission process. The central topic of this thesis is the study of the beam dynamics of the ALTO facility. The first part presents studies concerning the injector. The simulations made with the simulation code PARMELA allowed the optimization of the characteristics of pre-buncher (dephasing HF, accelerating field peak...) to obtain a good bunching factor at the entrance of the buncher and at the entrance of the accelerating section according to the distance separating the two systems. The second part of this thesis is related to measurements of transverse emittance of the beam at the buncher exit. The three gradients method has been selected and the optical system used is a solenoid. The results obtained are in good agreement with former measurements. Finally a calculation of the beam line was carried out to optimize the transport of the beam to the PARRNe target without degrading its characteristics. The calculation codes that have been used are BETA and TRACE-WIN. (author)

  10. The thorium phosphate diphosphate as matrix for radioactive waste conditioning: radionuclide immobilization and behavior under irradiation; Le phosphate diphosphate de thorium, matrice pour le conditionnement des dechets radioactifs: immobilisation de radionucleides, comportement sous irradiation

    Energy Technology Data Exchange (ETDEWEB)

    Pichot, Erwan [Inst. de Physique Nucleaire, Paris-11 Univ., 91 - Orsay (France)

    1999-04-13

    The aim of this work was to perform successively the decontamination of liquid solutions and the final immobilization of radionuclide storage using the same matrix. For this, thorium phosphate-diphosphate (TPD) of the formula Th{sub 4}P{sub 6}O{sub 23}, is proposed as a very resistant to water corrosion matrix. A new compound, thorium phosphate hydrogeno-phosphate (TPHP) of the formula Th{sub 2}(PO{sub 4}){sub 2}(HPO{sub 4}), nH{sub 2}O with n=3-7 was synthesized and characterized. Heated at 1100 deg.C it is transformed into the TDP. Ion exchange properties of TPHP were investigated. The exchange yields of imponderable caesium, strontium and americium ion onto TPHP (NaNO{sub 3} 0.1 M media at pH=6) are equal to 60% for the first one and 100% for the two others. The results interpreted in terms of ion-exchange led to determine selectivity coefficient values for each cation and suggested that only hydrated ions are exchanged. While the TPD is proposed for the high level nuclear waste storage, the irradiation effects, particularly structural modifications were studied using both {gamma} irradiation and charged particle irradiation. ESR and TL methods were carried out in order to identify radicals created during gamma radiation exposure. Correlation between ESR and TL experiments performed at room temperature clearly show three of PO{sub 3}{sup 2-} species and one POO{center_dot} species of free radicals. We have shown that Au-ion irradiation in the range of MeV energy involved TPD structure and chemical modifications. Important sputtering was interpreted in terms of local thermal chemical decomposition. We have shown, at room temperature, that the amorphization dose for heavy ion irradiation is between 0.1 to 0.4 dpa. (author) 146 refs., 46 figs., 21 tabs.

  11. Fixation of radioactive cerium-144 on white blood cells. Possibilities for use in physiopathology; Fixation du cerium radioactif ({sup 144}Ce) sur les globules blancs. Possibilites d'emploi en physiopathologie

    Energy Technology Data Exchange (ETDEWEB)

    Aeberhardt, A [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    From the study of the means of transport of cerium in the blood of various laboratory animals, after intra-venous injection of {sup 144}Ce-{sup 144}Pr without carrier, we have been able to show up the part played by the white cells in the transport of this fission product during its passage in the blood. This observation has led to the study, in vitro, of the methods of cerium fixation on the white cells, with a view to determining the possibilities of using this property for white cell labelling, the methods used up to the present not being entirely satisfactory. Using the method for the separation of the known constituents of the blood proposed by us in 1956, we have studied the cerium fixation under various conditions: - on suspensions of white cells from the rabbit, - on a suspension of human white cells, - on the white cells in whole from the rabbit. (author) [French] L'etude du mode de transport du cerium dans le sang chez differents animaux de laboratoire, apres injection intra-veineuse de {sup 144}Ce-{sup 144}Pr sans entraineur, nous a permis de mettre en evidence le rale des globules blancs dans le transport de ce produit de fission au cours de son passage dans le sang. Cette constatation nous a conduit a etudier, in vitro, les modalites de la fixation du cerium sur les globules blancs afin de preciser les possibilites d'utilisation de cette propriete pour le marquage des globules blancs, les methodes employees jusqu'ici ne donnant pas entiere satisfaction. Disposant de la methode de separation des elements figures du sang que nous avons proposee en 1956, nous avons etudie la fixation du cerium, dans diverses conditions: - sur des suspensions de globules blancs de lapin, - sur une suspension de globules blancs humains, - sur les globules blancs dans le sang total de lapin. (auteur)

  12. The potentialities of the complexation ultrafiltration technique for the decontamination of fission product contaminated aqueous effluents; Potentialites de la complexation - ultrafiltration a la decontamination d`effluents radioactifs en produits de fission

    Energy Technology Data Exchange (ETDEWEB)

    Thibert, V

    1995-07-01

    Many nuclear researchers and industrial operators lay emphasis on improving the back end of the fuel cycle. A major problem concerns the liquid wastes generated by the reprocessing plant at La Hague, discharged into the sea after treatment in the Effluent Treatment Station (STE) (3), and which have become crucial matter. The activity of these wastes is well below the current legal limits, and is constantly decreasing these last years. To bring it close to zero, and ambitious goal, entails innovative new reprocessing techniques. We accordingly investigated the possibilities of complexation-ultrafiltration, a technique that uses water-soluble macromolecules to complex the target elements to be separated. We first achieved the strontium (II) separation with poly-acrylic and poly-sulfonic acids. The effects of pH and NaNO{sub 3} concentration influence on Sr (II) complexation were studied. The Sr (II) complexation and concentration phases, followed by cation de-complexation to recover the polymer, were also taken into account. This research, combined with a potentiometric study of the polymers, offered a close understanding of the chemical systems involved, and of the operating conditions and limits of complexation-ultrafiltration. The laboratory results were also validated on a tangential ultrafiltration pilot plant. We then used complexation-ultrafiltration to treat a real effluent generated bu La Hague`s STE 3 plant. This experiment demonstrated minimum 90 % decontamination of Sr (II) (with polyacrylate complexing agent), and also for {sup 134-137}Cs (with simple ultrafiltration). The use of two polyamides allowed partial decontamination of the effluent for {sup 60}Co and {sup 106}Ru. This work therefore offers a global approach to complexation-ultrafiltration, from laboratory to pilot scale, on real and simulated effluents. The future of this technique relies chiefly on the ability to solve the problem of polymer recovery. (Abstract Truncated)

  13. The distribution of radionuclides and some trace metals in the water columns of the Japan and Bonin trenches; Repartition des nucleides radioactifs et de quelques metaux-traces dans les fosses du Japon et des iles Bonin

    Energy Technology Data Exchange (ETDEWEB)

    Nozari, Y.; Yamada, M. [Tokyo Univ. (Japan). Ocean Research Inst; Nakanishi, T. [Kanazawa Univ. (Japan). Dept. of Chemistry; Nagaya, Y.; Nakamura, K.; Yamada, M. [National Inst. of Radiological Sciences, Hitachinaka, Ibaraki (Japan); Shitashima, K.; Tsubota, H. [Hiroshima Univ. (Japan). Faculty of Integrated Arts and Sciences

    1998-05-01

    Presented here is the first geochemical data on the U/Th series Th, Pa, Ac, and Pb isotopes and artificial fallout radionuclides ({sup 90}Sr, {sup 137}Cs, and Pu isotopes), and some trace elements (V, Zn, Cd, Cu, Mn, and Ni) in two water columns of the Japan and Bonin trenches down to the bottom depths of 7585 m and 9750 m, respectively. Hydrographic properties such as temperature, salinity dissolved oxygen, and nutrient content within the trench valley remain constant at the same levels as those in the bottom water of the Northwest Pacific basin (typically {approx}6000 m in depth). The radionuclide activities and most trace metal concentrations are also not very different from those in the overlying water at depths of around 5000-6000 m. This means that any chemical alteration which sea water undergoes during its residence within the trench was not obviously detected by the techniques used here. The suggestion follows that the trench water is rather freely communicating y isopycnal mixing with the bottom water overlying the Northwest Pacific abyssal plain. The trench waters contain high {sup 239,240}Pu activities throughout, indicating that Pu is actively regenerating from rapidly sinking, large particles at the bottom interface, probably due to a change in the oxidation state. On the other hand, the vertical profiles of {sup 210}Pb and {sup 231}Pa show lower activities within the trench than those in the overlying deep waters, suggesting that the effect of boundary and bottom scavenging is significant in controlling their oceanic distributions. However, none of the trace metals studied here obviously follows the behaviour of the above nuclides. The {sup 228}Th data show scattering within the Bonin Trench that is largely ascribable to analytical errors. If, however we accept that the scatter of {sup 228}Th data is real and the variation is caused solely by decay of its parent {sup 228}Ra, we can set an upper limit of {approx}5 years for the renewal time of the trench water. (authors) 47 refs.

  14. Analyses and quantitative determination of the strontium radioisotopes 89 and 90 in milk powder; Recherche et dosage des isotopes radioactifs 89 et 90 du strontium dans le lait en poudre

    Energy Technology Data Exchange (ETDEWEB)

    Jeanmaire, L; Michon, G [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1959-07-01

    The authors describe a procedure for the determination of the strontium radioisotopes 89 and 90. The concentration of strontium is made possible by the insolubility of its nitrate salt in strong nitric acid which allows the removal of greatest part of calcium. The purification is performed on a cation exchange column. The amount of radioisotope 90 is determined by means of its daughter product yttrium 90 necessary calibrations and computations are treated in special paragraphs. With regard to the reproducibility of the measurements, the fluctuations are less than 20 per cent. This seems satisfaction for such a technique which have great sensibility while being long and necessitative great carefulness. (author) [French] Les auteurs decrivent une technique de dosage des isotopes 89 et 90 du strontium. La concentration du strontium est assuree grace a l'insolubilite de son nitrate dans l'acide nitrique concentre, ce qui permet d'eliminer la plus grande partie du Ca. La purification se fait sur une colonne echangeuse de cations. L'isotope 90 est dose grace a son descendant l'yttrium 90. Les etalonnages et calculs necessaires font l'objet de paragraphes detailles. En ce qui concerne la reproductibilite des mesures, les fluctuations sont inferieures a 20 pour cent, ce qui semble satisfaisant devant la grande sensibilite de la methode qui reste cependant longue et delicate. (auteur)

  15. Where, when, how: the place of radioactive wastes in France. Andra, 1998 activity report; Ou, quand, comment: la place des dechets radioactifs en France. Andra, rapport d'activite 1998

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-07-01

    The 1998 activity report of the French national agency of radioactive wastes (Andra) presents successively: the role and missions of the Andra (history, status of radioactive wastes in France, surface storage and know-how, underground research laboratories, site selection and public information); the aspects of safety (inventory, identification and labelling of wastes, environmental policy, public relation, safety rules and reports, information storage); the scientific programs (collaborations, financing, site studies, rock mechanics and reversibility of storage, design of storage facilities, services); financial report. (J.S.)

  16. N.590 National assembly. Law project of program relative to the sustainable management of radioactive materials and wastes; N. 590 Assemblee Nationale. Projet de loi de programme relatif a la gestion durable des matieres et des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    This document presents the different articles of the law text n. 590 on the management of the radioactive wastes and materials. It concerns the obligations and the liabilities of producers and users of radioactive spent fuels and wastes. (A.L.B.)

  17. Disposal of Low-Activity Waste and Accumulation in Cultivated Soils; Rejets d'Effluents Faiblement Radioactifs et Accumulation dans les Sols Cultives; 0416 0418 0414 ; Desechos y Efluentes de Baja Actividad: Su Acumulacion en los Terrenos Cultivados

    Energy Technology Data Exchange (ETDEWEB)

    Barbier, G. [Station Centrale d' Agronomie, Versailles (France); Michon, G. [Service d' Hygiene Atomique et de Radiopathologie, Centre d' Etudes Nucleaires, Saclay (France)

    1960-07-01

    The paper describes a method of accumulating long-lived radioisotopes in soils and calculating the maximum contamination they would cause in vegetables grown on these soils. The authors suggest a way of expressing this contamination and a formula by which the maximum contamination of one kilogramme of the harvested produce in relation to the tolerated contamination per litre of irrigation water could be calculated. (author) [French] L'article decrit une methode destinee a prevoir l'accumulation des radioelements de longue periode dans les sols et a chiffrer la contamination limite qui en resultera pour des legumes cultives sur ces sols. Les auteurs proposent un mode d'expression de cette contamination et une formule qui permettrait de calculer la contamination limite d'un kg de produit recolte par rapport a la contamination toleree d'un litre d'eau d'irrigation. (author) [Spanish] En la memoria se describe un metodo para evaluar la acumulacion de los radioelementos de periodo largo en los terrenos y para calcular la contaminacion limite resultante para las hortalizas cultivadas en dichos terrenos. Los autores proponen un metodo para expresar dicha contaminacion y una formula que permita determinar la contaminacion limite de un kilogramo de producto cosechado en funcion de la contaminacion admisible por litre de agua de riego. (author) [Russian] V stat'e opisyvaetsja metod, pozvoljajushhij predvidet' nakoplenie dolgozhivushhih radioaktivnyh izotopov v pochve i opredeljat' predel'nyj uroven' vytekajushhego iz jetogo zarazhenija dlja ovoshhej, vyrashhivaemyh na jetih zemljah. Avtory stat'i predlagajut metod vyrazhenija jetogo zarazhenija i formulu, pozvoljajushhuju vychislit' predel'nyj uroven' zarazhenija odnogo kilogramma ovoshhej po otnosheniju k dopustimomu urovnju zarazhenija odnogo litra oroshajushhej vody. (author)

  18. Shape coexistence in krypton and selenium light isotopes studied through Coulomb excitation of radioactive ions beams; Etude de la coexistence de formes dans les isotopes legers du krypton et du selenium par excitation Coulombienne de faisceaux radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Clement, E

    2006-06-15

    The light krypton isotopes show two minima in their potential energy corresponding to elongated (prolate) and compressed (oblate) quadrupole deformation. Both configuration are almost equally bound and occur within an energy range of less than 1 MeV. Such phenomenon is called shape coexistence. An inversion of the ground state deformation from prolate in Kr{sup 78} to oblate in Kr{sup 72} with strong mixing of the configurations in Kr{sup 74} and Kr{sup 76} was proposed based on the systematic of isotopic chain. Coulomb excitation experiments are sensitive to the quadrupole moment. Coulomb excitation experiments of radioactive Kr{sup 74} and Kr{sup 76} beam were performed at GANIL using the SPIRAL facility and the EXOGAM spectrometer. The analysis of these experiments resulted in a complete description of the transition strength and quadrupole moments of the low-lying states. They establish the prolate character of the ground state and an oblate excited state. A complementary lifetime measurement using a 'plunger' device was also performed. Transition strength in neighboring nuclei were measured using the technique of intermediate energy Coulomb excitation at GANIL. The results on the Se{sup 68} nucleus show a sharp change in structure with respects to heavier neighboring nuclei. (author)

  19. Problems raised by radioactive ion acceleration in the SPIRAL project. Accelerator tuning and stabilisation; Problemes poses par l`acceleration d`ions radioactifs dans le project SPIRAL. Reglage et stabilisation de l`accelerateur

    Energy Technology Data Exchange (ETDEWEB)

    Boy, L. [Paris-6 Univ., 75 (France)

    1997-12-31

    This study is related to the SPIRAL project. This facility uses a cyclotron to accelerate radioactive ion beams produced in a thick target by the Grant Accelerateur National d`Ions Lourds primary beam. The low intensity of radioactive beams and the mixing of several species imply special tuning methods and associated diagnostics. Also, a cyclotron and the beam line will be used to switch from this tuning beam to the radioactive one. We present a theoretical study and a numerical simulation of the tuning of five radioactive beams using three different methods. the beam dynamic is performed through the injection beam line and the cyclotron up to the electrostatic deflector. Within the frame of these methods we have described all the SPIRAL beam diagnostics. Construction and test of a new low intensity diagnosis based on a plastic scintillator for phase measurement inside the cyclotron is described in details. (author). 63 refs.

  20. Monitoring of Fresh Waters Used for Dispersal of Radioactive Wastes; Controle des Eaux Fluviales Utilisees pour la Dispersion des Dechets Radioactifs; 0418 0417 041c 0414 ; Monitoraje de las Aguas Dulces Utilizadas para la Dispersion de Desechos Radiactivos

    Energy Technology Data Exchange (ETDEWEB)

    Ophel, I. L. [Environmental Research and Radiation Dosimetry Branch, Division of Biology and Health Physics, Atomic Energy of Canada Limited, Chalk River, ON (Canada)

    1960-07-01

    The Ottawa River is a very large river. The water has a low solids content with little plankton. In many ways the river resembles a lake. Effluent is diluted, into a great volume of low-activity cooling water and enters the river at a concentration of radionuclides less than the MPCW for occupational workers. The concentration of total B {gamma} radionuclides above the plant is 2 x 10{sup -8} {mu}c/ml, and 1.6 km below the plant it is 3 x 10{sup -8} {mu}c/ml. Sampling of the river bottom shows that its radioactivity has been decreasing for several years in spite of continuous addition of activity adsorbed on colloidal silica deposited from the water. Large fish are the only river organisms used by man. Traces of Sr{sup 90} have occasionally been found in the bones, but none in the flesh. Although P{sup 32} forms only 0.04% of the total radioactivity found in the effluent, it makes up 75-95% of the total radionuclides found in most samples. A maximum concentration of 10{sup -3} {mu}c/g wet weight has been found in the whole bodies of small perch. (author) [French] Ottawa est un tres grand fleuve. Ses eaux ne contiennent que peu' de substances solides, notamment peu de plancton. A bien des egards, ce fleuve ressemble a un lac. Les effluents sont dilues dans. une grande quantite d'eau de refroidissement, de faible activite; lorsqu'ils penetrent dans le fleuve, leur concentration en radionuclides est inferieure a la concentration maximum admissible dans l'eau pour les travailleurs exposes professionnellement. La concentration totale en emetteurs beta et gamma est 2 x 10{sup -8} {mu}c/ml en amont de l'usine et 3 x 10{sup -8} {mu}c/ml a 1,6 km en aval. Les echantillons preleves au fond du fleuve montrent que sa radioactivite diminue depuis plusieurs annees, en depit des apports continuels de l'activite adsorbee par les silices colloiedaux en suspension qui se deposent. Les seuls organismes presents dans le fleuve et utilises par l'homme sont les gros poissons. On a parfois trouve des traces de strontium-90 dans leurs aretes, mais il n'en a pas ete decele dans la chair. Pour les petites perches, on a constate une concentration maximum de 10{sup -3} {mu}c de {sup 32}P par gramme de poids brut, pour l'organisme entier. Bien que le phosphore-32 ne constitue que 0,04 pour cent de la radioactivite totale relevee dans les effluents, il represente de 75 a 95 pour cent de la quantite totale de radionuclides trouves dans la plupart des echantillons. (author) [Spanish] El Ottawa es un rio muy ancho. Sus aguas contienen, pocas materias solidas y escaso plancton. En muchos aspectos puede compararse a un lago. El efluente se diluye en una gran cantidad de agua refrigerante, de baja actividad, y su concentracion de radionuclidos al penetrar en el rio es inferior a la concentracion maxima admisible en el agua para trabajadores expuestos por razones profesionales. La concentracion total de radionuclidos beta gamma es, aguas arriba de la instalacion, de 2 x 10{sup -8} {mu}c/ml y de 3 x 10{sup -8} {mu}c/ml a 1,600 metros aguas abajo de la instalacion. Las muestras tomadas en el lecho del rio indican que su radiactividad esta decreciendo desde hace algunos anos, no obstante la continua adicion de sustancias radiactivas adsorbidas a la silice coloidal que depositan las aguas. Los unicos organismos del rio que utiliza el hombre son peces de regular tamano. En algunas ocasiones se han encontrado vestigios de estroncio-90 en sus espinas, pero nunca en la carne. En la perca pequena se ha hallado una concentracion maxima, en todo el organismo, de 10{sup -3} {mu}c de {sup 32}P/g en peso humedo. Aunque el fosforo-32 produce solamente el 0,04 por ciento de la radiactividad total hallada en el efluente, representa del 75 al 95 por ciento del total de radionuclidos encontrados en la mayoria de las muestras. (author) [Russian] Reka Ottava javljaetsja ochen' bol'shoj. V ee vode soderzhitsja malo tverdyh veshhestv i imeetsja nebol'shoj plankton. Vo mnogih otnoshenijah jeta reka predstavljaet ozero. Jeffljujent razbavljaetsja bol'shimi ob{sup e}mami nizkoaktivnoj vody, ispol'zovannoj dlja ohlazhdenija, i postupaet v reku pri koncentracii radionuklidov, ne prevyshajushhih predel'no dopustimoj koncentracii dlja rabochih. Obshhaja koncentracija beta- i gamma-radionuklidov vverh po techeniju ot zavoda sostavljaet 2 x 10{sup -8} millikjuri/millilitr i 1,6 kilometra vniz po techeniju ot zavoda ravna 3 x 10{sup -8} millikjuri/millilitr. Vzjatie prob so dna reki pokazyvaet, chto radioaktivnost' ponizhaetsja v techenie celogo rjada let nesmotrja na postojannoe dobavlenie aktivnosti, osazhdajushhejsja na kolloidal'nom kremnii, vydeljajushhemsja iz vody. Iz rechnyh organizmov chelovekom upotrebljaetsja v pishhu tol'ko krupnaja ryba. Sledy stroncija-90 byli sluchajno obnaruzheny v kostjah, no ne v mjase. Maksimal'noe soderzhanie 10{sup -3} millikjuri R{sup 32}/g obshhego vesa bylo obnaruzheno v nebol'shih okunjah. Hotja fosfor-32 sostavljaet tol'ko 0,04% obshhej radioaktivnosti jeffljuenta, on predstavljaet 75-95% vseh radionuklidov obnaruzhennyh v bol'shinstve vzjatyh na issledovanie ryb. (author)

  1. Incineration/vitrification of radioactive wastes and combustion of pyrolysis gases in thermal plasmas; Incineration/vitrification de dechets radioactifs et combustion de gaz de pyrolyse en plasma d`arc

    Energy Technology Data Exchange (ETDEWEB)

    Girold, Ch. [CEA de la Vallee du Rhone, Departement de Retraitement des Dechets et du Demantelemnet, 30 - Marcoule (France)]|[Limoges Univ., 87 (France)

    1997-03-01

    Two thermal plasma processes used for incineration of radioactive technological wastes (cellulose, plastics, rubber...) have been investigated. First, the different types of radioactive wastes are presented, with a special attention to those which may benefit from a high temperature thermal treatment. The most significant thermal plasma processes, suitable for this goal, are described. Then, the author deals with the post-combustion, in an oxygen plasma jet reactor, of gases from burnable radioactive waste pyrolysis. An experimental planning method as been used to evaluate the combustion performances in the reactor, with a wide range of gas composition and running parameters such as oxygen excess and electrical power. The results of a modeling of kinetics, based on 116 chemicals reactions between 25 species, are compared with experimental values. Finally, an oxygen plasma reactor where the arc is transferred on a basalt melt is experimented. The efficiency of the combustion and the homogeneity of the glass are discussed. The volatility of some glass elements and tracers added to the wastes is also approached in two different ways: by post-trial material balance and by an optical emission spectroscopic method. The author built a diagnostic method that allows the following versus time of the metallic vapours above the melt. (author) 51 refs.

  2. Detection of radioactive gases in the CO{sub 2} cooling the reactors G 2 - G 3; Detection des gaz radioactifs dans le CO{sub 2} de refroidissement des piles G2 - G3

    Energy Technology Data Exchange (ETDEWEB)

    Pouthier, J; Rossi, J [Commissariat a l' Energie Atomique, Chusclan (France). Centre de Production de Plutonium de Marcoule

    1968-07-01

    The carbon dioxide cooling the reactors G2 - G3 contains activation gases and fission gases. It is of interest to know their concentration, for example to be able to deduce rapidly the norms which would have to be applied in the case of an incident in the circuit. Gas-phase chromatography is applied daily for carrying out analyses. The chromatogram has separate peaks due to tritium, argon 41, krypton 85 and the 133 and 135 isotopes of xenon. By integrating each peak it is possible to calculate the specific activity of each product. The construction of an apparatus for carrying out continuous measurements is under consideration. (authors) [French] Le gaz carbonique, refroidissant les reacteurs G2 - G3, contient des gaz d'activation et des gaz de fission. Il est interessant de connaitre leur teneur par exemple pour etre en mesure de deduire rapidement les normes qu'il y aurait lieu d'appliquer en cas d'incidents sur le circuit. La methode de chromatographie en phase gazeuse est employee quotidiennement pour faire des analyses. Le chromatogramme se presente sous forme de pics distincts dus au tritium, a l'argon 41, au krypton 85 et aux isotopes 133 et 135 du xenon. L'integration de chaque pic permet de calculer l'activite specifique de chaque compose. Il est envisage de construire un appareil pour des mesures en continu. (auteurs)

  3. A review on the Cigeo project, the industrial centre of geological storage of the most radioactive wastes; Le point sur le projet Cigeo, centre industriel de stockage geologique pour les dechets les plus radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-02-15

    This document briefly presents the Cigeo project which is designed for the underground geological storage of the most radioactive wastes. Requirements comprise safety after closure and without any human intervention, and a reversible operation during at least 100 years. The storage principle is briefly described. A brief history of this research project is reported

  4. Researches on the management of high activity and long-lived radioactive wastes. Axis 1 - separation-transmutation; Recherches sur la gestion des dechets radioactifs a haute activite et a vie longue. Axe 1 - separation-transmutation

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-11-15

    This document gathers the transparencies of seven presentations given at a technical workshop of the French nuclear energy society (SFEN) about the researches on separation-transmutation of high activity and long-lived radioactive wastes. The presentations deal with: inventory and radiotoxicity of the rad-wastes in concern; industrial experience; experience on chemical separation: molecules and processes; reactors physics and transmutation - reactors for transmutation; fuels and targets; scenarios that include transmutation; environmental impacts of these different scenarios. (J.S.)

  5. No 2906. Proposal of law with the aim of organizing the durable management of radioactive wastes; No 2906. Proposition de loi tendant a organiser la gestion durable des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-02-15

    This proposal of law is the result of a long thinking enriched by 15 years of reports preparation, workshops and exchange with foreign organizations in charge of radioactive waste management, mainly carried out in the framework of the December 30, 1991 law. This proposal of law deals with the following points: general conditions of the management of radioactive wastes, rules relative to the reprocessing of foreign wastes, national plan for the management of radioactive wastes, creation of a national commission of evaluation of the research work on the management of high-activity and long-lived radioactive wastes, creation of a funds for the financing of the research and the industrial management of radioactive wastes, the three complementary methods of waste management for the high-activity and long-lived wastes, date lines for the implementation of a first experimental reactor for transmutation, for a long duration surface or sub-surface storage facility and for a reversible disposal center, concerting obligation with people's representatives and creation of a public interest group, financial contribution allocated to territory authorities, radioactive wastes proprietorship, creation of a local information and follow-up committee for radioactive waste facilities, and eventual charge compensations relative to the implementation of this law. (J.S.)

  6. Comprehensive measurements in 4 {pi} geometry for radio-active samples having a low {beta}-activity (1962); Ensemble de mesure'en geometrie 4 {pi} pour echantillons radioactifs de faible activite {beta} (1962)

    Energy Technology Data Exchange (ETDEWEB)

    Colomer, J; Valentin, M [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1961-07-01

    The realisation is described of a comprehensive measurement system having low background noise and, as well as a lead-wall protection, an electronic protection made up of a plastic scintillator placed in anticoincidence with the 4 {pi} counter used for making the measurements. The apparatus is described and its performance discussed. (authors) [French] Realisation d'un ensemble de mesures ayant un faible bruit de fond en utilisant en plus d'une protection par murs de Pb, une protection electronique constituee par un scintillateur plastique mis en ainticoincidence avec le compteur 4 {pi} utilise pour faire les mesures. L'appareillage est decrit et ses performances discutees. (auteurs)

  7. The Containment of Radioactive Wastes in Deep Geologic Formations; L'Elimination des Dechets Radioactifs dans les Formations Geologiques Profondes; 0423 0414 0414 ; Evacuacion de Desechos Radiactivos en Formaciones Geologicas Profundas

    Energy Technology Data Exchange (ETDEWEB)

    Kaufman, W. J. [University of California, Berkeley (United States)

    1960-07-01

    Generally the volumes of low- and intermediate-level radioactive wastes produced at chemical processing sites are so great as to make permanent storage prohibitively costly. In many instances chemical treatment may provide sufficient decontamination to allow the discharge of these effluents to surface streams or estuaries. However, in some circumstances such methods are costly and either do not make possible adequate decontamination, or result in excessively large volumes of semi-solid wastes that must be permanently stored. It is believed that in such a situation the deep underlying formations of the earth may constitute a safe and economic waste-disposal resource. In sandstone formations large volumes of waste may be stored with a high degree of containment integrity. Both the interstitial voids and ion-exchange properties serve to make available a great storage capacity. The disposal system employing deep formations of the earth is conceived to consist of a pattern of injection wells for introducing the waste, and of relief wells which serve to reduce well-head pressures, permit monitoring, and direct the flow in such a manner as to make maximum use of the formation. Information needed for the design of such a system includes data on the dispersion or short-circuiting properties of the formations, ion-exchange characteristics of the media, and the chemical and radiochemical properties of the waste. A two-well prototype injection system has been in operation for two years at the Engineering Field Station of the University of California. (author) [French] En general, les dechets de faible ou moyenne activite produits dans les usines de traitement chimique atteignent un volume tel que le cout de leur entreposage permanent est prohibitif. Dans plusieurs cas, un traitement chimique peut produire une decontamination suffisante pour que ces effluents puissent etre jetes dans des cours d'eau et des estuaires. Dans certaines circonstances, cependant, ces methodes sont onereuses ; en outre, ou bien elles ne permettent pas une decontamination suffisante, ou bien elles donnent de grandes quantites de dechets semi-solides qui doivent etre entreposes d'une facon permanente. On croit qu'en pareils cas les dechets peuvent etre enfouis d'une maniere sure et a peu de frais dans les profondeurs des formations sous-jacentes du sol. De grandes quantites de dechets peuvent etre entreposees avec une tres forte probabilite d'isolement parfait dans les formations greseuses. Les vides interstitiels et les proprietes d'echange d'ions permettent de disposer d'une grande capacite d'entreposage. Les installations d'elimination qui permettent d'utiliser les formations profondes du sol comprennent des puits d'injection par lesquels on introduit les dechets et des puits de surete qui servent a reduire la pression a l'orifice des puits, a exercer un controle radiologique des operations et a diriger les effluents de maniere a utiliser la formation au maximum. Pour etablir le projet d'une telle installation, on a besoin de renseignements comprenant des donnees sur les proprietes de dispersion de la formation, les caracteristiques d'echange d'ions de la couche et les proprietes chimiques et radiochimiques des dechets. Le prototype d'une installation d'injection a deux puits fonctionne depuis deux ans a l'Engineering Field Station de l'Universite. (author) [Spanish] Por lo comun, el volumen de los desechos radiactivos de actividad baja e intermedia producidos en las instalaciones de tratamiento quimico es tan considerable que el coste de su almacenamiento permanente resulta prohibitivo. En muchos casos el tratamiento quimico permite alcanzar un grado de descontaminacion suficiente para permitir la evacuacion de los efluentes en estuarios o corrientes de agua superficiales. No obstante, en determinadas circunstancias estos metodos son demasiado costosos, y no permiten lograr un grado suficiente de descontaminacion o dan lugar a la formacion de enormes cantidades de desechos en estado semi-solido que han de almacenarse de modo permanente. Se estima que en tales casos las formaciones geologicas profundas pueden constituir un lugar de evacuacion satisfactorio desde el punto de vista de la seguridad y de la economia. En las formaciones de arenisca resulta posible acumular grandes cantidades de desechos con un alto grado de estabilidad del confinamiento. Merced a sus cavidades intersticiales y caracteristicas de intercambio ionico, esas formaciones suelen poseer una capacidad de almacenamiento muy considerable. En principio, el sistema de evacuacion que utiliza las formaciones geologicas profundas ha de consistir en un conjunto de pozos de inyeccion por los que se introducen los desechos, y de pozos de compensacion que sirven para reducir la presion en la boca de los pozos, medir la radiactividad y dirigir el flujo de tal modo que se aproveche al maximo la capacidad de almacenamiento de la formacion. Entre los datos necesarios para proyectar un sistema de este tipo figuran las propiedades de dispersion de la formacion sus caracteristicas de intercambio ionico y las propiedades quimicas y radioquimicas de los desechos. En el Centro tecnologico experimental de la Universidad de California viene funcionando desde hace dos anos un sistema piloto de dos pozos con una capa acuifera. (author) [Russian] Obychno na predprijatijah himicheskoj obrabatyvajushhej promyshlennosti radioaktivnye othody s nizkim i srednim urovnjami aktivnosti imejut mesto v takom bol'shom kolichestve, chto ih hranenie v techenie dolgogo vremeni nerentabel'no. Vo mnogih sluchajah himicheskaja obrabotka othodov mozhet obespechit' dostatochnuju ih dezaktivizaciju dlja otvoda othodov v reki ili morja. Odnako v nekotoryh sluchajah takie metody trebujut zatrat i libo ne obespechivajut dostatochnoj dezaktivacii, libo privodjat v itoge k obrazovaniju chrezvychajno bol'shogo kolichestva polutverdyh othodov, dlja kotoryh neobhodimo obespechit' stacionarnoe hranenie. Predpolagaetsja, chto v takom sluchae glubokie geologicheskie obrazovanija mogut javit'sja mestami dlja bezopasnogo i renta- bil'nogo zahoronenija othodov. V obrazovanijah peschanika mozhno hranit' v bol'shom kolichestve othody s vysokoj aktivnost'ju. Kak obshhee svojstvo zhidkostej, vsegda stremjashhihsja zapolnit' pustoty, tak i osobennosti ionnogo obmena v othodah blagoprijatstvujut shirokomu ispol'zovaniju takih emkostej dlja hranenija othodov. Sistema udalenija othodov, v kotoroj ispol'zujutsja glubokie geologicheskie obrazovanija, kak schitajut, sostoit iz sistemy vpusknyh skvazhin dlja vvedenija othodov i razgruzochnyh skvazhin, kotorye sluzhat dlja kontrolja i regulirovanija potoka othodov s cel'ju obespechit' naibolee racional'noe ispol'zovanie emkosti. Nuzhnye svedenija dlja proektirovki takoj sistemy vkljuchajut dannye po dispersionnym svojstvam, obrazovaniju dannoj geologicheskoj formacii, osobennostjam ionnogo obmena sredy, a takzhe po himicheskim i radiohimicheskim svojstvam othodov. V tehnicheskoj polevoj stancii universiteta v techenie dvuh let dejstvuet opytnaja dvuhskvazhennaja vpusknaja sistema. (author)

  8. Some analytical methods used by the Marcoule Centre for the control of radioactive effluents; Quelques methodes analytiques, utilisees sur le centre de Marcoule pour le controle radioactif des effluents

    Energy Technology Data Exchange (ETDEWEB)

    Scheidhauer, J.; Messainguiral, L.; Drogue, N.; Meiranesio, A. M.

    1962-07-09

    After three years of operation, the authors propose a review of the various methods used to determine the radioactivity of wastewaters released by the Marcoule Centre Laboratory. They describe the three main steps of this control: firstly, measurements of the global alpha radioactivity and beta radioactivity (principle and measurement method), secondly, dosing of strontium 89 and strontium 90 (principle, used reactants, operation mode for nitric compound precipitation, ferric decontamination, separation of barium 140, oxalic precipitation, precipitate counting, exploitation of counting results), and thirdly, the possible dosing of other fission products present in the effluents: cerium 144, plutonium (by two different methods), natural uranium, caesium 137, zirconium 95, niobium 95, ruthenium 103 and 106, iodine 131. The principle, reactants, operational mode with different precipitations, measurement devices are indicated for each of these radio-elements.

  9. Movement of Radioactive Effluents in Natural Waters at Hanford; Le Mouvement des Effluents Radioactifs dans les Eaux Naturelles a Hanford; 0414 0412 0418 0416 0414 ; Movimiento de los Efluentes Radiactivos en Aguas Naturales en Hanford

    Energy Technology Data Exchange (ETDEWEB)

    Honstead, J. F.; Foster, R. F.; Bierschenk, W. H. [Hanford Laboratories Operation, Hanford Atomic Products Operation, General Electric Company, Richland, WA (United States)

    1960-07-01

    The Hanford plant is located in a semi-arid region on a very thick bed of unconsolidated water-deposited sediments resting on the basalt bedrock. This material may be considered in two geologic units, the lower bed being much less permeable than the upper. The Columbia River flows through the plant area and it is first used for human consumption about 55 km downstream from the last reactor plant. Low-level effluent from the reactors is discharged into the Columbia River after a one-to-three hours' hold-up period in retention basins. More than 60 radioisotopes have been identified in the effluent, nearly all of very short half-life. Depletion of various radioisotopes in river water by mechanisms other than decay is observed. This averages about 40% in the 55 km between the reactors and Pasco and is ascribed to biological assimilation and sedimentation processes. Low-level waste solutions from chemical processing plants are discharged into the ground where they seep through 70 to 120 m of sediments before reaching the local water table. Most of the radioactive material is immobilized by adsorption or other reactions during passage through the soil. The water and the few contaminants that reach the water-table move with the ground water towards the Columbia River. The rate and direction of travel are determined by the form of the water-table surface and the hydraulic characteristics of the transmitting aquifers. The local water-table configuration has been radically affected by the disposal of large volumes of water. From the gradient and the measured permeabilities of the aquifers an average 'travel time' for water of 180 years is estimated. Is is recognized that the maximum velocity may be several times the average. However, the effect of adsorption or other reactions is to greatly slow down the movement of dissolved material relative to the rate of movement of the water. No movement of fission products from the disposal sites to the river has been detected. (author) [French] L'installation de Hanford se trouve dans une region semi-aride-de sediments non consolides en couche tres epaisse, qui ont ete deposes par les eaux et reposent sur un lit rocheux basaltique. Ces roches forment deux couches geologiques, la couche inferieure etant beaucoup moins permeable que la couche superieure. La Columbia traverse les terrains de l'installation et ce n'est qu'a environ 55 kilometres en aval du dernier reacteur qu'on commence a utiliser les eaux pour la consommation humaine. Les effluents de faible intensite provenant des reacteurs sont evacues dans la Columbia apres un sejour d'une a trqis heuges dans des reservoirs. Dans les effluents, on a pu identifier plus de 60 radioisotopes, qui, pour la plupart, ont y une tres courte periode. On a observe l'appauvrissement de l'eau fluviale en plusieurs radioisotopes par suite de mecanismes autres que la desintegration. Cet appauvrissement atteint 40% en moyenne sur les 55 kilometres qui separent les reacteurs et Pasco; il serait du a des processus d'assimilation biologique et de sedimentation. Les solutions de dechets de faible intensite provenant des usines de traitement chimique sont evacuees dans le sol ou elles filtrent a travers les sediments sur une profondeur de 70 a 120 metres avant d'atteindre la nappe aquifere. Pendant leur passage a travers le sol, la plupart des substances radioactives sont retenues par adsorption ou par d'autres reactions. L'eau et les quelques contaminants qui atteignent le niveau hydrostatique se deplacent avec les eaux souterraines en direction de la Columbia. La vitesse et la direction de ce deplacement sont determines par la forme de la surface piezometrique et les caracteristiques hydrauliques de l'aquifere. La configuration locale de la nappe a ete fortement influencee par l'evacuation de grandes quantites d'eau. Compte tenu du gradient hydraulique et du degre de permeabilite des aquiferes, on estime a 180 annees la duree moyenne du deplacement de J'eau. On reconnait que la vitesse maximum peut etre plusieurs fois superieure a cette moyenne. Cependant, l'adsorption ou les autres reactions ont pour effet de ralentir considerablement le mouvement des matieres dissoutes par rapport a la vitesse de deplacement de l'eau. On n'a decele aucun mouvement de produits de fissino entre les lieux d'evacuation et le fleuve. (author) [Spanish] La instalacion atomica de Hanford esta situada en un terreno semiarido asentado sobre una capa muy espesa de sedimentos sin consolidar depositados por el agua, que descansa sobre un lecho rocoso de basalto. Estos materiales pueden considerarse como dos formaciones geologicas distintas, pues la capa inferior es mucho menos permeable que la superior. El rio Columbia atraviesa los terrenos de la instalacion y el primer lugar donde sus aguas se utilizan para el consumo humano se encuentra a unos 55 km, rio abajo, del ultimo reactor. El efluente de baja actividad originado por los reactores se descarga en el rio despues de retenerlo de una a tres horas en estanques dispuestos al efecto. En el efluente se han detectado mas de 60 radioisotopos, casi todos ellos de periodo muy corto. Se ha observado que el agotamiento de algunos radioisotopos en las aguas del rio no solo se debe a procesos de desintegracion. Este agotamiento alcanza un valor medio del 40 por ciento en los 55 km que hay de los reactores a Pasco, y se supone que es el. efecto de procesos biologicos de asimilacion y sedimentacion. Los desechos liquidos de baja 'actividad procedentes de las plantas de tratamiento quimico se descargan en el terreno, donde se filtran a traves de sedimentos de 70 a 120 metros de espesor antes de alcanzar el manto freatico de la localidad. La mayor parte de las sustancias radiactivas quedan inmovilizadas por adsorcion u otras reacciones que tienen lugar a su paso a traves del terreno. El agua y las escasas sustancias contaminantes que llegan al manto freatico se desplazan con las aguas subterraneas hacia el rio Columbia. La velocidad y direccion de desplazamiento dependen de la forma de la superficie del manto y de las caracteristicas hidraulicas de las capas acuiferas portadoras. La forma del manto freatico ha sufrido una profunda modificacion debido a la evacuacion de grandes cantidades de agua. Basandose en la pendiente de las capas acuiferas y en las mediciones de su permeabilidad, se ha calculado que el desplazamiento dura por termino medio 180 anos. Se admite que la velocidad maxima puede ser varias veces superior a la media senalada. Sin embargo, el efecto de la adsorcion o de otras reacciones es disminuir considerablemente la velocidad de desplazamiento de las sustancias radiactivas, en relacion con la velocidad de las aguas. No hay indicios de que los productos de fision se esten desplazando desde los lugares de evacuacion hacia el rio. (author) [Russian] Hjenfordskij zavod raspolozhen v poluzasushlivom rajone na ochen' tolstom sloe netverdyh, soderzhashhih vodu otlozhenij, na korennoj bazal'tovoj porode. Takim obrazom mozhno rassmatrivat' dve geologicheskih porody, iz kotoryh nizhnjaja znachitel'no menee pronicaema. Reka Kolumbija protekaet cherez territoriju zavoda, i ee voda ispol'zuetsja dlja potreblenija tol'ko v 55 km vniz po techeniju ot poslednej ustanovki. Nizkoaktivnye zhidkie othody iz reaktorov slivajutsja v reku Kolumbiju posle 1-3 chasov vyderzhki v special'nyh bassejnah-otstojnikah. V takih othodah obnaruzheno bolee 60 radioizotopov, prichem pochti vse iz nih imejut ochen' korotkij period poluraspada. Rassmatrivajutsja voprosy obednenija, ne vkljuchaja obychnyj raspad, razlichnyh radioizotopov v rechnoj vode pomimo obychnogo raspada. Na rasstojanii 55 km mezhdu reaktorami i Pasko takoe obednenie v srednem sostavljaet 40% i ob{sup j}asnjaetsja processami biologicheskogo pogloshhenija i osazhdenija. Nizkoaktivnye rastvory zhidkih othodov s himicheskih zavodov po obrabotke topliva udaljajutsja v zemlju; oni dolzhny prosochit'sja cherez 70-120 metrov osadochnyh porod, prezhde chem dostignut podzemnyh vod. Bol'shinstvo radioaktivnyh materialov zaderzhivaetsja putem pogloshhenija ili drugih reakcij pri prohozhdenii cherez pochvu. Ochishhennaja takim obrazom voda i neznachitel'nye othody, dostigajushhie podzemnyh vod, napravljajutsja vmeste s nimi k reke Kolumbii. Skorost' i napravlenie opredeljajutsja formoj vodnogo gorizonta i gidravlicheskimi harakteristikami vodonosnyh plastov. Bol'shie ob{sup e}my vody, slivaemye v grunt, okazali korjonnoe izmenenie na harakter gorizonta podzemnyh vod. Ishodja iz izmerennoj pronicaemosti vodonosnyh plastov, srednee vremja prohozhdenija vody ocenivaetsja v 180 let. Priznaetsja takzhe to, chto maksimal'naja skorost' mozhet znachitel'no prevyshat' srednjuju velichinu. Odnako, vlijanie pogloshhenija ili drugih reakcij ochen' sil'no zamedljajut dvizhenie rastvorennogo materiala po otnosheniju k skorosti dvizhenija vody. Ne bylo obnaruzheno proniknovenija produktov delenija iz rajonov udalenija v rechnuju vodu. (author)

  10. Treatment, as radio-active waste, of large pieces of {proportional_to}-contaminated apparatus (1962); Conditionnement en tant que dechet radioactif de gros materiel contamine en {proportional_to} (1962)

    Energy Technology Data Exchange (ETDEWEB)

    Boutot, P; Capitaine, A; Giachetto, I [Commissariat a l' Energie Atomique, Centre de Production de Plutonium, Marcoule (France). Centre d' Etudes Nucleaires

    1962-07-01

    Two solutions have been adopted: - removal of the material from its original container, treatment in a special container; - treatment of the material directly inside its original protective packing. The treatment of a fluorination oven illustrates the second process. After a thorough cleaning of the enclosure, the oven is fixed in and the contamination held in place by a varnish. The assembly is placed in a special container and covered with shaken-down concrete. The container is shut by means of a welded cover. The operations are carried out under reduced pressure. At the end of this process it is impossible to detect any residual radioactivity. (authors) [French] Deux solutions ont ete adoptees: - extraire le materiel de son enveloppe d'origine et le conditionner dans un container special; - conditionner le materiel directement a l'interieur de la protection d'origine. Le conditionnement d'un four de fluoration illustre le deuxieme procede. Apres un nettoyage complet de l'enceinte, le four en a ete rendu solidaire et la contamination a ete fixee au moyen d'un vernis. L'ensemble a ete place dans un container special et enrobe de beton vibre. Le container a ete ferme par un couvercle soude. L'ensemble des operations a ete realise sous depression. A la suite de ces operations aucune activite residuelle n'a ete decelee. (auteurs)

  11. Treatment of Radioactive Effluents at the Saclay Nuclear Research Centre; Traitement des Effluents Radioactifs au Centre d'Etudes Nucleaires de Saclay; 041e 0414 ; Tratamiento de los Efluentes Radiactivos en el Centro de Energia Nuclear de Saclay

    Energy Technology Data Exchange (ETDEWEB)

    Wormser, G. [Service de Controle des Radiations et de Genie Radioactif, Commissariat a l' Energie Atomique, Saclay (France)

    1960-07-01

    The Report Gives The Account Of Four Years' Experience In Operating The Treatment Plant For Effluents From The Saclay Nuclear Research Centre. It Contains Data Relating To The Origin, Volume And Treatment Of Waste. (author) [French] Ce rapport presente un bilan d'exploitation de l'installation de traitement des effluents du Centre d'etudes nucleaires de Saclay depuis quatre ans. On donne des chiffres concernant l'origine des residus, leur volume, leur traitement. (author) [Spanish] El autor hace un balance de explotacion de la instalacion de tratamiento de efluentes del centro de Saclay desde hace cuatro anos, dando las cifras correspondientes al origen de los residuos, a su volumen y a su tratamiento. (author) [Russian] V jetom dokumente podvoditsja itog chetyrehletnej jekspluatacii ustanovki po obrabotke zhidkih othotov v Centre jadernyh issledovanij v Sakle. V doklade privodjatsja dannye o proishozhdenii othodov, jh ob'eme i obrabotke. (author)

  12. Report on the evaluation of the national plan on radioactive wastes and materials management; Rapport sur l'evaluation du plan national de gestion des matieres et des dechets radioactifs (PNG-MDR)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-02-15

    This document constitutes the evaluation of the first edition of the National Plan on radioactive wastes and materials management. It presents the definitive or temporary solutions for the radioactive wastes management, the national plan juridical framework defined by the laws of 1991 and 2006 and the first evaluation and perspectives. (A.L.B.)

  13. Development of a machine for sorting laundry according to its radioactive contamination (1962); Conception et mise en oeuvre d'une machine a trier le linge en fonction de sa contamination par des produits radioactifs (1962)

    Energy Technology Data Exchange (ETDEWEB)

    Cohendy, G; Alles, M; Pellerin, A [Commissariat a l' Energie Atomique, Centre de Production de Plutonium, Marcoule (France). Centre d' Etudes Nucleaires

    1962-07-01

    A the Marcoule Plutonium Production Centre special clothing is worn, in the active zones. A large fraction of these clothes is contaminated and must therefore be subjected to specialised treatments during washing in order to be reintroduced subsequently without danger. Because of the large amount of clothes to be treated it has become necessary to install a special semi-automatic machine; the role of the operator is limited to placing the clothing in the machine and to removing the baskets of sorted clothes. The machine itself has been designed and built by the Mechanics Section. The Radiation Protection Service chose the sorting method which is based on {beta} radiation and uses Geiger counters actuating an appropriate electronic system; the Service also developed this system, depending on the various degrees of contamination of the treated clothing. (authors) [French] Le Centre de Production de Plutonium de Marcoule utilise des vetements speciaux pour travailler dans les zones actives. Une proportion importante de ces vetements se contamine et doit, de ce fait, subir des traitements appropries au cours du lavage, de facon a pouvoir etre reintroduits sans danger dans le circuit d'utilisation. Devant l'importance des quantites a traiter, il est apparu necessaire de mettre en place une machine speciale, semi-automatique; le role de l'operateur, consiste en effet uniquement a introduire le linge dans la machine et a extraire de celle-ci les paniers de linge trie. La Section de Mecanique a concu et realise la machine proprement dite. Le Service de Protection contre les Radiations a choisi le mode de tri qui s'effectue en {beta} a l'aide de compteurs Geiger actionnant une electronique appropriee et a assure la mise au point de cette electronique, en fonction des divers degres de contamination du linge a trier. (auteurs)

  14. Nuclear toxicology file: cell response to the steady or radioactive chemical elements exposure; Dossier toxicologie nucleaire: reponse cellulaire a l'exposition aux elements chimiques stables ou radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Lopez, B.S.; Saintigny, Y. [Centre National de la Recherche Scientifique (CNRS), Sciences du Vivant, UMR 217, 92 - Fontenay aux Roses (France); CEA Fontenay aux Roses, IRCM, UMR 217, 92 (France); Adam, Ch. [Institut de Radioprotection et de Surete Nucleaire (IRSN:DEI/SECRE), Lab. de Radioecologie et d' Ecotoxicologie, 13 - Saint-Paul-lez-Durance (France)

    2008-09-15

    The cellular response to an exposure in a toxic element is made at different levels. The first level is the agent detoxication by its elimination or its neutralization. The second level is the repair of the damages caused by this agent (for example the DNA repair). The third level is the control of the cellular death programmed to eliminate the irreparably damaged cells.Finally, the hurt cell can inform the nearby cells by producing molecular effectors inducing an abscopal or bystander effect. (N.C.)

  15. The choice of sites considered with respect to problems of radioactive waste disposal; Le choix des sites considere dans ses rapports avec les problemes de rejets d'effluents radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Duhamel, F [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1960-07-01

    The author of this article shows clearly that a knowledge of the behaviour of wastes together with an analysis of the risks of accidents makes it possible to define the general characteristics of a site as a function of, on the one hand the geological and meteorological factors, and on the other, the proposed installations. Consideration of the biological environment makes it possible to clarify the sitological study and to make a choice between the several sites possible. The author shows the real necessity for radio-protection specialists to share their knowledge, to establish regulations, and to cooperate with the authors responsible for the installations, from the moment of the choice of the site and of the planning of the apparatus up to the final reject of the waste. (author) [French] L'auteur de ce rapport montre clairement que la connaissance du comportement des effluents jointe a l'analyse des risques d'accident permettent de degager les caracteristiques generales d'un site en fonction d'une part, des donnees geologiques et meteorologiques, d'autre part des installations projetees. La consideration du milieu biologique permet de preciser l'etude sitologique et d'effectuer un choix entre plusieurs sites donnes. L'auteur met en evidence la necessite absolue pour les specialistes de la radioprotection d'echanger leurs connaissances, d'etablir des reglements et de cooperer avec les autorites responsables des installations depuis le choix des sites et le projet des appareillages jusqu'au rejet ultime des residus. (auteur)

  16. The low to intermediate activity and short living waste storage facility. For a controlled management of radioactive wastes; Le centre de stockage des dechets de faible et moyenne activite a vie courte. Pour une gestion controlee des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    Sited at about 50 km of Troyes (France), the Aube facility started in 1992 and has taken over the Manche facility for the surface storage of low to intermediate and short living radioactive wastes. The Aube facility (named CSFMA) is the answer to the safe management of these wastes at the industrial scale and for 50 years onward. This brochure presents the facility specifications, the wastes stored at the center, the surface storage concept, the processing and conditioning of waste packages, and the environmental monitoring performed in the vicinity of the site. (J.S.)

  17. Colloquium C.L.I. operators and others... the becoming of radioactive products after use; Les CLI, les exploitants et les autres... Le devenir des produits radioactifs apres utilisaiton

    Energy Technology Data Exchange (ETDEWEB)

    Ancelin, G.; Artus, J.C.; Atteia, M.; Audebert, P.; Ballat, J.; Balle, St.; Bardols, M.; Basse-Cathalinat, B.; Baylet, J.M.; Bazot, G.; Beaufils, B.; Benech, R.; Bongiovanni, J.; Bontoux, J.; Boueilh, M.; Brunet, F.; Calafat, A.; Cartier, M.; Cavereau, S.; Cavereau, G.; Chambon, B.; Chouchan, M.; Criton, P.; Coudre-Genetti, S.; Bretesche, O. de la; Delcourt, R.; Delibes, J.L.; Diaham, A.; Dupouis, N.; Dutil, V.; Eimer, M.; Fauvre, D.; Figueredo, G.; Fongaro, G.; Gaillard, P.; Gazal, S.; Graschaire, G.; Grenier, St.; Ibert, J.; Jacob, E.; Kozlowski, E.; Laroche, D.; Le Bars, Y.; Linfort, J.M.; Sabatier, M.A.; Sasseigne, Ph.; Saut, C.; Sornein, J.F.; Terrenne, J.P.; Donzac, M. de; Thiese, I.; Tfibel, V.; Vidal, J.; Vieillard-Baron, B.; Vincent, D

    2006-07-01

    Colloquium to Golfech on September 17. and 18., 2003. The 3. colloquium of the A.N.C.L.I. took place to Golfech, to Alexis Calafat invitation, President of the C.L.I. of Golfech. The reserved subject was ' the C.L.I., the developers and the others: than can bring the various bodies of the nuclear power to the C.L.I.? ' A half-day was dedicated in particular to the future of the radioactive products after use, where the question of the transport of radioactive products was approached. 80 persons participated. The titles of the approached subjects were: dimensions of the expertise and the construction of the information; the C.L.I and its various interlocutors; C.L.I.N., the developer, the others and the transparency of the information; waste and radioactive waste in a hospital environment; safety of the transport of radioactive material; the relations of the Golfech C.N.P.E. with the C.L.I.; the new institute of radiation protection and nuclear safety; the national agency for the management of the radioactive waste, what projects; Implementation of municipal protection plans on the C.L.I. initiative; Socio-economic effects from the installation of Paluel and Penly C.N.P.E.; The case of the Garonne: the iodine 131 contamination; Analysis of the environment in contact with the secondary school of Bar-sur-Aube; C.L.I., the developer and the others: what relations. (N.C.)

  18. Impact of cementitious materials decalcification on transfer properties: application to radioactive waste deep repository; Influence de la decalcification de materiaux cimentaires sur les proprietes de transfert: application au stockage profond de dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Perlot, C

    2005-09-15

    Cementitious materials have been selected to compose the engineering barrier system (EBS) of the French radioactive waste deep repository, because of concrete physico-chemical properties: the hydrates of the cementitious matrix and the pH of the pore solution contribute to radionuclides retention; furthermore the compactness of these materials limits elements transport. The confinement capacity of the system has to be assessed while a period at least equivalent to waste activity (up to 100.000 years). His durability was sustained by the evolution of transfer properties in accordance with cementitious materials decalcification, alteration that expresses structure long-term behavior. Then, two degradation modes were carried out, taking into account the different physical and chemical solicitations imposed by the host formation. The first mode, a static one, was an accelerated decalcification test using nitrate ammonium solution. It replicates the EBS alteration dues to underground water. Degradation kinetic was estimated by the amount of calcium leached and the measurement of the calcium hydroxide dissolution front. To evaluate the decalcification impact, samples were characterized before and after degradation in term of microstructure (porosity, pores size distribution) and of transfer properties (diffusivity, gas and water permeability). The influence of cement nature (ordinary Portland cement, blended cement) and aggregates type (lime or siliceous) was observed: experiments were repeated on different mortars mixes. On this occasion, an essential reflection on this test metrology was led. The second mode, a dynamical degradation, was performed with an environmental permeameter. It recreates the EBS solicitations ensured during the re-saturation period, distinguished by the hydraulic pressure imposed by the geologic layer and the waste exothermicity. This apparatus, based on triaxial cell functioning, allows applying on samples pressure drop between 2 and 10 MPa and temperature from 20 to 80 C. Water permeability evolution relating to experimental parameters, uncoupled or coupled, was relied to mortars microstructural modifications. (author)

  19. MUST, a set of strip detectors for studying radioactive beams induced reactions; MUST, un ensemble de detecteurs a pistes pour l`etude des reactions induites par faisceaux radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Blumenfeld, Y.; Barbier, A.; Beaumel, D.; Charlet, D.; Clavelin, J.F.; Douet, R.; Engrand, M.; Lebon, S.; Lelong, P.; Lesage, A.; Leven, V.; Lhenry, I.; Marechal, F.; Petizon, L.; Pouthas, J.; Richard, A.; Rougier, D.; Soulet, C.; Suomijaervi, T.; Volkov, P.; Voltolini, G. [Paris-11 Univ., 91 - Orsay (France). Inst. de Physique Nucleaire; Auger, F.; Ottini, S.; Alamanos, N. [CEA Centre d`Etudes de Saclay, 91 - Gif-sur-Yvette (France). Dept. d`Astrophysique, de la Physique des Particules, de la Physique Nucleaire et de l`Instrumentation Associee; Sauvestre, J.E.; Bonnereau, B.; Champion, L.; Delbourgo-Salvador, P.; Ethvignot, T.; Szmigiel, M. [CEA Centre d`Etudes de Bruyeres-le-Chatel, 91 (France)

    1996-12-31

    This report states the specificity of light particles elastic scattering, and the need of detecting recoil protons to improve angular resolution. Then the development of a specific MUST strip detector is detailed: 60 strips detectors with Si O sub 2 dielectric, that yield 500 ps time resolution, and Si (Li) detectors following next. A versatile data acquisition system has been developed too, with CAMAC interface to suit to any experimental plant. (D.L.). 27 refs.

  20. Long-lived high and intermediate level radioactive wastes: defining the context, stakes and perspectives; Dechets radioactifs de haute activite et de moyenne activite a vie longue: situer le contexte, les enjeux et les perspectives

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    The French law from December 30, 1991 has defined an ambitious 15 years program of researches in order to explore the different possible paths for the long-term management of long-lived high and intermediate level radioactive wastes. The law foresees also that at the end of the 15 years research program, a project of law will be prepared by the French government and transmitted to the European parliament in 2006. A public debate has been organized and emceed in 2005 in order dialogue with the general public and to gather its questions, remarks and fears. In the framework of their contribution to this debate, the ministries of industry and environment have prepared this document which answers some key questions about radioactive waste management: where do wastes come from, what are the risks, how are they managed today in France and in foreign countries, what are the results of the researches carried out during 15 years, what are the advantages and drawbacks of each waste management solution considered, what is the perspective of application of each solution, what is the position of experts, what will be the decision process. This synthetic document supplies some reference marks to better understand these different points. Some pedagogical files about radioactivity, fuel cycle, and nuclear industry activities are attached to the document. (J.S.)

  1. The elimination as radioactive waste of a fluorination furnace from the plutonium extraction plant (1962); Elimination comme dechet radioactif d'un four de fluoration en provenance de l'usine d'extraction du plutonium (1962)

    Energy Technology Data Exchange (ETDEWEB)

    Boutot, P; Capitaine, A; Giachetto, L [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1961-07-01

    The furnace, 1.60 x 0. 75 x 0.80 m in dimensions, was placed inside a 2. 50 x 1.25 x 2 m glove box. The operations were as follows: - removal of the furnace from the glove box; - storage of the furnace in a special container ; - reduction to a minimum volume and elimination of the glove box. A very high {alpha} activity, oxidation of the various channeling, and waste products trapped in the box necessitated special safety measures such as fixing of the contamination, crushing, the use of appropriate vinyl envelopes. This long and tedious work was carried out with no resulting bodily or atmospheric contamination. (authors) [French] Le four de 1,60 x 0,75 x 0,80 m, etait place dans une boite a gants de 2,50 x 1,25 x 2 m. L'operation a consiste: - a extraire le four de la boite a gants; - a le stocker dans un container special; - a reduire a un volume minimum la boite a gants pour l'eliminer. Une activite {alpha} tres elevee, l'oxydation des differentes canalisations, les dechets occlus dans la boite ont exige des moyens de protection speciaux tels que l'encollage de la contamination, la mise en depression, l'emploi d'enveloppes de vinyle appropriees. Ce travail, long et fastidieux, a ete effectue sans entrainer de contamination corporelle ou atmospherique. (auteurs)

  2. The management of nuclear wastes from diffuse nuclear activities. A processing adapted to each situation; La gestion des dechets radioactifs du nucleaire diffus. Un traitement adapte a chaque situation

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    The French national agency of radioactive wastes (ANDRA) works with more than a thousand of clients belonging to hospitals, research centers and industries. These are called 'small producers' because they generate a small quantity of wastes. However, because of the large variety of these wastes, they require suitable and specific processes for their management which are presented in this brochure. (J.S.)

  3. Study of radionuclides complexes formation by organic compounds in intermediate and low-level radioactive wastes; Etude de la mobilisation, par des complexants organiques, des radionucleides contenus dans les dechets radioactifs de faible et moyenne activite

    Energy Technology Data Exchange (ETDEWEB)

    Bourbon, X.

    1994-12-01

    In the general framework of the safety of nuclear wastes of low and intermediate activity, we studied the effects of organic compounds on the solubilization of metallic cations. Organic compounds originate from the degradation of cellulose in concrete interstitial waters. Degradation reactions generate a number of products, among which carboxylic acids. These acids are known for their chelating properties. We first analysed the degradation of cellulose in alkaline conditions: we qualitatively and quantitatively determined the degradation products for various reaction progress indices, including a dozen of carboxylic acids. The principal goal of our work was the prediction of the behaviour of metallic cations in such cellulose degradation solutions. Owing the complexity of the system, a priori theoretical calculation are not possible. We have thus decided to choose tetra hydroxy pentanoic acid as a reference compound in order to simulate as accurately as possible the behaviour of more complex acids which contain similar functional groups. We have experimentally determined the complexing properties of this reference acid toward divalent cobalt and copper, and trivalent samarium and europium. Simple and mixed complex (hydroxyl) have been evidenced in alkaline medium. Their stability constants have been determined and extrapolated at zero ionic strength using the SIT theory. These results allowed us to theoretically predict the behaviour of our four reference cations in cellulose degradation products formed in concrete interstitial waters. In parallel, we have measured their solubility in real cellulose degradation solutions. Solubility predictions are correct for transition metals, but not for rare earth cations. In this case the complexes which have been identified with tetra hydroxy pentanoic acid are not stable enough to dissolve metallic hydroxides. In real degradation solutions, other compounds would account for the enhancement of rare earth elements solubility.

  4. Experimental study of mechanical behaviour of a clay-stone: application to nuclear waste disposals; Etude experimentale du comportement mecanique d'argiles raides: application au stockage de dechets radio-actifs

    Energy Technology Data Exchange (ETDEWEB)

    Chiarelli, A.S. [Laboratoire de Materiaux et Sciences des Constructions, UPRES JE 2200, IUP Genie Civil et Infrastructures, 95 - Cergy Pontoise (France); Shao, J.F. [Laboratoire de Mecanique de Lille, URA CNRS 1441, EUDIL, 59 - Villeneuve d' Ascq (France); Ledesert, B. [Laboratoire de Sedimentologie et Geodynamique, FRE 2255, 59 - Villeneuve d' Ascq (France); Hoteit, N. [Agence Nationale pour la Gestion des Dechets Nucleaires (ANDRA), 92 - Chatenay Malabry (France)

    2001-02-01

    A study of mechanical behaviour of deep argillaceous rocks from East of France, the 'argilites de l'Est' as a potential host rock for radioactive waste disposal studied by ANDRA, (french national radioactive waste management agency) is presented. Some uniaxial and triaxial compression tests with unloading-reloading cycles were realised on samples from three different depths. Important plastic strains associated to directional degradation of elastic properties show that the two principles strain mechanisms are plasticity and induced anisotropic damage. At microscopic scale, it is related to sliding of clay sheets and oriented microcracks. The influence of mineralogy is that brittle behaviour is more important with calcite while it decreases with clay. (authors)

  5. Fabrication, characterization and radiation damage stability of hollandite based ceramics devoted to radioactive immobilisation; Synthese, caracterisation et etude du comportement sous irradiation electronique de matrices de type hollandite destinees au confinement du cesium radioactif

    Energy Technology Data Exchange (ETDEWEB)

    Aubin-Chevaldonnet, V. [CEA Valrho, Dir. de l' Energie Nucleaire (DEN/DETCD/SCDV), Dept. d' Etudes du Traitement et du Conditionnement des Dechets, Service de Conditionnement des Dechets et Vitrification, 30 - Marcoule (France)

    2004-11-01

    Research on treating specifically the long-lived and high level nuclear wastes, notably cesium, is currently carried out in France. Cesium immobilization in host matrices of high chemical durability constitutes the favoured option. Hollandite matrix is a good candidate because of its high cesium incorporation ability and its excellent chemical stability. During this study, different compositions of hollandite ceramics Ba{sub x}Cs{sub y}C{sub z}Ti{sub 8-z}O{sub 16} (C = Al{sup 3+}, Cr{sup 3+}, Ga{sup 3+}, Fe{sup 3+}, Mg{sup 2+}, Sc{sup 3+}), synthesized by oxide route, were characterized in terms of structure, microstructure and physical and chemical properties. Iron ions seems to be the most suitable of the studied C cations to get high-performance hollandites. The stability of these ceramics under external electron irradiation, simulating the {beta} particles emitted by radioactive cesium, were also estimated, at the macroscopic and atomic scale. The point defects creation and their thermal stability were followed by electron paramagnetic resonance. (author)

  6. Liver Scanning with Colloidal Radiogold; Exploration du foie a l'aide de l'or radioactif colloidal; Issledovanie pecheni pri pomoshchi radioaktivnogo kolloidal'nogo zolota; Exploracion del higado con oro coloidal radiactivo

    Energy Technology Data Exchange (ETDEWEB)

    Donato, L; Becchini, M F; Panichi, S [Centro di Medicina Nucleate, University of Pisa (Italy)

    1959-07-01

    The authors report their experience in the use of colloidal Au{sup 198} for liver scanning. To obtain a good differentiation of liver from surrounding organs and tissues, a tracer dose of 2.5 {mu}C/kg is usually required. The whole scanning procedure, starting 30 minutes after intravenous injection, takes about 90 minutes, when carried out with fully automatic equipment. Upper and lateral liver contours are usually better defined than the lower one; the use of focusing collimators (honeycomb type) increases the resolution remarkably. In normal conditions the liver is the only organ clearly evident on the scan; the spleen may also become evident in some cases of splenomegaly and liver cirrhosis, probably on account of the reduction of reticuloendothelial system of the liver. In the experience of the authors, the efficiency of the technique is very poor for the detection of liver metastases of small size, not inducing changes of the volume and shape of the liver. In fact, uncertain results have been obtained even in cases of micronodular metastatic diffusion, confirmed at operation. The Au{sup 198} scanning may be of help in cases with diffuse or zonal enlargement, whatever the origin, in order to establish whether the changes are due to enlargement of normally functioning tissue, or to the presence of intrahepatic pathologic entities. It has been found very helpful to combine liver scanning with x-ray examination of liver contours after carrying out a pneumoperitoneum, in order to compare anatomical and functional patterns. Scintigraphs and x-ray contours are normally superimposable, and the finding of significant discrepancies may be helpful in evaluating the possibility of surgical or radiation treatment in patients with tumours, especially of the gastrointestinal tract. Of course, a negative result will not rule out the possibility of liver metastases. Original scintigraphs and corresponding x-ray films are presented, and the results of major interest are discussed. (author) [French] Les auteurs decrivent la facon dont ils ont utilise l'Au{sup 198} pour l'exploration du foie. On se sert generalement d'une dose indicatrice de 2,5 {mu}C/kg pour distinguer nettement le foie des organes et tissus environnants. L'ensemble de l'exploration, qui commence 30 minutes apres l'injection intraveineuse, dure environ 90 minutes lorsqu'elle est faite avec un materiel entierement automatique. Les contours superieurs et lateraux du foie apparaissent d'ordinaire plus clairement que le contour inferieur; en se servant de collimateurs a focalisation (du type alveolaire) on accroit beaucoup la resolution. Normalement, le foie est le seul organe qui ressorte clairement; la rate peut egalement apparaitre dans certains cas de splenomegalie et de cirrhose du foie, probablement a cause de la reduction du systeme reticulo-endothelia l du foie. Les auteurs ont constate que cette technique ne permet guere de deceler les metastases du foie de petite dimension qui n'entrainent aucun changement dans le volume et la forme de l'organe. En fait, les resultats sont incertains meme dans les cas de diffusion metastatique micronodulaire confirmee par l'intervention operatoire. En cas d'hypertrophie diffuse ou zonale, quelle qu'en soit l'origine, l'exploration a l'aide de l'Au{sup 198} peut servir a determiner si les changements sont dus a l'hypertrophie de tissus fonctionnant normalement ou a la presence de corps pathologiques a l'interieur du foie. Les auteurs ont constate qu'il etait tres utile de combiner l'exploration du foie avec l'examen radiologique des contours de l'organe apres un pneumoperitoine, de facon a comparer le schema anatomique et le schema fonctionnel. Normalement, les scintigrammes et la radiographie des contours doivent coincider, et tout ecart important peut aider a determiner la possibilite d'une intervention chirurgicale ou radiotherapeutiqu e chez les patients qui souffrent de tumeurs, notamment dans l'appareil gastro-intestinal. Bien entendu, un resultat negatif n'exclut pas la possibilite de l'existence de metastases du foie. Les auteurs presentent des scintigrammes originaux, avec les radiographies correspondantes, et commentent les resultats les plus significatifs. (author) [Spanish] Los autores describen la experiencia que han adquirido con el empleo del {sup 198}Au para la exploracion del higado. Para diferenciar satisfactoriamente el higado de los organos y tejidos circundantes se requiere, por lo general, una dosis indicadora de 2,5 mcuries/kg. El procedimiento de exploracion, que se inicia 30 minutos despues de la inyeccion intravenosa, dura en total unos 90 minutos cuando se lleva a cabo con un equipo completamente automatico. Por lo general, los contornos superior y lateral del higado se destacan con mas claridad que el contorno inferior; el uso de colimadores de enfoque de tipo alveolar permite aumentar la resolucioen de manera considerable. En condiciones normales, el higado es el unico organo que aparece claramente en este tipo de examen; en algunos casos de esplenomegalia y de cirrosis hepatica, tambien puede observarse el bazo, probablemente a causa de la reduccion del sistema reticulo-endotelial del higado. Los autores han comprobado que esta tecnica es poco eficaz para la deteccion de pequenas metastasis del higado que no alteran ni el volumen ni la forma del organo. En realidad, los resultados son inciertos aun en los casos de difusion metastatica micronodular, confirmada al operar al paciente. En los casos de hipertrofia difusa o localizada, sea cual fuere su origen, la exploracion con {sup 198}Au puede resultar util para establecer si los cambios se deben a la hipertrofia de un tejido que funciona normalmente, o a la presencia de cuerpos patologicos en el interior del higado. Los autores han obtenido buenos resultados combinando la exploracion del higado con el examen radiologico de los contornos del organo despues de un neumoperitoneo, pues de esa forma pueden compararse los esquemas anatomico y funcional. (author) [Russian] Avtory soobshchayut o svoem opyte v ispol'zovanii kolloidal'nog o zolota Ah{sup 198} dlya issledovaniya pecheni. Dlya polucheniya chetkogo razgranicheniya pecheni ot sosednikh organov i okru-zhayushchikh tkanej obychno trebuetsya doza mechenykh ehlementov, sootvetstvuyushcha ya 2,5 {mu}C/Kg. Vsya protsedura issledovaniya, kotoraya nachinaetsya cherez 30 minut posle vnutrivennogo vspryskivaniya, zanimaet okolo 90 minut pri ispol'zovanii polnost'yu avtomaticheskoj apparatury. Verkhnie i bokovye kontury pecheni obychno luchshe razlichayutsya chem nizhnie. Ispol'zovanie fokusiruyushchi kh kollimatorov (poristogo tipa) znachitel'no uluchshaet poluchaemye rezul'taty. V obychnykh usloviyakh pechen' yavlyaetsya edinstvennym organom, kotoryj chetko viden na ehkrane. V nekotorykh sluchayakh pri splenomegalii i tsirroza pecheni mozhno krome togo videt' i selezenku, veroyatno v svyazi s sokrashcheniem retikulo-ehndotelialyyuj sistemy pecheni. Sudya po priobretennomu avtorami opytu, dannyj metod ves'ma maloehffektive n dlya opredeleniya nebol'shikh metastazov pecheni, kotorye ne izmenyayut ob{sup e}ma i Formy poslednej. Dazhe v sluchayakh podtverzhdennog o operatsiej nalichiya mnozhestva razbrosannykh melkikh uzelkov metastaticheskog o kharaktera issledovaniya ehtim metodom dali neyasnye rezul'taty. Ispol'zovanie radioaktivnog o zolota-198 mozhet v sluchayakh rasseyannogo ili zonal'nogo rasshireniya - nezavisimo ot prichiny - sposobstvovat' vyyasnesho, vyzvany li ehti izmeneniya rasshireniem normal'no funktsioniruyushche j tkani ili zhe nalichem v tkani pecheni patologicheski kh obrazovanij. Ochen' udalnym okazalos' sochetanie radioizotopnog o issledovaniya pecheni s issledovaniem ee konturov rentgenovskimi luchami posle provedeniya pnevmoperitoneuma, tak kak ono pozvolyaet provesti sravnenie mezhdu anatomicheskim i funktsional'ny m sostoyaniem dannogo organa. Kontury, poluchaemye na stsintigrammakh i na rentgenovskikh snimkakh, obychno sovpadayut, i obnaruzhenie znachitel'nykh raskhozhdenij mozhet okazat' pomoshch' pri opredelenii vozmozhnosti khirugicheskogo ili radiatsionnogo lecheniya zkoka-chestvennykh zabolevanij, osobenno zheludochno-kishechnog o trakta. Konechno, otritsatel'nyj rezul'tat ne isklyuchaet vozmozhnosti nalichiya metastazov v pecheni. Vosproizvodyats ya podlinnye stsintigrammy i sootvetstvuyushchi e rentgenovskie snimki; obsuzhdayutsya rezul'taty, predstavlyayushchi e naibol'shij interes. (author)

  7. Results of several years experiments on the absorption of radioactive strontium and caesium by cultivated plants (1962); Compte rendu d'experiences de plusieurs annees sur l'absorption du strontium et du cesium radioactifs par des plantes cultivees (1962)

    Energy Technology Data Exchange (ETDEWEB)

    Michon, M [Commissariat a l' Energie Atomique, Dept. de Protection Sanitaire, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires; Benard, M; Flanzy, M [Station Centrale de Technologie des Produits Vegetaux, 11 - Narbonne (France); Fioramonti, M; Marty, M [Station Agronomique de Toulouse, 31 (France); Barbier, M; Le Blaye, M; Brossard, M [Societe Centrale d' Agronomie, 78 - Versailles (France)

    1962-07-01

    This report follows on to the report number CEA 1860 and uses results obtained in 1960 to give more precise details concerning the data presented in the preceding report. First results obtained on the vine are given. The Sr absorption coefficient has varied very little from one year to the next and that of caesium has slightly diminished. The values obtained suggest that the concentrations of {sup 90}Sr and {sup 137}Cs in irrigation water should not exceed 1/5 of the maximum permissible concentration in drinking water. (authors) [French] Ce rapport fait suite au rapport CEA 1860 et precise grace aux resultats acquis en 1960 les donnees exprimees dans le precedent rapport. Il y est fait mention des premiers resultats obtenus pour la vigne. Le coefficient d'absorption du Sr a peu varie d'une annee sur l'autre et celui du cesium legerement diminue. Les valeurs obtenues permettent de penser qu'il serait souhaitable que la concentration en {sup 90}Sr et en {sup 137}Cs dans l'eau d'irrigation ne depasse pas le 1/5 de la concentration maxima admissible pour l'eau de boisson. (auteurs)

  8. Radioactive waste combustion / vitrification under arc plasma: thermal and dynamic modelling; Combustion - vitrification de dechets radioactifs par plasma d'arc: modelisation de la thermique et de la dynamique

    Energy Technology Data Exchange (ETDEWEB)

    Barthelemy, B

    2003-07-01

    This thesis concerns the thermal and dynamic modelling for a combustion/vitrification process of surrogate radioactive waste under transferred arc plasma. The writer presents the confinement processes for radioactive waste using arc plasma and the different software used to model theses processes. This is followed by a description of our experimental equipment including a plasma arc reactor and an inductive system allowing the homogenization of glass temperature. A combustion/vitrification test is described. Thermal and material balances were discussed. The temperature fields of plasma arc and the glass frit conductivity are measured. Finally, the writer describes and clarifies the equations solved for the simulations of the electrically plasma arc and the glass melting including the thin layer of glass frit coating the crucible cold walls. The modelling results are presented in the form of spatial distribution of temperature, velocity and volume power... (author)

  9. Radioactive waste packages stored at the Aube facility for low-intermediate activity wastes. A selective and controlled storage; Les colis de dechets radioactifs stockes au centre de stockage FMA de l'Aube. Une stockage selectif et maitrise

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    The waste package is the first barrier designed to protect the man and the environment from the radioactivity contained in wastes. Its design is thus particularly stringent and controlled. This brochure describes the different types of packages for low to intermediate activity wastes like those received and stored at the Aube facility, and also the system implemented by the ANDRA (the French national agency of radioactive wastes) and by waste producers to safely control each step of the design and fabrication of these packages. (J.S.)

  10. Radioactive waste combustion-vitrification under arc plasma: thermal and dynamic modelling; Combustion - vitrification de dechets radioactifs par plasma d'arc: modelisation de la thermique et de la dynamique

    Energy Technology Data Exchange (ETDEWEB)

    Barthelemy, B

    2003-06-01

    This thesis concerns the thermal and dynamic modelling for a combustion/vitrification process of surrogate radioactive waste under transferred arc plasma. The writer presents the confinement processes for radioactive waste using arc plasma and the different software used to model theses processes. This is followed by a description of our experimental equipment including a plasma arc reactor and an inductive system allowing the homogenization of glass temperature. A combustion/vitrification test is described. Thermal and material balances were discussed. The temperature fields of plasma arc and the glass frit conductivity are measured. Finally, the writer describes and clarifies the equations solved for the simulations of the electrically plasma arc and the glass melting including the thin layer of glass frit coating the crucible cold walls. The modelling results are presented in the form of spatial distribution of temperature, velocity and voluminal power... (author)

  11. Use of a thin-film evaporator for bitumen coating of radioactive concentrates; Utilisation d'un evaporateur a couche mince pour l'enrobage par le bitume de concentrats radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Lefillatre, G; Rodier, J; Hullo, R; Cudel, Y; Rodi, L [Commissariat a l' Energie Atomique, Chusclan (France). Centre de Production de Plutonium de Marcoule

    1969-07-01

    Following the development in the laboratory of a process for coating evaporation concentrates with bitumen, a technological study of this coating process has been undertaken. The report describes a pilot installation for the bitumen coating of concentrates, which uses a thin-film evaporator LUWA L 150. The first, inactive series of tests was designed to determine the maximum and optimum capacities of the evaporator by varying the amounts of bitumen and of concentrate, the rotor speed and the thermo-fluid temperature. Two rotors were tested, one of conventional type, the other a model especially designed for high viscosity products. The maximum capacity of evaporation of the apparatus is 72 kg/hr for a heating temperature of 221 deg. C. During normal operation, the evaporator can produce 50 kg/hr of coated product containing 55 to 60 per cent of bitumen (Mexphalte 40/50), the water content of the product remaining under 0.5 per cent. A second series of tests will shortly be carried out on this pilot installation using, in particular, bituminous emulsions containing mainly Mexphalte 40/50 and 80/100. (authors) [French] A la suite de la mise au point en laboratoire d'un procede d'enrobage par le bitume de concentrats d'evaporation, une etude technologique de cet enrobage a ete entreprise. Ce rapport decrit une installation pilote d'enrobage par le bitume de concentrats utilisant un evaporateur a couche mince LUWA L 150. La premiere serie d'essais en inactif a eu pour but de definir les capacites maximales et optimales de l'evaporateur en faisant varier les dosages en bitume et en concentrats, la vitesse du rotor et la temperature du thermo-fluide. Deux rotors ont ete testes, l'un de type classique, l'autre d'un modele special concu pour les produits de haute viscosite. La capacite d'evaporation maximale de l'appareil est de 72 kg/h d'eau pour une temperature de chauffage de 221 deg. C. En marche normale l'evaporateur peut debiter 50 kg/h d'enrobe compose de 55 a 60 pour cent de bitume (Mexphalte 40/50), la teneur en eau residuelle de l'enrobe restant inferieure a 0.5 pour cent. Une deuxieme serie d'essais sera prochainement realisee sur cette installation pilote avec notamment des emulsions bitumineuses a base de Mexphalte 40/50 et 80/100. (auteurs)

  12. Thierry De Putter, a geologist faced to the ''irrational'' fear of radioactive wastes; Thierry De Putter, un geologue face a la peur ''irrationnelle'' des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Putter, Th. de [Musee Royal de l' Afrique Centrale, Geologie Isotopique, Tervuren (Belgium); Pivot, A. [Paris-10 Univ., Sociologue, Ladyss/NSS, Maison Max Weber, 92 - Nanterre (France)

    2004-06-01

    The author analyses the origins of the irrational fear the public feels concerning the disposal of radioactive wastes in deep geological layers. This fear seems to be linked to the positive image of the earth that has been built for millenniums in all humane civilizations, according to it the earth appears as a universal, pure and prolific mother. The burial of radioactive wastes might be considered in an unconscious way as a direct and permanent threat to the integrity of the earth. In fact the earth is not so fragile, it has already undergone catastrophes worse than these that are looming like climate changing or extinction of species, but what is true is that humane civilizations settled on its surface are very fragile. Irrational fear might be an acute and unconscious awareness of this fragility. (A.C.)

  13. The reactivity of clay materials in a context of metallic corrosion: application to disposal of radioactive wastes in deep argillaceous formations; Reactivite des materiaux argileux dans un contexte de corrosion metallique: application au stockage des dechets radioactifs en site argileux

    Energy Technology Data Exchange (ETDEWEB)

    Perronnet, M

    2004-10-15

    In order to confine radioactive wastes in deep settings, it is envisaged to use some natural clay materials and bentonites. Their stability when in contact with metallic iron, main component of the canisters, is studied. These studies show that the reactivity of such materials is mainly controlled by those of their di-octahedral smectites and kaolinites. On the contrary, the presence of sulfides stops the Fe(0)-clays reaction. The kind of reaction products depends on the quantity of available metallic iron. When pH is over 7, the Fe(0) is oxidized consecutive to a physical contact with the oxidant agents of the smectite (H{sup +}, OH{sup -} et Fe{sup 3+}). This reaction is favored by the heterogeneities of the lateral surfaces of the smectite, which then describes a micro-environments in which some serpentines grow up if the iron supply is sufficient. Such new-crystallization imply a decrease of the confinement properties of the clay barrier. (author)

  14. Aspects of governance in the practical implementation of the concept of reversibility for deep geological disposal. Report no. 308; Stockage geologique de dechets radioactifs: mise en oeuvre pratique du concept de reversibilite et gouvernance. Rapport no. 308

    Energy Technology Data Exchange (ETDEWEB)

    Reaud, C.; Schieber, C.; Schneider, T.; Gadbois, S.; Heriard Dubreuil, G.

    2010-07-01

    The European project COWAM in Practice (CIP) was aimed to lead for three years (2007-2009) a process of monitoring, analyzing and evaluating the governance linked with radioactive waste management. This project, in cooperation with a research group and stakeholders, was conducted in parallel in 5 European countries (Spain, France, United Kingdom, Romania, Slovenia). In France, the issue of reversibility for a deep geological disposal was introduced in the Act of December 30, 1991 on the possible options to manage radioactive waste. The Act of June 28, 2006 relative to sustainable management of materials and radioactive waste confirmed the option, by calling for a reversible waste disposal facility in a deep geological formation to be designed. The main issue is no longer to justify the adoption of reversibility, but to investigate the practical procedures for its implementation. The French stakeholder Group 4 involved in the European project COWAM In Practice (CIP) had identified several subjects for investigation: - The different aspects associated with the practical implementation of reversible disposal: technical aspects, and aspects relative to monitoring, safety and expertise, in terms of legal, financial, administrative and political, etc. responsibility related to the notion of reversibility. - The stakes of governance related to the processes of assessment and decision-making - The roles of local stakeholders in these processes. The analysis conducted by CEPN in cooperation with the French stakeholder group, facilitated by Mutadis, showed that the practical implementation of reversibility aims to maintain a capacity of choice between three options: to continue to maintain the reversibility, to retrieve packages or to initiate the closure of all or part the disposal facility. Maintaining this choice in the long term implies setting up specific institutional, financial and decision-making systems,etc,. that need to be jointly developed in advance by all the actors concerned, be this at local, national and even international level. Thus, this study revealed perspectives for further study in various areas that could be developed by the different actors (institutions, associations, local actors,..). In particular, further investigations could be carried out in the following areas: - The political dimension and governance related to the practical implementation of the reversibility; - The technical aspects of monitoring the installation and its environment; - The financial aspects of the implementation of the reversibility concept. (authors)

  15. Law project on the radioactive materials and wastes management 2006 recommendations presented by Anne Duthilleul; Projet de loi sur la gestion des matieres et des dechets radioactifs 2006 avis presente par Mme Anne Duthilleul

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    This document provides recommendations on the law project concerning the radioactive material and wastes management. It precises the law objectives, the french particularities concerning the radioactive wastes and materials management, the public debate in France, the evaluation of the researches, the recommendations of the economic and social council. (A.L.B.)

  16. Report on the evaluation of the national plan on radioactive wastes and materials management; Rapport sur l'evaluation du plan national de gestion des matieres et des dechets radioactifs (PNG-MDR)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-02-15

    This document constitutes the evaluation of the first edition of the National Plan on radioactive wastes and materials management. It presents the definitive or temporary solutions for the radioactive wastes management, the national plan juridical framework defined by the laws of 1991 and 2006 and the first evaluation and perspectives. (A.L.B.)

  17. Transfer into the biosphere of radionuclides released from deep storage of radioactive wastes. Bibliographical study; Transfert dans la biosphere des radionucleides issus des stockages profonds de dechets radioactifs. Etude bibliographique

    Energy Technology Data Exchange (ETDEWEB)

    Guedon, V.; Siclet, F.

    1995-03-01

    Most countries with civilian nuclear programs today are encountering difficulty in implementing a nuclear waste management policy that is both technically safe in the long term and accepted by the public. To meet both criteria, the solution most generally envisaged is deep storage either of untreated spent nuclear fuel or of highly radioactive wastes resulting from reprocessing. In order to predict the potential impact of such storage on man, one needs to understand the path followed by radionuclides in the geosphere, and later in the biosphere. Given the time scales involved and the critical nature of the elements concerned, it is indispensable to turn to mathematical modeling of the phenomena. This report presents what is hoped to be a complete inventory of the radionuclides contained in ``high level`` wastes (categories B AND C). The elements concerned in studies on deep storage are essentially long-life radionuclides (both actinides and certain fission and activation products). Their physico-chemical characteristics and their behavior in various ecological compartments are examined. Bibliographical data bearing on: solubility (in an oxidizing, reducing medium), distribution factors (water/rock-sediment-soil), concentration and transfer factors (in aquatic and terrestrial mediums), dose conversion factors (in the case of internal and external irradiation), principal paths of exposure for each radionuclide studied, are presented in this report. Initial results from international projects to model what happens to radionuclides in the biosphere are also presented. In general, they are optimistic as to the future, but nonetheless point to a need to improve the conceptual base of the models, to ensure that all major phenomena and processes are taken into consideration and to examine any possible amplification (author). 67 refs., 39 figs., 20 tabs.

  18. Conference introductory keynote: Radioactive waste management and the future of nuclear energy; Elements essentiels de la conference: Gestion des dechets radioactifs et l'avenir de l'energie nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Waeterloos, Christian [Directorate General Energy and Transport, Nuclear Safety and Safeguards, European Commission, Rue de la Loi 200, 1049 Brussels (Belgium)

    2004-07-01

    Nuclear power contribution to the electricity consumption in the European Union amounts up to one third. Eight members states are nuclear electricity producers. These states make use of 143 nuclear plants. After extension of the Union 11 states will operate a total number of 163 nuclear reactors while the energy market could rest almost unchanged. On long term five members states declared a moratorium on new NPP construction while other states decided their nuclear reactors to be shut down at the end of their lifetime. A single state decided to construct a new reactor while others are hesitant. European Union's public opinion is not against nuclear power, on condition of safeguarding the nuclear installations, of non-proliferation of nuclear materials and of a secure and safe radioactive waste management. The speaker addresses the following topics: - The status of nuclear power; - The nuclear safety issue; - The directive 'Safety of nuclear installations'; - The directive 'Radioactive waste management'; - International cooperation. Summarizing, the author underlines as major target, the nuclear safety legislation proposals of The European Commission to ensure an extreme rigorous observance of nuclear protection throughout extended Union, in strict compliance with all international pertinent regulations. Application of this community legislation will enable European nuclear industry to evolve within a stable juridical frame. At the same time, by guaranteeing a sustainable high level nuclear safety the growth of a free and healthy concurrence in a deeply mutant electricity market will be enhanced. The debate on competence of the Community on nuclear safety matters was ceased as ordered by the EU Justice Court in December 2002. Indeed, the Court clearly uttered that Community has normative competence to be exerted. Hiding behind juridical arguments to avoid Union concern within a community frame in handling nuclear safety matters would be politically irresponsible, particularly in the current international context. Extended European Union should respond properly to this challenge as a whole and consequently the European Commission must take all the necessary measures to reach this goal. The radioactive waste management is an exemplary domain for implementing this programme.

  19. Numerical modeling of the thermomechanical behavior of networks of underground galleries for the storage of the radioactive waste: approach by homogenization; Modelisation numerique du comportement thermomecanique de reseaux de galeries souterraines pour le stockage des dechets radioactifs: Approche par homogeneisation

    Energy Technology Data Exchange (ETDEWEB)

    Zokimila, P

    2005-10-15

    Deep geological disposal is one of the privileged options for the storage of High Level radioactive waste. A good knowledge of the behavior and properties of the potential geological formations as well as theirs evolution in time under the effect of the stress change induced by a possible installation of storage is required. The geological formation host will be subjected to mechanical and thermal solicitations due respectively to the excavation of the disposal tunnels and the release of heat of the canisters of radioactive waste. These thermomechanical solicitations will generate a stress relief in the host layer and disposal tunnels deformations as well as the extension of the damaged zones (EDZ) could cause local and global instabilities. This work aims to develop calculation methods to optimize numerical modeling of the thermoelastic behavior of the disposal at a large scale and to evaluate thermomechanical disturbance induced by storage on the geological formation host. Accordingly, after a presentation of the state of knowledge on the thermomechanical aspects of the rocks related to deep storage, of numerical modeling 2D and 3D of the thermoelastic behavior of individual disposal tunnel and a network of tunnels were carried out by a discrete approach. However, this classical approach is penalizing to study the global behavior of disposal storage. To mitigate that, an approach of numerical modeling, based on homogenization of periodic structures, was proposed. Formulations as numerical procedures were worked out to calculate the effective thermoelastic behavior of an equivalent heterogeneous structure. The model, obtained by this method, was validated with existing methods of homogenization such as the self-consistent model, as well as the Hashin-Shtrikman bounds. The comparison between the effective thermoelastic behavior and current thermoelastic behavior of reference showed a good coherence of the results. For an application to deep geological storage, the effective thermoelastic properties of a network of circular tunnels could be given in 2D for various dimensions of the distance between galleries. (author)

  20. Development of radioiodinated ligands for exploration of brain monoamine oxidase by tomo-scintigraphy; Developpement de ligands radioactifs pour l'exploration des monoamines oxydases cerebrales en tomoscintigraphie

    Energy Technology Data Exchange (ETDEWEB)

    Rafii, H

    1996-07-01

    Monoamine oxidases, MAO, are important in the regulation of monoaminergic neuro-transmissions. The fluctuations in MAO activities has been observed in some psychiatric and neuro-degenerative diseases. Thus, quantification of cerebral MAO activity would be useful for diagnosis and the therapeutic follow-up of these disorders. With the object of doing an in vivo scintigraphic exploration of cerebral MAO by SPECT, we have undertaken to synthesize some radioiodinated MAO inhibitors. In the first part of this work, we have discussed the general properties of the monoamine oxidases and their inhibitors. In the second part we have described the scintigraphic methods. the ligands to be used for MAO exploration, and the radioiodination methods. At last in the third part, the development of three radioiodinated ligands has been presented: - [{sup 125}I]3-iodopargyline. In vivo results showed that, this radioligand blocked the cerebral MAO-B with moderate selectivity. However, complementary in vivo studies would be needed to define precisely its activity.- [{sup 125}I]Ro 16-6491. The cerebral fixation of this radioligand was in accordance with the MAO-B sites in the rat brains, but its fixation was too low for scintigraphic exploration in vivo with iodine-123. - [{sup 125}I]Ro 11-9900. In vivo studies of rat brains showed that the MAO-A sites were bound preferentially by this radioligand. The cerebral biodistribution of this ligand labelled with iodine-123 is considered for use in a model animal nearest to human pathology. (author)

  1. Contribution and limits of geochemical calculation codes to evaluate the long term behavior of nuclear waste glasses; Apports et limites des modeles geochimiques pour l'evaluation du comportement a long terme des verres de confinement des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Fritz, B; Crovisier, J L [Universite Louis Pasteur, Centre de Geochimie de la Surface, CNRS ULP, Ecole et Observatoire des Sciences de la Terre, 67 - Strasbourg (France)

    1997-07-01

    Geochemical models have been intensively developed by researchers since more than twenty five years in order to be able to better understand and/or predict the long term stability/instability of water-rock systems. These geochemical codes were ail built first on a thermodynamic approach deriving from the application of Mass Action Law. The resulting first generation of models allowed to detect or predict the possible mass transfers (thermodynamic models) between aqueous and mineral phases including irreversible dissolutions of primary minerals and/or precipitation near equilibrium of secondary mineral phases. The recent development of models based on combined thermodynamics and kinetics opens the field of Lime dependent reactions prediction. This is crucial if one thinks to combine geochemical and hydrological studies in the so-called coupled models for transport and reaction calculations. All these models are progressively applied to the prediction of long term behavior of mineral phases, and more specifically glasses. In order to succeed in chat specific extension of the models, but also the data bases, there is a great need for additional new data from experimental approaches and from natural analogues. The modelling approach appears than also very useful in order to interpret the results of experimental data and to relate them to long term data extracted from natural analogues. Specific functions for modelling solid solution phases mat' also be used for describing the products of glasses alterations. (authors)

  2. Economic Management of a Centre for Processing Radioactive Residues; Gestion Economique D'un Centre de Traitement de Residus Radioactifs; Ehkonomicheskij aspekt obrashcheniya s radioaktivnymi otkhodami v obrabatyvayushchem tsentre; Gestion Economica de un Centro de Tratamiento de Desechos Radiactivos

    Energy Technology Data Exchange (ETDEWEB)

    Van Lint, J. M. [BELGONUCLEAIRE, Bruxelles (Belgium)

    1966-02-15

    The paper shows the differences between the operations of an industrial undertaking and an installation for residue processing and describes the auditing system of an industry concerned with various phases of processing. It shows that the auditing programme is necessarily and intimately connected with the general organization of the entire undertaking and that it is a useful tool of economic management. In this connection, the paper deals at length with the auditing principles used in arriving at - the overall cost of the final product, - the specific cost of each processing phase,. (author) [French] Apres avoir expose les differences existant entre les operations effectuees par une entreprise industrielle et par une installation de traitement des residus, le memoire decrit la comptabilite d'une industrie comprenant plusieurs phases de traitement. Il montre comment le plan comptable est necessairement et intimement lie a l'organisation generale de l'ensemble de l'entreprise et est un outil utile de gestion economique, A cette fin, le memoire developpe les principes comptables permettant d'etablir: - le prix de revient global du produit final obtenu, - les prix de revient specifiques de chaque phase de traitement partiel. (author) [Spanish] Despues de exponer las diferencias que existen entre las operaciones efectuadas en una empresa industrial y en una instalacion de tratamiento de desechos, el autor analiza la contabilidad de una industria que comprende diversas fases de tratamiento. Muestra como el plan contable esta necesaria e intimamente vinculado a la organizacion general del conjunto de la empresa y es un instrumento util de gestion economica. Con este fin, desarrolla los principios contables que permiten establecer: - el precio de costo global del producto final obtenido, - los precios de costo especificos de cada fase de tratamiento parcial. (author) [Russian] Posle Izlozhenija Razlichij, Sushhestvujushhih Mezhdu Operacijami Na Promyshlennom Predprijatii I Na Ustanovke Po Obrabotke Othodov, V Issledovanii Privodjatsja Dannye Ob Otchetnosti Na Promyshlennom Predprijatii S Neskol'Kimi Fazami Obrabotki. Pokazyvaetsja, Naskol'Ko Plan Otchetnosti Neobhodim I Tesno Svjazan S Obshhej Organizaciej Vsego Predprijatija, A Takzhe Javljaetsja Poleznym Dlja Jekonomicheskogo Upravlenija. V Jetoj Svjazi Razrabatyvajutsja Principy Otchetnosti, Pozvoljajushhie Ustanovit': Obshuju Sebestoimost' Poluchennoj Gotovoj Produkcii; Udel'Nye Sebestoimosti Kazhdoj Fazy Chastichnoj Obrabotki. (author)

  3. Proceedings of the workshop on siting of radioactive waste repositories in geological formations. Compte rendu d'une reunion de travail sur le choix des sites des depots de dechets radioactifs dans les formations geologiques

    Energy Technology Data Exchange (ETDEWEB)

    1981-01-01

    The objectives of this workshop were: to review the approaches used in NEA Member countries for the siting of repositories; to consider what information is required to determine whether a particular location is suitable as a disposal site; to review the technical means that can be used to obtain the necessary information; to discuss possible approaches for effectively communicating to the public the results of the site characterisation process. The papers and discussions at the meeting are recorded in these proceedings which provide a synthesis of the present thinking in this field.

  4. Conceptual study for the final underground disposal of radioactive wastes with short-lived or limited toxicity. Etude conceptuelle pour le stockage souterrain definitif de dechets radioactifs dont la toxicite est de courte duree ou restreinte

    Energy Technology Data Exchange (ETDEWEB)

    1980-08-01

    The project of a repository is a part of an iterative optimization process of the safety of disposal. It contains the specifications of the wastes admitted to the repository and the safety analyses of the repository containing the wastes. In a general way, the study has refined the idea of type A repositories as defined in the 1978 concept of NAGRA and has shown possibilities for realization. It could be shown that the realistic geologic conditions that have been considered will not hinder the construction of the repository. It has proved that the realization and maintenance of a reliable artificial barrier for 100 years is technically realizable. Technological alternatives are available to overcome the difficulties which will be met. The radiation protection of the working personnel will be assured through adequate conception of the installations and careful planning of the operations. The work and the equipment can be conceived without major difficulties in order that the risk incurred relative to various accidents is reduced to an acceptable level.

  5. Order of the 10 january 2003 authorizing the national agency for the radioactive wastes management to follow the gaseous and liquid effluents release for the exploitation of the radioactive wastes storage center of the Manche; Arrete du 10 janvier 2003 autorisant l'Agence nationale pour la gestion des dechets radioactifs a poursuivre les rejets d'effluents gazeux et liquides pour l'exploitation du centre de stockage de dechets radioactifs de la Manche

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-01-01

    This document, took out from the Official Journal, is the law text relative to the order of the 10 january 2003 authorizing the national agency for the radioactive wastes management to follow the gaseous and liquid effluents release for the exploitation of the radioactive wastes storage center of the Manche. (A.L.B.)

  6. Sr{sup 90} determination in calcareous water; Determination du {sup 90}Sr dans des eaux chargees en calcium

    Energy Technology Data Exchange (ETDEWEB)

    Cohen, P; Pardo, G; Wormser, G [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    The Straub method (ref. 2) for determination of radioactive strontium in water containing calcium is valid within very wide limits, and particularly in the case of residual water from the chemical purification treatment of the radioactive liquid effluent at the C.E.N. Saclay. (author) [French] La methode de Straub (ref. 2) de determination du strontium radioactif dans une eau chargee en calcium est valable dans des limites tres larges et en particulier dans le cas d'eaux residuaires provenant du traitement d'epuration chimique des effluents liquides radioactifs du C.E.N. de Saclay. (auteur)

  7. Note from the radioprotection group's shipping service

    CERN Multimedia

    2006-01-01

    Le service SHIPPING du groupe de radioprotection souhaite vous rappeler qu'avant toute expédition de matériel susceptible d'être radioactif, une demande de transport doit être établie par EDH en cochant la case appropriée (danger radioactif). Merci de bien vouloir prendre note des informations figurant dans le site Web: http://cern.ch/service-rp-shipping Toute demande non conforme ne sera pas prise en compte. Radioactive Shipping Service http://cern.ch/service-rp-shippingTél: 73171Fax: 69200

  8. Submission of the national commission of the public debate on the options concerning the long life high and medium activity radioactive wastes management; Saisine de la commission nationale du debat public sur les options generales en matiere de gestion des dechets radioactifs de haute activite et de moyenne activite a vie longue

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    This document deals with the presentation of a public debate on the radioactive wastes management and the opportunities of its organization. It presents successively the long life high and medium activity radioactive wastes, the today radioactive wastes management policy and some questions and topics which could be discussed during the debate. (A.L.B.)

  9. Renewal of release and sampling authorizations of the Cattenom nuclear power plant. Complementary note on the authorizations demands of radioactive release; Renouvellement des autorisations de rejets et de prelevements de la centrale nucleaire de Cattenom. Note complementaire sur les demandes d'autorisation de rejets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Marignac, Y.; Coeytaux, X

    2003-10-15

    The present note follows the exchanges with the contracting authority, the Cattenom nuclear power plant, during the public hearing stood on the 10. of october 2003 at Cattenom. In the frame of the evaluation of the inquiry file by WISE -Paris, this note constitutes a deepening on the question of authorization demands for the radioactive releases. The elements supplied by E.D.F in the file submitted to the inquiry, and the presentation of these demands and the information complements brought during the meeting of the 10. of october, raise different problems of evaluation and justification relative to the evolution of radioactive release of Cattenom. The note analyses in particular, the increasing of dosimetry impact expected from the progression of real release forecasted by the operator, and the weight linked to the feedback of clad failure problem. It discusses the justification brought by E.D.F. to the standing and even the increasing of liquid tritium release instead of the expected reduction, facing the arguments of the operator to the experience feedback on the park and to the uncertainties on the future progress. (N.C.)

  10. Design of an equipment for the testing of target dedicated to the production of radioactive ions through the ISOL method; Realisation d'un dispositif de test de cibles pour la production d'ions radioactifs par la methode ISOL

    Energy Technology Data Exchange (ETDEWEB)

    Durantel, F

    2005-01-15

    In the ISOL (isotope separation on line) technique, a primary ion beam impinges on a thick target, the incident ions are stopped through fragmentation reactions that generate radioactive nuclei. As soon as they have collected enough electrons, the radioactive nuclei begin diffusing outside the target as radioactive atoms. In order to improve this diffusion the target is strongly heated. The radioactive atoms diffuse till a ion source that ionize them, they are then accelerated to form a secondary beam that is delivered to the experimental area. This work deals with the design of an equipment able to measure the diffusion capacities of various targets, it is made up of -) a high temperature (> 2300 K) oven that will contain the target, -) a ionization source for ionizing radioactive atoms and -) a target dispatcher able to introduce in the oven or remove from the oven any target of a set of 12 targets. This equipment has proved to be able to test during a single experiment several primary beams and target materials. Measurements will be performed in a sequential way for the different projectile-target couples which will assure very closed experimental conditions for each measuring campaign. (A.C.)

  11. 2002 summary of the report on studies and activities. Research on the Disposal of High-level Long-lived Radioactive Wastes; 2002 synthese du bilan des etudes et travaux. Recherches pour le stockage des dechets radioactifs haute activite et a vie longue

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-01-01

    This synthesis presents the studies underway and the major results obtained in the framework of the second research area prescribed by the Law of 1991 (the feasibility study of a deep geological repository). It also clarifies the French and international contexts of that research, namely with regard to the development of scientific partnerships. Content: 1 - scientific knowledge gained in 2002: packages, materials evolution, works about the clayey environment, works about the granitic environment, modeling approach; 2 - the 2002 granite dossier: context and goals, content; 3 - the 2002 concept choices for the clayey environment: overall architecture, packages and storage cells for B-type wastes, packages and storage cells for C-type vitrified wastes, packages and storage cells for spent fuels; 4 - international context: IAEA, OECD/NEA, integrated group for the safety case (IGSC), forum for stakeholders confidence (FSC), working party on decommissioning and dismantling (WPDD), general direction of energy transport, general direction of research, status of partnerships and bilateral agreements, advance of research cooperations, European Union; 5 - ANDRA's participations to international meetings; 6 - scientific partnerships: Ecole des Mines, BRGM, GdR FORPRO, MoMas, CEA, IFP, PRACTIS, PARIS, 7 - information and evaluation: national commission of evaluation (CNE), scientific committee, permanent group, orientation and follow-up committee; 8 - ANDRA's theses; 9 - ANDRA's publications. (J.S.)

  12. Updated synthesis of the knowledge about the impact on marine environment of the radioactive releases from Fukushima Dai-ichi damaged site - October 26, 2011; Synthese actualisee des connaissances relatives a l'impact sur le milieu marin des rejets radioactifs du site nucleaire accidente de Fukushima Dai-ichi - 26 octobre 2011

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-10-26

    A strong radioactive contamination of the marine environment close to the damaged Fukushima Dai-ichi power plant has been observed since March 21. The high concentration of some nuclides ({sup 131}I, {sup 137}Cs, {sup 134}Cs, {sup 136}Cs, {sup 132}Te, {sup 132}I) comes from three possible sources: the liquid effluents from the damaged site, the atmospheric fallouts, and the weathering of contaminated soils. This information note presents and comments the most recent informations gathered by the French institute of radiation protection and nuclear safety (IRSN) since the previous information note from July 11 and devoted to the same topic. It presents the estimation of the relative contribution of each contamination source and the evolution with time of the marine contamination. The mapping of {sup 137}Cs concentrations in surface seawater allows to estimate the amount of total {sup 137}Cs in the marine environment and its evolution with time. {sup 137}Cs and {sup 134}Cs concentrations were measured both in samples of surface coastal sediments and in river fishes and seafood products (mainly fishes and molluscs). Results are reported in graphs showing their evolution with time. (J.S.)

  13. Study of deuterons induced nuclear reactions on light elements (N, Al and Si): Application to containment materials of radioactive wastes; Etude des reactions nucleaires induites par des deuterons sur des elements legers (N, Al, Si): application aux materiaux de confinement des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Pellegrino, St

    2004-03-01

    Nuclear reaction analysis is well adapted to the quantification of light element. Profiles of concentration in order to follow elements migration into materials can be undertaken. This technique is used to study the behavior of the future matrices for nuclear waste containment. This technique is isotopic, characterized by a good signal-to-background ratio and a very low detection limit. The probability of a nuclear reaction is linked to a parameter called 'cross section' we have to know in order to carry out quantitative analysis. We have determined excitation curves for nitrogen, aluminium and silicon. These experiments were done with deuterons from 0.5 to 2 MeV. Two methods for the cross section characterization are presented and are in agreement with each other. The second one reduces uncertainty. Data are incorporated in the simulation software SIMNRA. We have compared the results obtained on different samples when we use data in literature or data of the study. We have noticed a great fit improvement with the data of this study. The new cross sections of this work will be integrated in the general data base SIGMABASE. Applications on materials such as Si{sub 3}N{sub 4}, nano-metric powders, WCN and nuclear glass YLaMgSiAlON studied for radioactive waste containment are also presented. (author)

  14. Simultaneous photon and neutron interrogation using an electron accelerator in order to quantify actinides in encapsulated radioactive wastes; Double interrogation simultanee neutrons et photons utilisant un accelerateur d'electrons pour la caracterisation separee des actinides dans les dechets radioactifs enrobes

    Energy Technology Data Exchange (ETDEWEB)

    Jallu, F

    1999-09-24

    Measuring out alpha emitters, such as ({sup 234,235,236,238}U {sup 238,239,240,242,}2{sup 44P}u, {sup 237}Np {sup 241,243}Am...), in solid radioactive waste, allows us to quantify the alpha activity in a drum and then to classify it. The SIMPHONIE (SIMultaneous PHOton and Neutron Interrogation Experiment) method, developed in this Ph.D. work, combines both the Active Neutron Interrogation and the Induced Photofission Interrogation techniques simultaneously. Its purpose is to quantify in only one measurement, fissile ({sup 235}U, {sup 239,241}Pu...) and fertile ({sup 236,238}U, {sup 238,240}Pu...) elements separately. In the first chapter of this Ph.D. report, we present the principle of the Radioactive Waste Management in France. The second chapter deals with the physical properties of neutron fission and of photofission. These two nuclear reactions are the basis of the SIMPHONIE method. Moreover, one of our purposes was to develop the ELEPHANT (ELEctron PHoton And Neutron Transport) code in view to simulate the electron, photon and neutron transport, including the ({gamma}, n), ({gamma}, 2n) and ({gamma}, f) photonuclear reactions that are not taken into account in the MCNP4 (Monte Carlo N-Particle) code. The simulation codes developed and used in this work are detailed in the third chapter. Finally, the fourth chapter gives the experimental results of SIMPHONIE obtained by using the DGA/ETCA electron linear accelerators located at Arcueil, France. Fissile ({sup 235}U, {sup 239}Pu) and fertile ({sup 238}U) samples were studied. Furthermore, comparisons between experimental results and calculated data of photoneutron production in tungsten, copper, praseodymium and beryllium by using an electron LINear Accelerator (LINAC) are given. This allows us to evaluate the validity degree of the ELEPHANT code, and finally the feasibility of the SIMPHONIE method. (author)

  15. Presentation of the policy bill of program on the radioactive materials and wastes management by Francois Loos, Ministry delegate to the Industry, National Assembly; Presentation du projet de loi de programme sur la gestion des matieres et dechets radioactifs par Francois Loos, ministre delegue a l'Industrie, Assemblee Nationale

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-04-15

    This document provides the text of the presentation of Francois Loos. The bill institutes a national radioactive materials and waste management plan and defines a programme and calendar for research and work leading to implementation of this plan, which will comprise three major points: with a view to looking to reduce the quantity of waste, spent nuclear fuels taken from the nuclear power plants will be reprocessed for recycling in the plants; waste which cannot be recycled will be packaged in a robust matrix and then temporarily stored on the surface; after interim storage, waste which cannot be finally disposed of in a surface facility, will be placed in a deep geological reversible repository. In order to monitor each step in this plan, the bill strengthens independent assessment of research and involves greater information of the public. With regard to financing, the bill clarifies the fact that economic development of the departments concerned by research into disposal options and the research itself will be financed by additional taxes on the operators of nuclear installations. (A.L.B.)

  16. Production of fast neutrons from deuteron beams in view of producing radioactive heavy ions beams; Etude de la production de neutrons rapides a partir de faisceaux de deutons en vue de la mise en oeuvre de faisceaux d'ions lourds radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Pauwels, N

    2000-11-01

    This thesis is part of two research and development programmes for the study of neutron rich radioactive nuclear beam production. The technique is based on the ISOL method and can be summarized as follows. Fast neutrons are generated by the break-up of deuterons in a thick target. These neutrons irradiate a fissionable {sup 238}U target. The resulting fission products are extracted from the target, ionised, mass selected and post-accelerated. The aim of the thesis is to study the neutron angular and energetic distributions. After a bibliographical research to justify the choice of deuterons as the best projectile, we developed more specifically three points: - the extension of the activation detector method for neutron spectroscopy to a wide energy range (1 to 150 MeV), - the experimental measurement of neutron angular and energetic distributions produced by deuterons on thick targets. The deuteron energy ranges from 17 to 200 MeV and the thick targets were Be, C and U, - the realization of a code based on Serber's theory to predict the neutron distribution for any couple (deuteron energy-thick target). We conclude that for our application the most suitable target is C and the best deuteron energy is about 100 MeV. (author)

  17. Contribution to the study of maximum levels for liquid radioactive waste disposal into continental and sea water. Treatment of some typical samples; Contribution a l'etude des niveaux limites relatifs a des rejets d'effluents radioactifs liquides dans les eaux continentales et oceaniques. Traitement de quelques exemples types

    Energy Technology Data Exchange (ETDEWEB)

    Bittel, R; Mancel, J [Commissariat a l' Energie Atomique, 92 - Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires, departement de la protection sanitaire

    1968-10-01

    The most important carriers of radioactive contamination of man are the whole of foodstuffs and not only ingested water or inhaled air. That is the reason why, in accordance with the spirit of the recent recommendations of the ICRP, it is proposed to substitute the idea of maximum levels of contamination of water to the MPC. In the case of aquatic food chains (aquatic organisms and irrigated foodstuffs), the knowledge of the ingested quantities and of the concentration factors food/water permit to determinate these maximum levels, or to find out a linear relation between the maximum levels in the case of two primary carriers of contamination (continental and sea waters). The notion of critical food-consumption, critical radioelements and formula of waste disposal are considered in the same way, taking care to attach the greatest possible importance to local situations. (authors) [French] Les vecteurs essentiels de la contamination radioactive de l'homme sont les aliments dans leur ensemble, et non seulement l'eau ingeree ou l'air inhale. C'est pourquoi, en accord avec l'esprit des recentes recommandations de la C.I.P.R., il est propose de substituer aux CMA la notion de niveaux limites de contamination des eaux. Dans le cas des chaines alimentaires aquatiques (organismes aquatiques et aliments irrigues), la connaissance des quantites ingerees et celle des facteurs de concentration aliments/eau permettent de determiner ces niveaux limites dans le cas de deux vecteurs primaires de contamination (eaux continentales et eaux oceaniques). Les notions de regime alimentaire critique, de radioelement critique et de formule de rejets sont envisagees, dans le meme esprit, avec le souci de tenir compte le plus possible des situations locales. (auteurs)

  18. Law project adopted by the National Assembly, after urgency declaration, of the program relative to the sustainable management of radioactive materials and wastes; Projet de loi adopte par l'Assemblee Nationale, apres declaration d'urgence, de programme relatif a la gestion durable des matieres et des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    The document presents the different articles of the law project dealing with the terminology, the radioactive wastes storage and disposal, the safety and the transport, the financing, the liabilities, the control and the sanctions. (A.L.B.)

  19. Control of radioactive wastes and coupling of neutron/gamma measurements: use of radiative capture for the correction of matrix effects that penalize the fissile mass measurement by active neutron interrogation; Controle des dechets radioactifs et couplage de mesures neutron/gamma: exploitation de la capture radiative pour corriger les effets de matrice penalisant la mesure de la masse fissile par interrogation neutronique active

    Energy Technology Data Exchange (ETDEWEB)

    Loche, F

    2006-10-15

    In the framework of radioactive waste drums control, difficulties arise in the nondestructive measurement of fissile mass ({sup 235}U, {sup 239}Pu..) by Active Neutron Interrogation (ANI), when dealing with matrices containing materials (Cl, H...) influencing the neutron flux. The idea is to use the neutron capture reaction (n,{gamma}) to determine the matrix composition to adjust the ANI calibration coefficient value. This study, dealing with 118 litres, homogeneous drums of density less than 0,4 and composed of chlorinated and/or hydrogenated materials, leads to build abacus linking the {gamma} ray peak areas to the ANI calibration coefficient. Validation assays of these abacus show a very good agreement between the corrected and true fissile masses for hydrogenated matrices (max. relative standard deviation: 23 %) and quite good for chlorinated and hydrogenated matrices (58 %). The developed correction method improves the measured values. It may be extended to 0,45 density, heterogeneous drums. (author)

  20. The Origin and Nature of Radioactive Wastes in the United States Atomic Energy Programme; Origine et Nature des Dechets Radioactifs de l'Execution des Programmes d'Energie Atomique aux Etats-Unis; 041f 0420 041e 0418 0421 0425 041e 0416 0414 ; Origen y Naturaleza de los Desechos Radiactivos en el Programa de Energia Atomica de los Estados Unidos

    Energy Technology Data Exchange (ETDEWEB)

    Bruce, F. R. [Oak Ridge National Laboratory, Oak Ridge, TN (United States)

    1960-07-01

    The composition of nuclear power wastes is determined, firstly, by the treatment employed for fuel reprocessing, and secondly, by the initial fuel composition. In solvent-extraction processing, wastes of high, intermediate and low activity are produced in approximate volumetric ratios of one, five and 100, respectively. The wastes resulting from reprocessing of highly enriched fuels are large in volume because they contain the fuel diluent. Low-enrichment fuels usually consist of a uranium core clad with aluminium, zirconium or stainless steel, and they produce two waste streams: one, an intermediate-activity waste containing about 0.1% of the fission products, results from the chemical dissolution ; the other is a high-activity waste containing the remainder of the fission products in a dilute nitric acid solution. The volume of evaporated waste varies from 0.8 1/kg of uranium for low- enrichment fuels to 500 1/kg of uranium for highly-enriched fuels. The average volume of combined high- and intermediate-level waste from the anticipated United States nuclear power industry is about five 1/kg of uranium. In the United States it is estimated that the nuclear power industry will have produced about 3,000 million curies of radioactivity in 27 million litres of solution by 1970, and 60,000 million curies in 1,100 million litres of solution by 2000. Power reactor, wastes present new storage and disposal problems because of their composition. (author) [French] La composition des dechets nucleaires est determinee, d'abord, par le procede employe pour le traitement du combustible et, ensuite, par la composition du combustible lui-meme. Le procede de l'extraction par solvants produit des dechets ayant une activite elevee, moyenne ou faible dans des proportions volumetriques d'environ 1,5 et 100 respectivement. Les dechets provenant du traitement des combustibles fortement enrichis, representent un volume important parce qu'ils contiennent le diluant du combustible. Les cartouches de combustible faiblement enrichi consistent ordinairement en un element d'uranium gaine d'aluminium, de zirconium ou d'acier inoxydable et donnent lieu a deux sortes de dechets. Les uns sont des dechets a activite moyenne contenant environ 0,1% de produits de fission et proviennent de la dissolution chimique. Les autres sont des dechets a activite elevee contenant tous les autres produits de fission dans une solution d'acide nitrique etendue. Le volume des dechets condenses varie de 0,8 litre par kilogramme d'uranium pour les combustibles peu enrichis a 500 litres par kilogramme d'uranium pour les combustibles fortement enrichis, le volume de l'ensemble des dechets d'intensite elevee et intermediaire qui, a ce que l'on prevoit, proviendront des centrales nucleaires aux Etats-Unis. est d'environ 5 litres par kilogramme d'uranium en moyenne. Aux Etats-Unis, on estime qu'en 1970, les centrales nucleaires auront produit environ 3 milliards de curies contenues dans 27 millions de litres de solution, et en l'an 2000, 60 milliards de curies contenues dans 1,1 milliard de litres de solution. En raison de leur composition, les dechets provenant des reacteurs de puissance posent des problemes nouveaux d'entreposage et d'elimination. (author) [Spanish] La composicion de los desechos que se forman como consecuencia de la produccion de energia nucleoelectrica depende en primer lugar del tratamiento empleado en la regeneracion del combustible y, en segundo, de la composicion inicial de este. Por cada unidad de volumen de desechos de actividad elevada, obtenidos en la extraccion mediante disolventes, se forman 5 y 100 volumenes, respectivamente, de desechos de actividad media y baja. Los desechos que se producen en la regeneracion de los combustibles muy enriquecidos son muy voluminosos por contener el diluente del combustible. Los combustibles poco enriquecidos consisten habitualmente en un nucleo de uranio revestido de aluminio, zirconio o acero inoxidable, y producen dos clases de desechos: desechos de actividad media, que resultan de la disolucion quimica, y contienen el 0,1 per ciento, aproximadamente, del total de los productos de fision, y desechos de actividad elevada, que contienen el resto de los productos de fision en una solucion diluida de acido nitrico. El volumen de los desechos evaporados varia entre 0,8 1 per kilogramo de uranio, para los combustibles poco enriquecidos y 500 1 por kilogramo de uranio, para los muy enriquecidos, se prove que la industria nuecleoelectrica de los Estados Unidos producira como termino medio unos 5 1 de desechos de actividad elevada y media por kilogramo de uranio utilizado. En los Estados Unidos se calcula que para 1970 esta industria habra producido unos 3 x 10{sup 9} curies disueltos en un volumen de 2,7 x 10{sup 7} l y 6 x 10{sup 10} curies en 1,1 x 10{sup 9} l de solucion para el ano 2000. Los desechos procedentes de los reactores generadores plantean, por razon de su composicion, nuevos problemas de almacenamiento y evacuacion. (author) [Russian] Sostav othodov, obrazuemyh pri jekspluatacii reaktorov, zavisit, vo-pervyh, ot obrabotki, kotoraja primenjaetsja pri vosproizvodstve toplivnyh jelementov, i, vo-vtoryh, ot pervonachal'nogo sostava toplivnyh jelementov. Pri obrabotki s primeneniem jekstrakcii vodnyh rastvorov vysokaja, srednjaja i nizkaja aktivnost' othodov voznikaet v priblizitel'nom ob'emnom sootnoshenii, ravnom odnomu, pjati i 100 sootvetstvenno. Othody, voznikajushhie v rezul'tate vosproizvodstva vysokoobogashhennyh toplivnyh jelementov, byvajut bol'shimi po ob{sup e}mu, tak kak oni soderzhat toplivnyj razbavitel'. Nizkoobogashhennye toplivnye jelementy obychno sostojat iz uranovoj serdceviny, pokrytoj aljuminiem, cirkoniem ili nerzhavejushhej stal'ju ; jeti jelementy dajut dva vida othodov. Pervye othody srednej stepeni aktivnosti, soderzhashhie okolo 0,1% produktov raspada, voznikajut v rezul'tate himicheskogo rastvorenija. Vtoroj vid othodov s vysokoj stepen'ju aktivnosti, soderzhit ostatki produktov raspada v razvedennom rastvore azotnoj kisloty. Ob'em isparjajushhihsja othodov kolebletsja ot 0,8 litrov na kilogramm urana dlja nizkoobogashhenshdh toplivnyh jelementov do 500 litrov na kilogramm urana dlja vysokoobogashhennyh toplivnyh jelementov, srednij ob{sup e}m soedinennyh vmeste othodov vysokoj i srednej stepeni aktivnosti ot jadernoj jenergeticheskoj promyshlennosti Soedinennyh Shtatov sostavljaet okolo pjati litrov na kilogramm urana. Po sushhestvujushhim ocenkam jadernaja jenergeticheskaja promyshlennost' v Soedinennyh Shtatah budet proizvodit' okolo 3 mlrd. kjuri radioaktivnosti v 27 mln. litrah rastvora k 1970 godu i 60 mlrd. kjuri v 1,1 mlrd. litrah rastvora k 2000 godu. (author)

  1. Study of pentane and cyclopentane radiolysis with the aid of radioactive iodine; Etude de la radiolyse du pentane et du cyclopentane a l'aide d'iode radioactif; Issledovanie radioliza pentana i tsiklopentana s pomoshch'yu radioaktivnogo joda; Estudio de la radiolisis del pentano y del ciclopentano con ayuda de yodo radiactivo

    Energy Technology Data Exchange (ETDEWEB)

    Dauphin, J [Laboratoire de Chimie-Physique, Faculte des Sciences de Paris (France)

    1962-03-15

    Irradiation of hydrocarbons by ionizing radiation such as Co{sup 60} gamma-rays produces, inter alia, free radicals. Analysis of these radicals may lead to at least a partial explanation of the phenomena occurring. For analysis, the ''isotopic dilution'' method is used: the iodine used for taking up the radicals is labelled with iodine-131, resulting in a whole series of labelled iodides when the reaction is completed. Separation is affected by means of distillation on a microcolumn after inactive carriers have been added and the mineral iodine has been extracted. The activity of each fraction is measured directly it leaves the column. A control is used to obtain absolute G values from the counting. Precautions are taken to prevent isotopic exchange during separation. This method has been applied to cyclopentane and n-pentane and has yielded a detailed radiolysis spectrum. (author) [French] Les hydrocarbures irradies par des rayonnements ionisants tels que les {gamma} du cobalt-60 produisent entre autres entites des radicaux libres, dont l'analyse peut amener a decouvrir une explication au moins partielle des phenomenes. Pour effectuer cette analyse, on utilise la technique de la : l'iode servant de capteur est marque par de l'iode-131, ce qui a pour resultat de donner toute une serie d'iodures marques en fin de reaction. La separation se fait par distillation sur une microcolonne, apres addition d'entraineurs inactifs et extraction de l'iode mineral. L'activite de chaque fraction est mesuree directement a la sortie de la colonne. Un temoin permet l'obtention de valeurs absolues de G a partir des comptages. Des precautions sont prises pour eviter l'echange isotopique en cours de separation. Appliquee au cyclopentane et au n-pentane, cette methode a permis d'obtenir un spectre detaille de radiolyse. (author) [Spanish] La exposicion de los hidrocarburos a la accion de radiaciones ionizantes tales como los rayos gamma del {sup 60}Co da lugar a la formacion de radicales libres. Es posible que el analisis de estos radicales permite explicar, por lo menos parcialmente, los fenomenos observados. El autor efectua el analisis por : el yodo empleado como receptor se marca con yodo-131, por lo que al final de la reaccion se obtiene toda una serie de yoduros marcados. Lleva a cabo la separacion por destilacion en una microcolumna despues de haber anadido portadores inactivos y extraido el yodo inorganico. La actividad de cada fraccion se mide directamente a la salida de la columna. Los valores absolutos del coeficiente G se determinan por recuento de la actividad de una muestra testigo. El autor adopta las precauciones necesarias para evitar el intercambio isotopico durante la separacion. El metodo se aplico al ciclopentano y al n-pentano, habiendose obtenido un espectro de radiolisis detallado. (author) [Russian] Uglevodorody, obluchennye ioniziruyushchimi luchami, takimi, kak gamma-luchi kobal'ta-60, sredi drugikh veshchestv dayut svobodnye radikaly. Analiz ehtikh radikalov mozhet privesti k chastichnomu ob{sup y}asneniyu yavlenij. CHtoby osushchestvit' ehtot analiz, primenyayut metod ''izotopnogo razbavleniya'': jod, sluzhashchij ulovitelem, metyat jodom-131, chto privodit k tomu, chto v kontse reaktsii poluchaetsya tselaya seriya mechenykh jodidov. Razdelenie osushchestvlyaetsya peregonkoj na mikrokolonnom apparate posle dobavleniya neaktivnykh nositelej i izvlecheniya svobodnogo joda. Aktivnost' kazhdoj fraktsii izmeryaetsya pryamo posle vykhoda iz kolonki. Znak daet vozmozhnost' poluchit' absolyutnye znacheniya G ot nachala scheta. Byli prinyaty mery predostorozhnosti, chtoby izbezhat' izotopnogo obmena vo vremya razdeleniya. EHtot metod primenyalsya k tsiklopentanu i k p-pentanu i pozvolil poluchit' podrobnyj spektr radioliza. (author)

  2. Voltametric study of formic and dihydroxy malonic acids on platinum for the definition of a process for the electrolytic destruction of carboxylic acids in radioactive aqueous effluents; Etude voltamperometrique des acides formiques et dihydroxymalonique sur platine en vue de la definition d`un procede de destruction electrolytique d`acides carboxyliques d`effluents aqueux radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Le Naour, C.

    1994-05-01

    To limit the amount of nuclear glasses generated by the treatment of the degraded solvent from the PUREX process for reprocessing of nuclear fuels, by solutions of sodium carbonate and caustic soda, it is planned to exploit the complexing power of certain carboxylic acids to return the metallic cations to the aqueous phase. The concept of this new treatment of the solvent by `substitution` reagents demands a process for the decomposition of these reagents, especially to CO{sub 2}. The investigation of the electrochemical behaviour, on platinum, of a substance selected as a model for understanding the interfacial mechanisms (HCOOH), and of dihydroxy malonic acid, revealed two distinct electro-poisoning processes: one is due to the adsorption of CO on the surface sites of platinum, and the second to the formation of a passivating layer of P{dagger}O. The application of 20 kHz ultrasonic flux in the neighbourhood of the platinum / aqueous formic acid solution interface also appears to cause a change in the superficial structure of the electrode used, in a direction that favours the decomposition of this compound. To overcome problems of poisoning of the platinum surface, aqueous solutions of formic, dihydroxy malonic and oxalic acids were electrolysed, in a cell without diaphragm, by applying voltage and current ranges, at levels adapted to each of the species. It is necessary to bring the working electrode to a higher potential than the oxidation potential for formic acid, and to a lower potential for dihydroxy malonic and oxalic acids. The frequent modifications of the electrode potentials helped to achieve quantitative destruction of these species, to CO{sub 2} (and to water) with an electrochemical efficiency approaching 100 %. This wet oxidation process also offers the advantage of not raising the energy potential of the effluents to be treated, because it takes place in mild conditions (ambient temperature and pressure). (author). 131 refs., 90 figs., 48 tabs.

  3. Assessment of risks associated to ionizing radiations: lung cancers after domestic radon exposure and thyroid cancers after accidental exposure to radioactive iodines; Evaluation des risques associes aux rayonnements ionisants: cancers du poumon apres exposition domestique au radon et cancers de la thyroide apres exposition accidentelle aux iodes radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Catelinois, O

    2004-09-15

    The aim of this work is to develop a critical analysis of quantitative risk assessment in the field of ionizing radiation and to provide new estimates of attributable risks for particular situations of environmental exposure to ionizing radiation. This work is based on knowledge about dose-response relationships and ionizing radiation exposure of the general population. The work focuses on two different situations that both present an important interest for public health: lung cancer associated with domestic radon exposures (natural situation) and thyroid cancer associated with the Chernobyl accident fallout (accidental situation). The assessment of lung cancer risk associated with domestic radon exposure considers 10 dose-response relationships resulting from miner cohorts and case-control studies in the general population. A critical review of available data on smoking habits has been performed and allowed to consider the interactions between radon and tobacco. The exposure data come from measurements campaigns carried out since the beginning of the 1980 by the Institute for Radiation protection and Nuclear Safety and the Health General Directory in France. The French lung cancer mortality data are provided by the I.N.S.E.R.M.. Estimates of the number of attributable cancers are carried out for the whole country, stratified by 8 large regions (Z.E.A.T.) and by 96 departments for the year 1999 allowing to perform a sensibility analysis according to the geographical level of calculation. Uncertainties associated to risk coefficients and exposures have been quantified and it's impact on risk estimates is calculated. The estimated number of deaths attributable to domestic radon exposure ranges from 543 (90% uncertainty interval (U.I.): 75-1,097) to 3,108 (90% U.I.: 2,996-3,221). The corresponding risk fractions range from 2.2% (90% U.I.: 0.3%-4.4%) to 12.4% (90% U.I.: 11.9%-12.8%). The assessment of thyroid cancer risk in the most exposed area of France due to the Chernobyl nuclear power plant accident fallout, is based on the excess relative risk model published by E. Ron et al. in 1995. The target population is composed of all children younger than 15 years and living in the eastern part of France at the time of the accident (26 April 1986). The incidence rates between 1978 and 1997 are analysed and forecasted up to 2007 using age-period-cohort models. Thyroid doses are estimated from all available data about the contamination in France from the Chernobyl fallout/ The risks characterization is carried out by considering various scenarios on the projection of spontaneous incidence rates, the effectiveness of internal exposures compared to external ones and the levels of radioactive deposits. Uncertainties to the risk coefficient, the expected spontaneous incidence rates and the thyroid dose are considered. The estimated number of thyroid cancer cases in excess between 1991 and 2007 for the target population ranges from 5 (90% U.I.: 1-15) to 63 (90% U.I. 12-180). In comparison, depending on the scenario of spontaneous rate projection, the number of spontaneous cancer cases should range from 894 (90% U.I.: 869-920) to 1,716 (90% U.I.:1,691-1,741) between 1991 and 2007. The results show that the thyroid cancer incident rate increase observed in France during last 20 years cannot be explained by the Chernobyl fallout. The work provides an adaptation of the classical risk assessment method integrating each of its step such as a discussion about the choice of the dose-response relationship. The data analysis considers the interaction between ionizing radiation and other risk factors, a spontaneous incidence rate projection and a quantification of uncertainties. This work provides new results showing the importance of the choice of the dose-response relationship, of the consideration of the spontaneous incidence trend and of the quantification of uncertainties in risk assessment. In conclusion, this work provides new knowledge for public health by the analysis of enlarged epidemiological data. (author)

  4. Policy bill of program on the radioactive materials and wastes management. Press conference. Intervention of Francois Loos, Ministry delegate to the Industry; Projet de loi de programme sur la gestion des matieres et dechets radioactifs. Conference de presse. Intervention de Francois Loos, ministre delegue a l'Industrie

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    This document provides the presentation of Francois Loos concerning the policy bill on the program of radioactive materials and wastes. Three axis of researches are decided: the separation and transmutation, the deep underground disposal and long dated storage and conditioning processes. The bill institutes a national radioactive materials and waste management plan and defines a programme and calendar for research and work leading to implementation of this plan, which will comprise three major points: with a view to looking to reduce the quantity of waste, spent nuclear fuels taken from the nuclear power plants will be reprocessed for recycling in the plants; waste which cannot be recycled will be packaged in a robust matrix and then temporarily stored on the surface; after interim storage, waste which cannot be finally disposed of in a surface facility, will be placed in a deep geological reversible repository. In order to monitor each step in this plan, the bill strengthens independent assessment of research and involves greater information of the public. With regard to financing, the bill clarifies the fact that economic development of the departments concerned by research into disposal options and the research itself will be financed by additional taxes on the operators of nuclear installations. (A.L.B.)

  5. Log live high activity radioactive wastes / Researches and results law of the 30 December 1991. Separation and transmutation of long lived radionuclides; Les dechets radioactifs a haute activite et a vie longue / recherches et resultats Loi du 30 decembre 1991. Separation et transmutation des radionucleides a vie longue

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-12-15

    The law of the 30 December 1991 on the high activity long lived radioactive wastes reached the end. This synthesis final document presents the scientific and technological results, obtained still the end of 2005, on the separation and the transmutation of long lived radionuclides of high activity long lived radioactive wastes. It is organized in five chapters: a presentation of the context and the historical aspects, the researches, the objectives and the strategy of the axis 1, the researches results on the advanced separation, the researches results on the transmutation, the scenario of separation-transmutation and their environmental, technical and economical impacts. (A.L.B.)

  6. Fission-Product Separation as a Final Solution to the Problem of Storing Highly Radioactive Waste; La Separation des Produits de Fission Comme Solution Definitive du Stockage des Dechets Fortement Radioactifs; 0412 042b 0414 ; La Separacion de los Productos de Fision Como Solucion Definitiva del Problema del Almacenamiento de los Desechos de Elevada Radiactividad

    Energy Technology Data Exchange (ETDEWEB)

    Raggenbass, A.; Lefevre, J. [Centre d' Etudes Nucleaires, Saclay (France)

    1963-02-15

    At the 1955 Geneva Conference; it was suggested by Glueckauf that the problems presented by solutions of concentrated fission products could be dealt with by isolating caesium-137 and strontium-90 with a decontamination factor of at least 10{sup 4} so that, after conventional effluent processing, disposal could be effected in 10 to 20 years' time. This paper considers the suggestion in the light of the present situation. Thanks to the progress made in methods of separating caesium and strontium it now seems feasible to obtain this factor of 10{sup 4} under industrial conditions. The following methods are very promising: (a) For caesium-137: precipitation by phosphotungstic acid, exchange using an ammonium salt of a heteropoly-acid, fixation using a zirconium phosphate and (b) For strontium-90: oxalate precipitation, extraction by di-2 ethyl hexylphosphoric acid, exchange using various salts, strontium sulphate, etc. This progress in chemical techniques, backed up by advances in the industrial processing of effluents, indicate that Glueckauf's proposal is technically possible. In addition, the increasing use of large quantities of fission products, particularly in the SNAP programmes, justifies the outlay of capital, which will be recovered at least in part by the sale of the products made. There is no doubt that refractory sources with a very high resistance to attack by all external agents, constitute the most satisfactory means of storage for products so dangerous and of such long half-life. We believe, therefore, that both technically and psychologically, storing by means of concentrated sources with strong cladding is the most reliable method. A comparison of this method with that of fixation in glass is worthy of full and detailed examination. (author) [French] Glueckauf avait formule, a la Conference de Geneve en 1955, l'hypothese qu'une solution definitive aux problemes poses par les solutions de produits de fission concentres pouvait etre trouvee dans l'isolement du cesium-137 et du strontium-90 avec un facteur de decontamination d'au moins 10{sup 4}, ce qui permettrait d'envisager le rejet, apres un traitement d'effluents classique, au bout d'une periode de 10 a 20 ans. Le but du memoire est de faire le point de cette question en l'annee 1962. Les progres realises dans les methodes de separation du cesium et du strontium permettent d'envisager l'obtention de ce facteur 10{sup 4} dans des conditions exploitables industriellement. Des methodes pleines de promesses sont: a) Pour le cesium-137, la precipitation par l'acide phosphotungstique, l'echange sur un sel d'ammonium d'un heteropolyacide, la fixation par un phosphate de zirconium. b) Pour le strontium-90, la precipitation d'oxalate, l'extraction par l'acide di-2-ethyl-hexylphosphorique, l'echange sur des sels varies, sulfate de strontium, etc. Ces progres chimiques sont renforces par les progres realises dans le traitement industriel des effluents et permettent de considerer comme techniquement possible la solution preconisee par Glueckauf. Parallelement, le developpement de l'utilisation de grandes quantites de produits de fission, particulierement dans les programmes SNAP, justifie des investissements qui seront au moins pairtiellement recuperes par la vente des produits fabriques. Il est certain que des sources refractaires, a resistance tres elevee a tous les agents d'agression exterieurs, constituent le mode de stockage le plus satisfaisant pour des produits aussi dangereux et d'aussi longue periode. L'auteur considere done, techniquement et psychologiquement, Inverted-Exclamation-Mark /utilisation de sources concentrees a gainage riche comme le moyen de stockage presentant le plus de garanties. Une discussion comparative de cette methode avec la methode d'incorporation dans les verres meriterait un examen complet et approfondi. (author) [Spanish] En la Conferencia de Ginebra de 1955, Glueckauf formplo la hipotesis de que los problemas planteados por las soluciones de productos de fision concentrados podrian resolverse aislando el cesio-137 y el estroncio-90 con un factor de descontaminacion minimo de 10{sup 4}, lo que, despues de un tratamiento de efluentes ordinario permitiria proceder a la evacuacion al cabo de un periodo de 10 a 20 anos. La finalidad de esta memoria es exponer el estado de la cuestion en 1962. Los progresos realizados en los metodos de separacion del cesio y del estroncio permiten esperar la obtencion del mencionado factor 10{sup 4} en condiciones industrialmente explotables. He aqui los metodos que ofrecen mejores perspectivas: a) Para el cesio-137: la precipitacion mediante el acido fosfowolfrimico, el intercambio a base de una sal de amonio de un heteropoliacido, la fijacion mediante un fosfate de circonio, b) Para el estroncio-90: la precipitacion del oxalato, la extraccion mediante el acido di-2-etilhexil- fosforico, el intercambio a base de sales diversas, sulfato de estroncio, etc. Estos progresos en el terrenorde la quimica, a los que se suman los progresos realizados en el tratamiento industrial de los efluentes, permiten considerar tecnicamente posible la solucion propuesta por Glueckauf. Al mismo tiempo, el desarrollo de la utilizacion de grandes cantidades de productos de fision, particularmente dentro del marco de los programas SNAP, justifica la inversion de capitales que seran recuperados, poit lo menos parcialmente, mediante la venta de los productos fabricados. Es evidente que las fuentes refractarias, de muy alta resistencia frente a todos los agentes exteriores de ataque, constituyen la forma de almacenamiento mas satisfactoria para productos tan peligrosos y de periodo tan prolongado. Los autores consideran, pues, que desde el punto de vista tecnico y psicologico el empleo de fuentes concentradas con abundante revestimiento es el medio de almacenamiento que ofrece mayores garantias. Valdria la pena efectuar un estudio completo y detallado del metodo descrito comparandolo con el metodo de incorporacion de los desechos a masas vitreas. (author) [Russian] V 1955 godu na Zhenevskoj konferencii Gljukauf sformuliroval gipotezu o tom, chto okonchatel'noe reshenie problemy udalenija aktivnyh rastvorov, soderzhashhih produkty delenija, mohet byt' najdeno putem vydelenija cejeija-137 i stroncija-90 s kojefficientom ochistki porjadka menee 10{sup 4}, chto pozvolilo by posle vyderzhki 10-20 let svobodno udaljat' jeti othody posle sootvetstvujushhej pererabotki. Doklad presleduet cel' snova vernut'sja k jetomu voprosu v 1963 godu. Uspehi, dostignutye v metodah vydelenija cezija i stroncija, pozvoljaet poluchit' kojefficient ochistki porjadka 10{sup 4} v uslovijah promyshlennoj jekspluatacii ustanovki. Dlja cejeija-137 javljaetsja perspektivnym osazhdenie fosforvo.i'framatnoj kislotoj, obmen s ammonijnymi soljami geteropolikisloty, fiksacija fosfatom cirkonija, a dlja stroncija-90 - oksalatnoe osazhdenie, jekstrakcija di-2- jetilgeksilfosfornoj kislotoj, obmen s razlichnymi soljami, vkljuchaja sul'fat stroncija i dr. Jeti uspehi v oblasti himii vmeste s uspehami v oblasti promyshlennoj pererabotki jefljuentov sdelali vozmozhnym s tehnicheskoj tochki zrenija podtverdit' gipotezu Gljukaufa. Narjadu s jetim, razrabotka metodov ispol'zovanija bol'shih kolichestv produktov delenija, osobenno v sootvetstvii s programmami SNAP, chastichno opravdyvaet kapitalovlozhenija za schet prodazhi proizvodimoj produkcii. Ochevidno, chto ispol'zovanie ogneupornyh istochnikov, ustojchivyh k agressivnym vozdejstvijam vneshnej sredy, predstavljaet soboj primer, kotoryj naibolee otvechaet trebovanijam hranenija othodov, ves'ma opasnyh v techenie prodolzhitel'nogo perioda. My schitaem takzhe, chto s tehnicheskoj i psihologicheskoj tochek zrenija koncentrirovannye istochniki, pokrytye zashhitnoj obolochkoj, naibolee nadezhny kak sredstva hranenija radioaktivnyh othodov. Sravnenie jetogo metoda s metodom vvedenija radioaktivnosti v stekla zasluzhivaet bolee polnogo i glubokogo rassmotrenija. (author)

  7. Proceedings No. 41. Audition of M. Francois Loos, Delegate Minister of Industry, about the law project relative to the management of radioactive materials and wastes; Compte rendu n. 41. Audition de M. Francois Loos, ministre delegue a l'industrie, sur le projet de loi relatif a la gestion des matieres et dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-03-15

    The project of law about the management of radioactive materials and wastes is the logical continuation of the law no 91-1381 from December 30, 1991 relative to the researches on radioactive waste management. At the occasion of the presentation of this law project at the board of ministers, F. Loos, the French minister of industry, presented this project the same day also at the house of commons. This document is the proceedings of the audition of F. Loos. It comprises a brief recall of the researches carried out so far and a presentation of the 3 main points of the project of law: reprocessing of spent fuels and recycling in reactors, interim surface storage of non-recyclable wastes, and underground reversible disposal of ultimate wastes. One aspect of the project concerns the scheduling of future research works according to the 3 ways defined in the 1991 law: storage, disposal and transmutation. This presentation is followed by questions from the deputies about some particular points of the project like the safety aspects, the selection of storage sites, the acceptance and information of the public, the financial aspects etc. (J.S.)

  8. Program law n. 2006-739 of the 28 June 2006 relative to the sustainable management of radioactive materials and wastes: presentation by article; La loi de programme n. 2006-739 du 28 juin 2006 relative a la gestion durable des matieres et dechets radioactifs: presentation par article

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    The french law of 1991, decided to define management solutions in the radioactive wastes management policy, is now over. The results of researches led to the promulgation of a new planing act, the law of the 28 June 2006. This law concerns the sustainable management of radioactive materials and wastes. It takes also in account a public debate, organized in September 2005 by the National Commission for Public Debate. The Law project architecture can be described in three main points: the implementing of a national policy of radioactive materials and wastes, a better transparency and democratic control and the implementing of specific modalities for the organization and the financing of spent fuels and radioactive wastes management. This document presents what is in the different articles, with a special attention to the contributions of the parliamentary debate. (A.L.B.)

  9. Public debate on the general options relative to the management of high-medium activity and long-lived radioactive wastes; Debat public sur les options generales en matiere de gestion des dechets radioactifs de haute activite et de moyenne activite a vie longue

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-09-15

    The law from December 30, 1991, precisely defines 3 axes of researches for the management of high level and long-lived radioactive wastes: separation/transmutation, surface storage and underground disposal. A global evaluation report about these researches is to be supplied in 2006 by the French government to the Parliament. A first synthesis of the knowledge gained after 14 years of research has led the national commission of the public debate (CNDP) to organize a national debate about the general options of management of high-level and long-lived radioactive wastes before the 2006 date line. This document presents the organizational aspects of the debate: origin, organization committee (mission, members, commitments), framework (the December 31, 1991 law, technical enlargement, society aspects), topics (summary of the debate in ten questions), organization modalities (4 main steps, schedule, venues), objectives and perspectives (sharing information, decision making processes to be implemented by 2006). (J.S.)

  10. Oceanographic Research Required in Support of Radioactive Waste Disposal; Recherches Oceanographiques Necessaires pour l'Elimination des Dechets Radioactifs; 041e 041a 0415 0410 041d 041e 0413 0420 0414 ; Investigaciones Oceanograficas Necesarias para la Evacuacion de Desechos Radiactivos

    Energy Technology Data Exchange (ETDEWEB)

    Ketchum, Bostwick H. [Woods Hole Oceanographic Institution, Woods Hole, MA (United States)

    1960-07-01

    For low-level waste disposal in coastal waters the character of the biota and the eating habits of local human populations will determine the safe limits of contamination. In such a situation the sedimentary bottom populations win be important, since they will be exposed continuously, while planktonic and fish populations will drift through or enter the area of contamination sporadically. In the open ocean, on the other hand, planktonic populations are of prime importance, both as the food supply of pelagic edible species, and because they may be effective in transporting isotopes. Similar questions face biologists studying either sedentary or planktonic populations. These include the need to know the distribution and density of populations of various species, the rate of growth of the individuals and of the populations, the seasonal cycle of production and of abundance, the ability of various organisms to accumulate various elements, and the ways in which these elements are transported through the food web, to the bottom through sedimentation or vertically within the water column through migration and exchange. For each specific waste-disposal problem a survey of the local biota will be required, as will the subsequent monitoring of the operation. (author) [French] En ce qui concerne l'evacuation des dechets de faible activite dans les eaux cotieres, les limites de securite pour la contamination seront determinees par le milieu biologique et le regime alimentaire des habitants de la region. Dans une telle situation, ce sont les populations du fond sedimentaire qui joueront un role important puisqu'elles subissent une exposition permanente alors que le plancton et les poissons n'entrent dans les regions contaminees qu'en passant ou dans des cas isoles. En revanche, dans la haute mer, les populations planctoniques sont d'une importance primordiale a la fois comme source alimentaire pour les especes pelagiques comestibles et comme transporteurs eventuels d'isotopes. Des questions semblables se posent aux biologistes qui etudient les populations sedentaires ou planctoniques. Il faut qu'ils connaissant entre autres la distribution et la densite des populations de diverses especes, la rapidite de croissance des individus et de ces populations, le cycle saisonnier de la reproduction et de l'abondance, la faculte de divers organismes d'accumuler divers elements, et la facon dont ces elements atteignent le fond au moyen de la chaine alimentaire par voie de sedimentation, ou sont transportes verticalement au sein de la colonne d'eau par migration ou echange. Pour chaque probleme concret que souleve l'elimination des dechets, il faudra etudier le milieu biologique local et, par la suite, faire le controle radiologique de l'operation. (author) [Spanish] Cuando se trata de evacuar desechos de baja actividad en aguas costeras, - las condiciones de seguridad de la operacion quedan determinadas por el caracter de la fauna y la flora y por la forma de alimentacion de la poblacion humana local. En dicho caso habra que estudiar especialmente los organismos bentonicos sedentarios, que estaran expuestos continuamente a la irradiacion, en tanto que los peces y el plancton atravesaran la zona contaminada o solo entraran en ella de cuando en cuando. En cambio, las poblaciones planctonicas son de fundamental importancia en mar abierto, tanto por servir de alimento a las especies pelagicas comestibles como porque pueden transportar isotopos. Los biologos que estudian las poblaciones bentonicas o planctonicas deben resolver problemas similares. Por ejemplo: la necesidad de conocer la distribucion y la densidad de poblaciones de distintas especies; el indice de crecimiento individual y colectivo; el ciclo estacional de produccion y de abundancia ; la capacidad de algunos organismos para acumular diversos elementos, y la forma en que esos alimentos son transportados a traves de la cadena de alimentacion al fondo del mar (por medio de la sedimentacion) o verticalmente, dentro de la columna de agua (por migracion e intercambio). Para cada problema concreto de evacuacion de desechos sera necesario estudiar la fauna y flora local, asi como el consiguiente monitoraje de la operacion. (author) [Russian] Dlja udalenija othodov s nizkim urovnem aktivnosti v pribrezhnye vody opredeljajushhim faktorom urovnja zarazhenija budet sluzhit' harakter zhivotnogo i rastitel'nogo mira i sredstva pitanija mestnogo naselenija. Pri takom polozhenii veshhej sleduet udelit' vnimanie osadochnomu zhivotnomu miru, poskol'ku on budet podvergat'sja oblucheniju nepreryvno, togda kak planktony i ryba budut lish' proplyvat' ili zahodit' v zony sporadichnogo zarazhenija. S drugoj storony, v otkrytom okeane planktony igrajut pervostepennoe znachenie, kak s tochki zrenija togo, chto oni javljajutsja morskoj raznovidnost'ju pishhevogo produkta, tak i s tochki zrenija togo, chto oni javljajutsja nositeljami izotopov. S podobnymi voprosami stalkivajutsja biologi, izuchajushhie libo mir neperedvigajushhihsja zhivyh organizmov, libo mir planktonov. Zdes' neobhodimo znat' rasselenie i plotnost' razlichnyh raznovidnostej jetih organizmov; skorost' rosta otdel'nyh organizmov i ih semejstv v celom; vremja ih razmnozhenija i izobilija; sposobnost' razlichnyh organizmov akkumulirovat' v sebe razlichnye jelementy, a takzhe puti, po kotorym jeti jelementy perenosjatsja pishhevoj tkan'ju na dno posredstvom osazhdenija ili vertikal'no v vodjanom sloe posredstvom migracii i obmena. Dlja kazhdoj specificheskoj problemy po udaleniju othodov trebuetsja issledovanie mestnogo haraktera zhivotnogo i rastitel'nogo mira, a takzhe posledujushhego kontrolja samoj operacii po udaleniju othodov. (author)

  11. Treatment, Processing and Future Disposal of Radioactive Wastes at the Idaho Chemical Processing Plant; Traitement et Elimination Future des Dechets Radioactifs a l'Usine de Traitement Chimique de L'Idaho; 0410 041d 0414 ; Tratamiento y Evacuacion de Desechos Radiactivos en la Planta de Tratamiento Quimico de Idaho

    Energy Technology Data Exchange (ETDEWEB)

    Stevens, James I. [Phillips Petroleum Company, Atomic Energy Division, Idaho Falls (United States)

    1960-07-01

    Acidic wastes from the recovery of enriched uranium from aluminium, zirconium, and stainless-steel fuels at the Idaho Chemical Processing Plant are stored in underground tanks of two configurations and nominal sizes of 30,000 and 300,000 gallons. The design and operation of the waste-tank farm as well as the methods of environmental disposal of low-level wastes is described. The ''concentrate and contain'' philosophy of waste disposal has as its ultimate aim the production of a solid mass containing the fission products. The disadvantage of increased treatment costs may or may not be offset by reduction in storage costs. The low thermal conductivity of solids makes storage temperature considerations more important than for liquids. The acid aluminium nitrate wastes from the processing of fuels of the Material Testing Reactor type may be converted to granular alumina by calcining in a fluidized bed from 350 Degree-Sign to 550 Degree-Sign C. The major process components are the NaK heated calciner, an off-gas cleaning system and the solids storage vessels. The process design and the research and development programme are reviewed. On the basis of the successful demonstration of fluidized-bed calcining and high-temperature solids storage in conjunction with other considerations, a number of future storage concepts and their environmental connotations are discussed. (author) [French] A l'usine de traitement chimique de l'Idaho, les dechets acides provenant de la recuperation de l'uranium enrichi contenu dans les cartouches de combustible en aluminium, zirconium, et acier inoxydable sont stockes dans des reservoirs souterrains de deux formes differentes et d'une capacite theorique de 30,000 et de 300,000 gallons. L'auteur donne une description du plan et du fonctionnement de l'annexe ou se trouvent les reservoirs a dechets, ainsi que des methodes d'elimination des dechets de faible activite dans le milieu ambiant. Le but meme du systeme qui consiste a concentrer et a incorporer dans d'autres substances les dechets a eliminer est la production d'une masse solide contenant les produits de fission. L'inconvenient que constituent les frais de traitement plus eleves peut etre parfois compense par une reduction des frais de stockage. La faible conductivite thermique des corps solides donne plus d'importance a la temperature de stockage que dans le cas de liquides. Les dechets acides de nitrate d'aluminium provenant du traitement des combustibles du type de ceux que l'on utilise dans les reacteurs d'essai des materiaux peuvent etre transformes en aluminium granule par voie de calcination dans un lit fluidifie a une temperature allant de 350 Degree-Sign a 550 Degree-Sign C. Les principaux elements de l'installation sont: un calculateur chauffe au NaK, un systeme d'epuration des gaz d'echappement et un ensemble de recipients pour le stockage des matieres solides obtenues. L'auteur donne un apercu du processus de traitement et du programme de recherche et de mise au point. L'auteur examine un certain nombre de systemes futurs de stockage et leurs incidences sur le milieu ambiant en prenant pour base les resultats positifs de la demonstration du systeme de calcination a ht fluidifie et d'emmagasinage a haute temperature ainsi que d'autres considerations. (author) [Spanish] En la planta de tratamiento quimico de Idaho, los desechos acidos procedentes de la recuperacion del uranio enriquecido de los combustibles nucleares que contienen aluminio, zirconio y acero inoxidable se almacenan en tanques subterraneos de dos formas, con capacidades nominales de 30,000 y 300,000 galones. El autor describe la organizacion y funcionamiento de la seccion de tanques, asi como los metodos utilizados para la evacuacion de desechos de baja actividad. La evacuacion de desechos con arreglo al, principio de la 'concentracion y confinamiento' tiene por finalidad la obtencion de una masa solida que retenga los productos de fision. Los gastos mas elevados que este tratamiento supone pueden a veces quedar compensados por la reduccion de los gastos por concepto de almacenamiento. La baja conductividad termica de los solidos obliga a conceder mayor importancia a la temperatura de almacenamiento que en el caso de los liquidos. Los desechos acidos de nitrato aluminico que se forman al tratar los combustibles del tipo utilizado en los reactores de ensayo de materiales (MTR), pueden transformarse en alumina granular por calcinacion en un lecho fluidificado, a una temperatura comprendida entre 350 Degree-Sign y 550 Degree-Sign C. Los principales componentes de tal instalacion son: el calcinador alentado por una aleacion de NaK, un sistema.de depuracion de los gases desprendidos y los tanques para el almacenamiento de solidos. El autor describe el diseno de la instalacion, asi como el programa de investigaciones y desarrollo. Basandose en los resultados favorables obtenidos con este sistema de calcinacion en lecho fluidificado y almacenamiento de solidos a elevada temperatura, y en otras consideraciones, el autor examina diversos sistemas de almacenamiento y sus relaciones con el medio ambiente. (author) [Russian] Kislotnye othody, poluchajushhiesja ot rekuperacii obogashhennogo urana iz toplivnyh jelementov s aljuminiem, cirkoniem i nerzhavejushhej stal'ju na Zavode po himicheskoj pererabotke v Ajdaho, hranjatsja v podzemnyh bakah dvuh razlichnyh geometricheskih form s nominal'noj emkost'ju v 30,000 i 300,000 gallonov. V dokumente opisyvajutsja konstrukcii i rabo ta ustanovki dlja hranenija othodov v bakah, a takzhe metody udalenija v okruzhajushhuju sredu othodov s nizkim urovnem aktivnosti. Princip ''koncentracii i uderzhanija'' pri udalenii othodov vylilsja v konechnuju formu proizvodstva tverdoj massy, soderzhashhej produkty delenija. Nevygoda ot uvelichenija stoimosti obrabotki mozhet byt' pokryta sokrashheniem stoimosti hranenija, no ne vo vseh sluchajah. Vvidu nizkoj teploprovodnosti tverdyh tel soobrazhenija o temperature hranenija igrajut bolee znachitel'nuju rol', chem dlja zhidkih tel. Kislotnye othody azotnokislogo aljuminija, poluchajushhiesja pri pererabotke toplivnyh jelementov reaktorov tipa, sluzhashhego dlja ispytanija materialov, mogut byt' prevrashheny v granulirovannye aljuminy putem obzhiganija ih v razzhizhennom sostojanii pri temperature ot 350 do 550 Degree-Sign C. Glavnymi sostavnymi chastjami javljajutsja obzhigatel'naja pech's podogrevom na NaK, sistema ochistki vyhodjashhih gazov i emkosti dlja hranenija othodov v tverdom vide. V dokumente delaetsja opisanie jetoj konstrukcii, proizvodimyh issledovanij i programmy dal'nejshih rabot. V zavisimosti ot uspeha opytnoj ustanovki pechi dlja obzhiganija v razzhizhennom sostojanii i ot uspeha hranenija othodov v tverdom vide pri vysokoj temperature, a takzhe v svjazi i s drugimi soobrazhenijami, v doklade obsuzhdajutsja drugie vozmozhnosti hranenija othodov v budushhem i ih vlijanie na okruzhajushhuju sredu. (author)

  12. 2005 dossier. ANDRA's researches on the geological disposal of high-level and long-lived radioactive wastes. Results and perspectives; Dossier 2005. Les recherches de l'Andra sur le stockage geologique des dechets radioactifs a haute activite et a vie longue. Resultats et perspectives

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-06-15

    This document makes a status of the researches carried out by the French national agency of radioactive wastes (ANDRA) about the geologic disposal of high-level and long-lived radioactive wastes in deep geologic formations (argilites and granites). Content: 1 - Research on deep disposal of radioactive waste: general interest task: Legislative framework, ANDRA scientific objectives, Inspections and assessments; 2 - Designing a safe and reversible disposal system: Repository safety, Reversibility: an essential requirement; 3 - Clay Research on a repository in a clay formation, A long research programme, Dossier 2005 Argile; 4 - Meuse/Haute-Marne site clay: Expected properties of the rock formation, Choice of argillite, Meuse/Haute-Marne site, Conclusions from 10 years of research at the Meuse/Haute-Marne site; 5 - Repository installations: Safe and reversible architecture, Disposal of B waste, Disposal of C waste, Possible disposal of spent fuel (CU); 6 - The disposal facility in operation: From waste packages reception to their disposal in cells, Stages of the progressive closure of engineered structures; 7 - Reversible management: Freedom of choice for future generations, Various closure stages; 8 - Long-term evolution of the repository: Apprehending the repository complexity Main evolutions expected, Slow and limited release of radioactive substances; 9 - Repository safety and impact on man: Several evolution scenarios, Normal evolution, Altered evolution; 10 - Granite Research on a repository in a granite formation: A global approach, Scientific co-operations, Dossier 2005 Granite; 11 - Characteristics of French granite formations: What properties are required for a repository?, Different types of granite formations; 12 - Repository installations: Repository design adapted to granite fractures, Clay seals to prevent water flows, Waste disposal packages ensuring long-term leak-tightness, Physical and chemical environment favourable for waste packages, Architecture limiting the effects of heat; 13 - Results Status of progress and new perspectives: Fifteen years of considerable progress in research, The feasibility of a repository in a clay formation has been established, A repository in a granite formation is conceivable, After 2006: What are the perspectives for research on clay formation?.

  13. The Meuse-Haute Marne underground research laboratory. A scientific research tool for the study of deep geologic disposal of radioactive wastes; Le Laboratoire de Recherche souterrain de Meuse/Haute-Marne. Un outil de recherche scientifique pour etudier le stockage geologique profond de dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    The Meuse-Haute Marne underground research laboratory, is an essential scientific tool for the achievement of one of the ANDRA's mission defined in the framework of the law from December 30, 1991 about the long-term management of high-level and long-living radioactive wastes. This document presents this laboratory: site characterization, characteristics of the Callovo-Oxfordian clay, and laboratory creation, coordinated experiments carried out at the surface and in depth, and the results obtained (published in an exhaustive way in the 'Clay 2005' dossier). (J.S.)

  14. The ISRN has assessed the safety and radioprotection of the solid radioactive waste management area at CEA/Saclay; L'IRSN a expertise la surete et la radioprotection de la zone de gestion des dechets radioactifs solides du CEA/Saclay

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2009-07-01

    Completed by a report of a Permanent Group of Experts on the safety re-examination for the solid radioactive waste management area of the CEA/Saclay, this paper is a statement of the assessment by the IRSN (the French Institute of Radioprotection and Nuclear Safety) of this safety re-examination. It first recalls what a safety re-examination is for a nuclear installation and indicates the documents which have been transmitted by the CEA and analysed. Then, it briefly describes the activities which are performed in the concerned area: collecting, warehousing, conditioning, control and shipping of solid radioactive wastes or useless fuels. The IRSN comments the works done and to be done for the different operations on different types of waste (low or middle activity), and then the different aspects of the installation safety (radiations, confining, fire, climatic events, civil engineering)

  15. Status of the public debate on the general options of management of high and intermediate activity and long-lived radioactive wastes; Bilan du debat public sur les options generales en matiere de gestion des dechets radioactifs de haute activite et de moyenne activite a vie longue

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-01-15

    The law from December 30, 1991, precisely defines 3 axes of researches for the management of high level and long-lived radioactive wastes: separation/transmutation, surface storage and underground disposal. A global evaluation report about these researches is to be supplied in 2006 by the French government to the Parliament. A first synthesis of the knowledge gained after 14 years of research has led the national commission of the public debate (CNDP) to organize a national debate about the general options of management of high-level and long-lived radioactive wastes before the 2006 date line. The debate comprised 4 public hearings (September 2005: Bar-le-Duc, Saint-Dizier, Pont-du-Gard, Cherbourg), 12 round-tables (October and November 2005: Paris, Joinville, Caen, Nancy, Marseille), a synthesis meeting (December 2005, Dunkerque) and a closing meeting (January 2006, Lyon). This document is a status of the general organisation and progress of the debate from its preparing to its end in mid-January 2006. It shows the challenges the CNDP had to take up to treat the scientifical and technical questions in an accessible way, allowing the participation and the hearing of the large public. A status is made of the deception and satisfaction of the public. A lack of confidence in public authorities and scientists has been expressed several times. No pro-nuclear/anti-nuclear shock has occurred and the debate has revealed a remarkable richness in its content. One contribution of the debate to the future project of law is its enlargement to the overall nuclear wastes and valorizable materials and not only to the high/intermediate-level and long-lived wastes. (J.S.)

  16. Radio-tracer techniques in the study of corrosion by molten fluorides; Etude, a l'aide d'indicateurs radioactifs, de la corrosion provoquee par les fluorures fondus; Primenenie metodov radioaktivnykh indikatorov nrn izuchenii korrozii, prichinyaemoj rasplavlennymi ftoristymi soedineniyami; Estudio con indicadores radiactivos de la corrosion ocasionada por fluoruros fundidos

    Energy Technology Data Exchange (ETDEWEB)

    Grimes, W R; Watson, G M; DeVan, J H; Evans, R B [Oak Ridge National Laboratory, Oak Ridge, TN (United States)

    1962-03-15

    When Inconel or Inor-8 alloys are exposed to a molten fluoride mixture containing reducible material, chromium is selectively oxidized and removed from the alloy. By the use of radio-tracer Cr{sup 51}, the self-diffusion coefficients for chromium in Inconel and Inor-8 and the applicability of these values to alloys under corrosive conditions have been evaluated. Overall coefficients have been obtained (1) by measuring depletion of Cr{sup 51} (charged as CrF{sub 2}) for non-corrosive fluoride melts in alloy capsules and (2) by comparison of measured total radioactivity of exposed alloy specimens with that of the salt to which they were exposed. In addition, coefficients were obtained from measurement of tracer concentration profiles through successive electropolishings of the specimens. The overall coefficients and those obtained from electropolishing experiments agree very well for Inconel at high temperatures and for Inor-8 at all temperatures. For temperatures below 750{sup o}C, coefficients obtained by electropolishing Inconel specimens are higher than the overall values; the bulk diffusion process is not uniform for this case. In all cases, good agreement was found between the overall diffusion coefficients and those extrapolated from published data at higher temperature with generally similar Cr-Ni alloys. Duplicate, polythermal loops of Inor-8 were used to circulate a non-corrosive fluoride melt containing Cr{sup 51} (as CrF{sub 2}). One of these loops was sacrificed to evaluate take-up of Cr{sup 51} by the alloy; the second was used to circulate a melt containing FeF{sub 2} to obtain measurable removal of Cr from the alloy. Good agreement between observed behaviour and that predicted from the measured diffusion coefficients was obtained; this agreement suggests that the self-diffusion coefficient for Cr is insensitive to changes in chromium content of the Inor-8 alloy. (author) [French] Lorsqu'on soumet les alliages Inconel ou Inor-8 a l'action d'un melange de fluorures fondus contenant, des substances reductibles, le chrome est oxyde selectivement et elimine de l'alliage. En utilisant comme radioindicateur le chrome-51, les auteurs du memoire ont evalue les coefficients d'autodiffusion du chrome dans l'Inconel et l'Inor-8 et verifie dans quelle mesure les valeurs obtenues sont applicables aux alliages exposes a la corrosion. Les auteurs ont calcule les coefficients globaux: 1) en mesurant le passage du chrome-51 (employe sous forme de CrF{sub 2}) des capsules d'alliage aux fluorures non corrosifs fondus; 2) en comparant la radioactivite totale mesuree des echantillons d'alliage exposes avec celle du sel auquel ils avaient ete exposes. Ils ont calcule en outre des coefficients en mesurant les profils de concentration de l'indicateur par polissages electrolytiques successifs des echantillons. Les coefficients globaux et ceux qui ont ete obtenus par polissage electrolytique concordent parfaitement pour l'Inconel a des temperatures elevees et pour l'Inor-8 a toutes les temperatures. Pour les temperatures inferieures a 750{sup o}C, les coefficients obtenus par polissage electrolytique de l'Inconel sont superieurs aux coefficients globaux; dans ce cas, le processus de diffusion dans la masse n'est pas uniforme. Il y a toujours concordance satisfaisante entre les coefficients globaux de diffusion et les coefficients obtenus par extrapolation des donnees publiees au sujet d'alliages Cr-Ni generalement analogues, a des temperatures plus elevees. Les auteurs se sont servis de deux anneaux polythermiques d'Inor-8 pour faire circuler une masse de fluorures fondus non corrosifs contenant du chrome-51 (sous forme de CrF{sub 2}). Ils ont sacrifie l'un des circuits pour evaluer la quantite de {sup 51}Cr absorbee par l'alliage, et utilise l'autre pour faire circuler un melange fondu contenant du FeF{sub 2} et mesurer l'elimination du chrome de l'alliage. Les resultats obtenus concordent assez, bien avec les donnees fournies par les coefficients de diffusion mesures experimentalement; il est permis d'en conclure que le coefficient d'autodiffusion du chrome est insensible aux modifications de la teneur en chrome de l'alliage Inor-8. (author) [Spanish] Si se someten el Inconel o el Inor-8 a la accion de una mezcla de fluoruros fundidos, que contenga sustancias reducibles, el cromo sufre una oxidacion selectiva y es extraido de la aleacion. Con ayuda del indicador radiactivo {sup 51}Cr, los autores han evaluado los coeficientes de autodifusion del cromo en el Inconel y en el lnor-8, y han comprobado que los datos obtenidos son validos para las aleaciones expuestas a la corrosion. Han calculado los coeficientes globales 1) midiendo el paso del {sup 51}Cr de las capsulas de aleacion (empleado en forma do CrF{sub 2}) a los fluoruros no corrosivos fundidos, y 2) comparando la radiactividad total medida en las muestras de aleacion expuestas con la radiactividad de la sal a cuya accion fueron sometidas. Ademas, calcularon los coeficientes midiendo los perfiles do concentracion del indicador por pulidos electroliticos sucesivos de las muestras. Los coeficientes globales y los obtenidos por pulido electrolitico concuerdan satisfactoriamente para el Inconel a temperaturas elevadas, y para el lnor-8 a todas las temperaturas. Los valores obtenidos por pulido electrolitico del Inconel tratado a temperaturas inferiores a 760{sup o} C superan a los valores globales; en este caso, el proceso de difusion masica no es uniforme. Los coeficientes medios de difusion encontrados concuerdan siempre con los que se calculan por extrapolacion de los valores publicados, que fueron obtenidos con aleaciones de Cr-Ni similares, a temperaturas mas elevadas. Los autores se sirvieron de un par de buees politermicos de Inor-8 para hacer circular una masa de fluoruros no corrosivos fundidos que contenian {sup 51}Cr (en forma de CrF{sub 2}). Sacrificaron uno de estos bucles para evaluar la cantidad de {sup 51}Cr absorbida por la aleacion; el segundo se utilizo para hacer circular una mezcla fundida quo contenia FeF{sub 2} y medir la eliminacion del cromo de la aleacion. Los resultados obtenidos concuerdan satisfactoriamente con los que se calculan con ayuda de los coeficientes de difusion determinados experimentalmente; esta concordancia indica que el coeficiente de autodifusion del Cr no es afectado por las variaciones de la concentracion de cromo en la aleacion Inor-8. (author) [Russian] Kogda ''inkonel'' ili ''inor-8'' podvergayutsya dejstviyu rasplavlennykh ftoristykh smesej, soderzhashchikh vosstanavlivayushchie veshchestva, khrom izbiratel'no okislyaetsya i udalyaetsya iz splava. S pomoshch'yu radioaktivnogo indikatora Cr{sup 51} byli ustanovleny koehffitsienty samodiffuzii khroma v ''inkonsle'' i ''inore-8'', a takzhe byla izuchena primenimost' znachenij ehtikh koehffitsientov k splavam v korrozijnykh usloviyakh. Summarnye koehffitsienty byli polucheny putem sleduyushchikh zamerov: 1) obedneniya v Cr{sup 51} (zagruzhennogo v vide CrF{sub 2}) nekorrozijnykh ftoristykh rasplavov v legirovannykh kapsulakh i 2) sootnosheniya mezhdu izmerimoj obshchej radioaktivnost'yu obrabotannykh sol'yu obraztsov splava i radioaktivnost'yu soli, dejstviyu kotoroj obraztsy byli podvergnuty. Pomimo ehtogo, koehffitsienty byli polucheny putem zamera grafika kontsentratsii indikatora pri posledovatel'noj ehlektropolirovke obraztsov. Summarnye koehffitsienty, a takzhe koehffitsienty, poluchennye opytami ehlektropolirovki, ochen' blizko sovpadayut dlya ''inkonelya'' pri vysokikh temperaturakh i dlya ''inora-8'' pri vsekh temperaturakh. Dlya temperatur nizhe 750{sup o} C koehffitsienty, poluchetshe pri pomoshchi ehlektropolirovki obraztsov ''sinkonelya'' prevyshayut znacheniya summarnykh koehffitsientov; v ehtom sluchae protsess diffuzii v masse ne odnoobrazen. Vo vsekh sluchayakh nablyudalos' khoroshee sovladenie mezhdu summarnymi koehffitsientami diffuzii i koehffitsientami, poluchennymi putem ehkstrapolyatsii dannykh, opublikovannykh obychno dlya analogichnykh splavov khroma i nikelya pri bolee vysokikh temperaturakh. Dvojnye politermicheskie petli ''inora-8'' byli ispol'zovany dlya tsirkulyatsii nekorrozijnogo ftoristogo rasplava, soderzhashchego Cr{sup 51} (v vide CrF{sub 2}). Odna iz ehtikh petel' byla pozhertvovana dlya opredeleniya usvoeniya Cr{sup 51} ehtim splavom; vtoraya petlya byla ispol'zovana dlya tsirkulyatsii rasplava, soderzhashchego FeF{sub 2}, dlya polucheniya izmerimogo ustraneniya Cr iz splava. Bylo polucheno khoroshee sovpadenie mezhdu fakticheski nablyudavshimisya yavleniyami i prognozom, sdelannym na osnovanii izmerennykh koehffitsientov diffuzii. Iz ehtogo sovpadeniya mozhno zaklyuchit', chto koehffitsient samodiffuzii khroma nechuvstvitelen k izmeneniyam soderzhaniya khroma v splave ''inor-8''. (author)

  17. Towards a physical interpretation of third phase formation in liquid-liquid extraction. Application to the Diamex process for the treatment of high radioactive nuclear wastes; Vers une interpretation physique des phenomenes de troisieme phase en extraction liquide-liquide. Application au procede Diamex de traitement des effluents radioactifs de haute activite

    Energy Technology Data Exchange (ETDEWEB)

    Verdier-Erlinger, C

    1998-07-24

    Using SAXS, conductivity and phase behaviour determination we show that concentrated solutions of extractants are organised in reverse oligomeric aggregates which have many features in common with reverse micelles. The aggregation numbers of these reverse globular aggregates as well as their interaction potential are determined experimentally. The sticky sphere interaction is responsible for the de-mixing on the oil phase when in equilibrium with excess oil. Prediction of conductivity as well as formation condition for the third phase is possible using standard liquid theory applied to the reverse micelles. The attractive interaction, modeled with the sticky sphere model proposed by Baxter, is the balance of steric stabilisation introduced by the hydrophobic tails of the extracting molecule and the Van der Waals forces between the highly polarizable water core of the reverse molecule concentration, number of carbon atoms of aliphatic solvents, as well as proton and Neodymium cation concentration. It is shown that van der Waals interactions with a Hamaker constant of 2.5 kT explains the behaviour of DMDBTDMA in dodecane. (author) 184 refs.

  18. Nuclear structure of weakly bound radioactive nuclei through elastic and and inelastic scattering on proton. Impacts of the couplings induced by these exotic nuclei on direct reactions; Structure de noyaux radioactifs faiblement lies par diffusions elastiques et inelastiques sur proton. Effets des couplages induits par ces noyaux exotiques sur les reactions directes

    Energy Technology Data Exchange (ETDEWEB)

    Lapoux, V

    2005-09-15

    Information on the structure, spectroscopy and target interaction potentials of exotic nuclei can be inferred by interpreting measured data from direct reactions on proton such as elastic or inelastic scattering of proton (p,p') or one-nucleon transfer reaction (p,d). A series of experimental results has been obtained at the GANIL facilities on the setting composed of the MUST telescope array used for the detection of light charged-particles and of CATS beam detectors. This setting aims at measuring reactions on light proton or deuteron targets through reverse kinematics. Particularly, results on C{sup 10}, C{sup 11} and on direct reactions with the He{sup 8} beam of Spiral are presented. The first chapter is dedicated to the description of the most important theories concerning the nucleus. The experimental tools used to probe the nucleus are reported in the second chapter. The third and fourth chapters present the framework that has allowed us to analyse results from (p,p') and (p,d) reactions on weakly bound exotic nuclei. The last chapter is dedicated to the description of future experimental programs. (A.C.)

  19. Effect of previous administration of propyl-thiouracil on thyroid distribution of radioiodine. Contribution of secondary ion mass spectrometry microscopy to microdosimetry; Influence de l`administration prealable d`un antithyroidien de synthese (PTU) sur la distribution thyroidienne de l`iode radioactif. Apport de la microscopie ionique analytique a la microdosimetrie

    Energy Technology Data Exchange (ETDEWEB)

    Makki, B. [Centre Hospitalier Universitaire, 59 - Lille (France); Briancon, C.; Gavoille, A.; Fragu, P. [Centre de Lutte Contre le Cancer Gustave-Roussy, 94 - Villejuif (France)

    1995-12-31

    Radiation dose delivered to thyroid gland after radioiodine treatment for Graves` disease is modified by administration of propyl-thiouracil (PTU) which decreases the radioactive iodine uptake and increases its distribution heterogeneity within the thyroid follicle. Using secondary ion mass spectrometry (SIMS) microscopy which is able to map quantitatively chemical elements on histological specimen, we measured stable ({sup 127} I) and radioactive ({sup 129} I) iodine concentration within thyroid follicles of mice. Furthermore, we estimated the size of thyroid follicles and their spacing using image analysis processing. We demonstrated that only SIMS parameters were determinant for microdosimetry in the three experimental groups studied: treated with radioiodine or PTU therapy (A) or after short disrupting (B) and control (C). It is for the group B that the therapeutic conditions are best. Our results underline the interest of SIMS for revisiting dosimetry in metabolic radiotherapy. (authors). 21 refs., 2 tabs., 2 figs.

  20. Processing of spent fuels and radioactive waste coming from foreigner: application of the new decree L.542-2--1 from the code of environment; Traitement des combustibles uses et des dechets radioactifs provenant de l'etranger: application de l'article nouveau L.542-2-1 du code de l'environnement

    Energy Technology Data Exchange (ETDEWEB)

    Lahorgue, M.B. [Faculte de Droit de Poitiers - IDUCA EA - 2246, 86 (France)

    2008-04-15

    This decree clarifies the procedures applicable to the treatment of spent fuels and waste resulting from the foreigner. He has to have preliminary agreement between the governments and the obligation for the operator to set up devices of distribution of the waste as well as system of follow-up of entrances and exit out of the territory of radioactive substances. In any case, the storage of the waste has to exceed the technical period imposed by the reprocessing. An annual report must be put back by the operator and given to the public in two newspapers of national distribution. (N.C.)

  1. Proceedings of the public debate on the general options of management of high and intermediate activity and long-lived radioactive wastes; Compte-rendu du debat public sur les options generales en matiere de gestion des dechets radioactifs de haute activite et de moyenne activite a vie longue

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-01-15

    The law from December 30, 1991, precisely defines 3 axes of researches for the management of high level and long-lived radioactive wastes: separation/transmutation, surface storage and underground disposal. A global evaluation report about these researches is to be supplied in 2006 by the French government to the Parliament. A first synthesis of the knowledge gained after 14 years of research has led the national commission of the public debate (CNDP) to organize a national debate about the general options of management of high-level and long-lived radioactive wastes before the 2006 date line. The debate comprised 4 public hearings (September 2005: Bar-le-Duc, Saint-Dizier, Pont-du-Gard, Cherbourg), 12 round-tables (October and November 2005: Paris, Joinville, Caen, Nancy, Marseille), a synthesis meeting (December 2005, Dunkerque) and a closing meeting (January 2006, Lyon). This document is a summary of the main questions tackled during this debate from its preparation to its closing meeting and dealing with: the acceptation of the debate, the progress of the debate, the socio-technical problem of gathering the different points to be debated with respect to the different areas in concern, the general questions about the overall nuclear wastes and materials (radioactivity, health, radioprotection, management, reprocessing, control, actors organization, knowledge sharing, perenniality of the financing), the specific questions about long-lived wastes (inventory, separation-transmutation feasibility, nuclear energy and energy policy, management solutions, storage and geologic disposal feasibility, impact of debates on the 2006 law, long-lived waste territories), the conclusions for the 2006 law: mastering the overall nuclear wastes and materials and step-by-step building up of a solution for long-lived wastes (difficulties, lessons learnt from foreign experience, first draft of the 2006 law). Some opinions expressed by some participants about these proposals conclude the document. (J.S.)

  2. Detection of WIMPs in the Edelweiss experiment. Study of the radioactive background noise and measurements with bolometers; Recherche des wimp's du halo galactique dans l'experience edelweiss: etude du bas bruit radioactif et mesures a l'aide de bolometres a double detection ionisation/chaleur

    Energy Technology Data Exchange (ETDEWEB)

    Miramonti, L. [CEA/Saclay, Dept. d' Astrophysique, de la Physique des Particules, de la Physique Nucleaire et de l' Instrumentation Associee (DAPNIA), 91 - Gif-sur-Yvette (France)]|[Paris-11 Univ., 91 - Orsay (France)

    1999-11-01

    This thesis is dedicated to the detection of black matter in the form of WIMPs (weakly interacting massive particle). The characteristics of the interaction of WIMPs with matter are recalled. The very low number of expected events (<1 event/day.Kg) implies a radioactive background noise as weak as possible, furthermore the exponential decrease of the interacting rate with increasing energy calls for detectors with very low thresholds. Bolometers present advantages in WIMPs detection: i) very good resolution and very low thresholds, ii) very broad range of materials that can be used as absorber, the only requirements are: a crystal structure, to be a diamagnetic isolator and to have a convenient Debye temperature, iii) the possibility of detecting ionizing or non-ionizing particles, iv) the possibility of identifying the incident particle by measuring both temperature and another parameter such as ionization or scintillation, and v) the possibility of localizing the interaction inside the absorber by detecting ballistic phonons. The problematic of radioactive background noise is presented and the answers to the different sources (cosmic radiation,natural and artificial radioactivity) generating the background noise are examined. The materials used in the building of the detector and cryostat must be carefully chosen, they should be as little radioactive as possible. The test benches used to select materials for the Edelweiss experiment are described. The first measurements concerning the detectors Ge-4 and Ge-7 are presented. (A.C.)

  3. Optimization of the energy resolution and of the radioactive background rejection for ionization-heat detectors equipped with thermometric thin films for the direct WIMPs detection; Optimisation du pouvoir de resolution et du rejet du fond radioactif de detecteurs ionisation-chaleur equipes de couches minces thermometriques pour la detection directe de WIMPS

    Energy Technology Data Exchange (ETDEWEB)

    Dolgorouky, Y.W.

    2008-09-15

    The EDELWEISS experiment aims at the direct detection of WIMPs as possible candidates for dark matter. It uses heat-and-ionization detectors that can discriminate these particles from the radioactive background. To date, this method is limited by events with incomplete charge collection that occur just beneath the detectors electrodes. In order to identify and reject these undesirable events, we have developed detectors equipped with thin films used both as thermometers - and hence sensitive to the transient athermal regime - and as electrodes for the charge collection. This thesis focuses on the optimization of such thin films regarding surface events rejection and on the modelling of the physical processes enabling this identification. The optimization must both maximize the fiducial volume and conserve an energy resolution such that the recoil energy threshold is of the order of 30 keV. Our work explores four generations of detectors each of which corresponds to successive evolutions in their conception. In all cases, the electrode-thermometer is an amorphous Anderson insulator NbSi thin film polarized by two interleaved comb-shaped niobium electrodes. In spite of constant progress in the successive detectors performances, the latest generation does not display the performances required for the EDELWEISS II experiment. Our work has shown the difficulty of the transient thermal signal modelling due to the complex contribution of the charge collection. This works has lead to new ideas regarding the detectors configuration, so that the athermal regime can be optimized to enhance both the rejection capability and the resolution. (author)

  4. Characterisation of gas transport properties of the Opalinus clay, a potential host rock formation for radioactive waste disposal; Caracterisation des proprietes des argiles d'Opalinus (roche d'accueil potentielle pour un stockage de dechets radioactifs) relatives au transport des gaz

    Energy Technology Data Exchange (ETDEWEB)

    Marschall, P. [Nagra - National Cooperative for the Disposal of Radioactive Waste, Wettingen (Switzerland); Horseman, S. [British Geological Survey, Kingsley Dunham Centre, Keyworth (United Kingdom); Gimmi, T. [Bern Univ. (Switzerland); Paul Scherrer Inst. (PSI), Villigen (Switzerland)

    2005-07-01

    The Opalinus Clay in Northern Switzerland has been identified as a potential host rock formation for the disposal of radioactive waste. Comprehensive understanding of gas transport processes through this low-permeability formation forms a key issue in the assessment of repository performance. Field investigations and laboratory experiments suggest an intrinsic permeability of the Opalinus Clay in the order of 10{sup -20} to 10{sup -21} m{sup 2} and a moderate anisotropy ratio {<=} 10. Porosity depends on clay content and burial depth; values of {approx} 0.12 are reported for the region of interest. Porosimetry indicates that about 10-30% of voids can be classed as macro-pores, corresponding to an equivalent pore radius > 25 nm. The determined entry pressures are in the range of 0.4-10 MPa and exhibit a marked dependence on intrinsic permeability. Both in situ gas tests and gas permeameter tests on drill-cores demonstrate that gas transport through the rock is accompanied by pore water displacement, suggesting that classical flow concepts of immiscible displacement in porous media can be applied when the gas entry pressure (i.e. capillary threshold pressure) is less than the minimum principal stress acting within the rock. Essentially, the pore space accessible to gas flow is restricted to the network of connected macro-pores, which implies a very low degree of desaturation of the rock during the gas imbibition process. At elevated gas pressures (i.e. when gas pressure approaches the level of total stress that acts on the rock body), evidence was seen for dilatancy controlled gas transport mechanisms. Further field experiments were aimed at creating extended tensile fractures with high fracture transmissivity (hydro- or gas-fractures). The test results lead to the conclusion that gas fracturing can be largely ruled out as a risk for post-closure repository performance. (authors)

  5. Chemical analysis of radioactive liquid wastes. Volumetric dosage of sulfates in the presence of phosphates, 'nitrochromazo' being used as an indicator; Analyse chimique des effluents radioactifs - dosage volumetrique des sulfates en presence de phosphates a l'aide du 'nitrochromazo' comme indicateur

    Energy Technology Data Exchange (ETDEWEB)

    Testemale, G; Girault, J [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1969-07-01

    A simple titration technique of SO{sub 4} ions in the presence of PO{sub 4} ions has been perfected. The pH of the medium is stated to 1,7-2,0 the colour of the indicator changes from violet to blue. The method is quick, accurate and can be fitted to biological studies or in the industry of fertilizes. The synthesis method of nitrochromazo (acid 2, 7 bis (4 nitro 2 sulfobenzene 1 azo) 1-8 hydroxynaphthalene 3-6 disulfonic) is described. (authors) [French] Une technique simple de titrage des ions SO{sub 4} en presence d'ions PO{sub 4} a ete mise au point. Le pH du milieu est fixe a 1,7-2,0, le virage de l'indicateur s'effectue du violet au bleu. La methode est rapide, precise et peut etre adaptee a des travaux de biologie ou dans l'industrie des engrais. La methode de synthese du 'Nitrochromazo' (acide 2, 7 bis (4 nitro 2 sulfobenzene 1 azo) 1-8 dihydroxynapthtalene 3-6 disulfonique) est decrite. (auteurs)

  6. Results of several years experiments on the absorption of radioactive strontium and caesium by cultivated plants (1962); Compte rendu d'experiences de plusieurs annees sur l'absorption du strontium et du cesium radioactifs par des plantes cultivees (1962)

    Energy Technology Data Exchange (ETDEWEB)

    Michon, M. [Commissariat a l' Energie Atomique, Dept. de Protection Sanitaire, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires; Benard, M.; Flanzy, M. [Station Centrale de Technologie des Produits Vegetaux, 11 - Narbonne (France); Fioramonti, M.; Marty, M. [Station Agronomique de Toulouse, 31 (France); Barbier, M.; Le Blaye, M.; Brossard, M. [Societe Centrale d' Agronomie, 78 - Versailles (France)

    1962-07-01

    This report follows on to the report number CEA 1860 and uses results obtained in 1960 to give more precise details concerning the data presented in the preceding report. First results obtained on the vine are given. The Sr absorption coefficient has varied very little from one year to the next and that of caesium has slightly diminished. The values obtained suggest that the concentrations of {sup 90}Sr and {sup 137}Cs in irrigation water should not exceed 1/5 of the maximum permissible concentration in drinking water. (authors) [French] Ce rapport fait suite au rapport CEA 1860 et precise grace aux resultats acquis en 1960 les donnees exprimees dans le precedent rapport. Il y est fait mention des premiers resultats obtenus pour la vigne. Le coefficient d'absorption du Sr a peu varie d'une annee sur l'autre et celui du cesium legerement diminue. Les valeurs obtenues permettent de penser qu'il serait souhaitable que la concentration en {sup 90}Sr et en {sup 137}Cs dans l'eau d'irrigation ne depasse pas le 1/5 de la concentration maxima admissible pour l'eau de boisson. (auteurs)

  7. Measurement of radioactive isotopes by {gamma} and x rays spectrometry with INa crystals. application to radiochemistry of some fission and activation products; Mesures d'isotopes radioactifs par spectrometrie {gamma} et x a l'aide de cristaux INa. application a la radiochimie de certains produits de fission et d'activation

    Energy Technology Data Exchange (ETDEWEB)

    Simonet, P; Boile, G; Simonet, G [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1965-07-01

    The measurement of an number of atoms N may be obtained by detection of one {gamma} ray emitted if its branching ratio K{sub E} is known (number of E energy {gamma} transitions/number of disintegrations). N = A/{lambda} N{sub {gamma}}{sub E} / (K{sub E} * {lambda}) This measurement is effectuated in well-defined geometry, {gamma} rays emitted by the source are detected by a calibrated NaI crystal which is connected to a photomultiplier delivering electric impulses analysed by a multichannel analyser. Crystals are chosen according to energy, intensity of measured rays and of background. Calibration is established with standard sources or by total absolute efficiency of a definite crystal. Half-life, energy of measured photopeak branching ratio have been determined for these isotopes: Fission products: {sup 95}Zr, {sup 95}Nb, {sup 99}Mo, {sup 103}Ru, {sup 106}Ru, {sup 111}Ag, {sup 115}Cd, {sup 115m}Cd, {sup 132}Te, {sup 129m}Te, {sup 134}Cs, {sup 136}Cs, {sup 137}Cs, {sup 140}Ba, {sup 140}La. Rare earth elements: {sup 91}Y, {sup 141}Ce, {sup 144}Ce, {sup 147}Nd, {sup 156}Eu. Products from reactions (n, {gamma}) (n, 2n): 1{sup 10}Ag, {sup 124}Sb, {sup 239}Np, {sup 237}U, {sup 241}Am. (authors) [French] La mesure du nombre d'atomes N d'un isotope peut s'effectuer sur un rayonnement {gamma} si l'on connait le rapport d'embranchement K{sub E} (nombre de rayonnements {gamma} d'energie E/nombre de desintegrations). N = A/{lambda} N{sub {gamma}}{sub E} / (K{sub E} * {lambda}) La mesure s'effectue en geometrie definie; les rayonnements {gamma} emis par la source sous mylar sont detectes par un cristal INa etalonne en fonction de l'energie, lequel est relie a un photomultiplicateur delivrant des impulsions electriques qui seront analysees par un selecteur multicanaux. La connaissance de la distribution theorique (effet photoelectrique, compton, paires, retrodiffusion, echappement... ) permet de determiner qualitativement si les elements sont purs, et de faire une mesure sur le photopic, qui est gaussien, en tenant compte eventuellement des superpositions de spectres. Les cristaux sont choisis suivant l'energie, l'intensite des rayonnements a mesurer et ambiants. L'etalonnage se fait a l'aide de sources etalons ou d'un cristal etalon, par le photopic ou par efficacite totale. La periode, l'energie du photopic mesure, le pourcentage de rayons {gamma} sont donnes pour les isotopes generalement etudies: Produits de fission: {sup 95}Zr, {sup 95}Nb, {sup 99}Mo, {sup 103}Ru, {sup 106}Ru, {sup 111}Ag, {sup 115}Cd, {sup 115m}Cd, {sup 132}Te, {sup 129m}Te, {sup 134}Cs, {sup 136}Cs, {sup 137}Cs, {sup 140}Ba, {sup 140}La. Terres rares: {sup 91}Y, {sup 141}Ce, {sup 144}Ce, {sup 147}Nd, {sup 156}Eu. Produits de reactions (n, {gamma}) (n, 2n): 1{sup 10}Ag, {sup 124}Sb, {sup 239}Np, {sup 237}U, {sup 241}Am. (auteurs)

  8. High-dilution on-stream isotopic tracer techniques; Emploi d'indicateurs radioactifs tres dilues pour le controle les courants; Metody primeneniya sil'no razbavlennykh v potokakh izotopnykh indikatorov; Empleo de indicadores radiactivos muy diluidos en el control de corrientes

    Energy Technology Data Exchange (ETDEWEB)

    Johnston, W H; Findeis, A F; Vestal, M [William H . Johnston Laboratories, Inc., Baltimore, MD (United States)

    1962-01-15

    The present paper concerns large-scale tracer applications in which isotope tagging is done on a component of main flowing fluid or stream without subsequent mainline separation. Equations are derived which relate the required levels of tracer concentrations, the instrumental background, the efficiency of the detector, the required statistical reliability, the time desired for the measurements of sample and background, the stream flow rates, and the tracer nuclide. These equations are shown graphically and allow a ready selection of the tracer concentrations for specific applications. The sampling programme for large-scale tracer applications is analysed for steady state and pulse injections. In the latter case, the longitudinal mixing is treated by the concept of eddy diffusion coefficients. By estimating certain parameters, the longitudinal tracer detection range and the first arrival time are obtained as a function of distance between injection and collection. l'or high-dilution on-stream radiotracing with beta-emitters, the detectors are large low-level internal-gas-tube counters, foil-flow counters, and plastic scintillators. New anticoincidence counters are presented. The advantages of low-atomic-number shielding are emphasized. Recent developments in stable transistorized electronics for low-level counting are shown. A new amplifier and a new tunnel-diode adder circuit are described. Examples are given of several new applications of high-dilution on-stream tracers to problems of source-identification of pollutions in rivers and streams. (author) [French] Le memoire traite de l'emploi a grande echelle d'indicateurs pour le marquage isotopique des eaux d'un courant affluent qui ne se separe pas ensuite du courant principal. Les auteurs ont etabli des equations indiquant les rapports entre le taux de concentration des indicateurs, le bruit de fond du aux instruments, l'efficacite du detecteur, la qualite que l'on attend des donnees statistiques obtenues, le temps desire pour la mesure de l'echantillon et du rayonnement ambiant, la vitesse du courant et le radioelement utilise comme tracteur. Ils donnent une representation graphique de ces equations qui permet de determiner rapidement la concentration a adopter pour telle ou telle application. Le memoire analyse le programme d'echantillonnage pour l'emploi a grande echelle d'indicateurs injectes de facon continue ou par intermittence. Dans ce dernier cas, on etudie le melange longitudinal en appliquant les coefficients de diffusion par turbulence. En estimant certains parametres, on obtient les limites longitudinales de detection des traceurs et le temps d'arrivee en fonction de la distance entre le point d'injection et l'endroit ou se fait l'echantillonnage. Pour le controle au moyen d'emetteurs beta tres dilues, les detecteurs utilises sont de grands compteurs avec tube a gaz pour faibles intensites, des compteurs a feuilles et a flux continu et des scintillateurs en plastique. Les auteurs donnent des renseignements sur nouveaux compteurs a anticoincidence et soulignent les avantages de la protection au moyen d'elements a. faible nombre atomique. Le memoire rend compte des progres recents dans le domaine des circuits electroniques stables a transistors pour le comptage de faibles intensites et decrit un nouvel amplificateur et un nouveau circuit additionneur a diode . Il donne aussi des exemples de plusieurs applications nouvelles des indicateurs tres dilues pour l'identification des sources de pollution dans les fleuves et les cours d'eau. (author) [Spanish] Los autores estudian las aplicaciones en gran escala de trazadores en las que se procede a la marcacion isotopica de uno de los componentes de una corriente o fluido en movimiento, sin separarlo despues de la corriente principal. Los autores obtienen ecuaciones que permiten establecer relaciones entre las concentraciones a que se ha de utilizar el trazador, la actividad de fondo de los instrumentos, la eficacia del detector, el grado de exactitud estadistica necesaria, el margen de tiempo mas conveniente para las mediciones de las muestras y de la actividad de fondo, el caudal de la corriente y las caracteristicas del nuclido utilizado como indicador. Estas ecuaciones, representadas graficamente, permiten seleccionar facilmente las concentraciones del trazador mas adecuadas para una aplicacion concreta. La memoria analiza tambien el programa de muestreo que conviene seguir en las aplicaciones de trazadores en gran escala, tanto para adiciones intermitentes de trazador como para adiciones en regimen continuo. En el primer caso, la mezcla longitudinal se trata con arreglo a las leyes de la difusion turbulenta. Si se evaluan determinados parametros, se obtienen la distancia maxima de deteccion del trazador y el tiempo minimo de llegada en funcion de la distancia entre el lugar de descarga y el de la toma de muestras. En la marcacion de corrientes con ayuda de emisores beta muy diluidos, se utilizan como detectores grandes contadores de gas interno para bajas actividades, contadores de flujo con lamina detectora y centelleadores plasticos. Tambien describen nuevos contadores de anticoincidencias y subrayan las ventajas del blindaje con elementos de bajo numero atomico. La memoria expone los adelantos recientemente realizados en materia de circuitos electronicos estables con transistores para recuentos de baja actividad, y describe un nuevo amplificador y un nuevo circuito sumador de diodo tunel. Tambien dan ejemplos de varias aplicaciones nuevas de trazadores muy diluidos a la resolucion de problemas relativos a la identificacion de fuentes de contaminacion en rios y corrientes. (author) [Russian] V nastoyashchem doklade razbirayutsya voprosy primeneniya v shirokom masshtabe indikatorov v operatsiyakh, pri kotorykh mechenie izotopami proizvoditsya na pritoke glavnogo potoka zhidkosti ili ruch'ya bez dal'nejshego otklyucheniya glavnoj magistrali. Vyvodyatsya uravneniya, svyazyvayushchie trebuemye urovni kontsentratsii indikatorov, pribornoe oborudovanie, ehffektivnost' detektorov, trebuemuyu statisticheskuyu nadezh- nost', zhelatel'nuyu prodolzhitel'nost' vremeni, udelyaemogo na izmerenie obraztsa i fona, skorost' techeniya potoka i kharakter radioizotopnogo indikatora. EHti uravneniya predstavleny graficheski i dayut vozmozhnost' legko vybrat' nuzhnuyu dlya togo ili inogo primeneniya kontsentratsiyu indikatora. Razbiraetsya programma vzyatiya obraztsov dlya primeneniya indikatorov v shirokom masshtabe v voprosakh izucheniya ustojchivogo sostoyaniya i pul'siruyushchikh vpuskov. V poslednem sluchae smeshivanie v prodol'nom napravlenii traktuetsya po teorii koehffitsientov vikhrevoj diffuzii. Iskhodya iz nekotorykh predpolozhitel'nykh parametrov, mozhno opredelit' rasstoyanie, na kotorom mozhno obnaruzhit' indikator, i moment, kogda indikator vpervye dokhodit do mesta zamera, v funktsii ot rasstoyaniya mezhdu mestom vpuska indikatora i mestom vzyatiya obraztsa. Dlya mecheniya potokov sil'no razbavlennymi radioizotopami s pomoshch'yu beta-izluchatelej primenyayutsya detektory v vide bol'shikh schetchikov nizkogo urovnya s trubkami, zapolnennymi gazom, fol'ga-potochnye schetchiki i plasticheskie stsintillyatory. Opisyvayutsya novye schetchiki antisovpadenij. Podcherkivayutsya preimushchestva ehkranirovaniya materialami s nizkim atomnym chislom. Ukazyvayutsya novejshie dostizheniya v schete pri pomoshchi ustojchivykh rabotayushchikh na tranzistorakh ehlektronnykh ustrojstv nizkogo urovnya. Opisyvayutsya novyj usilitel' i novyj tunnel'nyj summiruyushchij diodnyj kontur. Dayutsya primery neskol'kikh novykh primenenij sil'no razbavlennykh indikatorov v potokakh dlya razresheniya problemy opoznavaniya istochnika zagryazneniya v rekakh i ruch'yakh. (author)

  9. Assessment of risks associated to ionizing radiations: lung cancers after domestic radon exposure and thyroid cancers after accidental exposure to radioactive iodines; Evaluation des risques associes aux rayonnements ionisants: cancers du poumon apres exposition domestique au radon et cancers de la thyroide apres exposition accidentelle aux iodes radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Catelinois, O

    2004-09-15

    The aim of this work is to develop a critical analysis of quantitative risk assessment in the field of ionizing radiation and to provide new estimates of attributable risks for particular situations of environmental exposure to ionizing radiation. This work is based on knowledge about dose-response relationships and ionizing radiation exposure of the general population. The work focuses on two different situations that both present an important interest for public health: lung cancer associated with domestic radon exposures (natural situation) and thyroid cancer associated with the Chernobyl accident fallout (accidental situation). The assessment of lung cancer risk associated with domestic radon exposure considers 10 dose-response relationships resulting from miner cohorts and case-control studies in the general population. A critical review of available data on smoking habits has been performed and allowed to consider the interactions between radon and tobacco. The exposure data come from measurements campaigns carried out since the beginning of the 1980 by the Institute for Radiation protection and Nuclear Safety and the Health General Directory in France. The French lung cancer mortality data are provided by the I.N.S.E.R.M.. Estimates of the number of attributable cancers are carried out for the whole country, stratified by 8 large regions (Z.E.A.T.) and by 96 departments for the year 1999 allowing to perform a sensibility analysis according to the geographical level of calculation. Uncertainties associated to risk coefficients and exposures have been quantified and it's impact on risk estimates is calculated. The estimated number of deaths attributable to domestic radon exposure ranges from 543 (90% uncertainty interval (U.I.): 75-1,097) to 3,108 (90% U.I.: 2,996-3,221). The corresponding risk fractions range from 2.2% (90% U.I.: 0.3%-4.4%) to 12.4% (90% U.I.: 11.9%-12.8%). The assessment of thyroid cancer risk in the most exposed area of France due to the Chernobyl nuclear power plant accident fallout, is based on the excess relative risk model published by E. Ron et al. in 1995. The target population is composed of all children younger than 15 years and living in the eastern part of France at the time of the accident (26 April 1986). The incidence rates between 1978 and 1997 are analysed and forecasted up to 2007 using age-period-cohort models. Thyroid doses are estimated from all available data about the contamination in France from the Chernobyl fallout/ The risks characterization is carried out by considering various scenarios on the projection of spontaneous incidence rates, the effectiveness of internal exposures compared to external ones and the levels of radioactive deposits. Uncertainties to the risk coefficient, the expected spontaneous incidence rates and the thyroid dose are considered. The estimated number of thyroid cancer cases in excess between 1991 and 2007 for the target population ranges from 5 (90% U.I.: 1-15) to 63 (90% U.I. 12-180). In comparison, depending on the scenario of spontaneous rate projection, the number of spontaneous cancer cases should range from 894 (90% U.I.: 869-920) to 1,716 (90% U.I.:1,691-1,741) between 1991 and 2007. The results show that the thyroid cancer incident rate increase observed in France during last 20 years cannot be explained by the Chernobyl fallout. The work provides an adaptation of the classical risk assessment method integrating each of its step such as a discussion about the choice of the dose-response relationship. The data analysis considers the interaction between ionizing radiation and other risk factors, a spontaneous incidence rate projection and a quantification of uncertainties. This work provides new results showing the importance of the choice of the dose-response relationship, of the consideration of the spontaneous incidence trend and of the quantification of uncertainties in risk assessment. In conclusion, this work provides new knowledge for public health by the analysis of enlarged epidemiological data. (author)

  10. The dismantling of nuclear installations and the radioactive wastes management. Report of the President of the Republic followed by the answers of concerned administrations and organisms; Le demantelement des installations nucleaires et la gestion des dechets radioactifs. Rapport au President de la Republique suivi des reponses des administrations et des organismes interesses

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-01-15

    The discussed subjects concerns the situation and the challenges of the nuclear installations dismantling and the radioactive wastes management (main intervenors, panorama of the situation, rules applied to the dismantling and the radioactive wastes), the first experiences of dismantling and radioactive wastes disposal (experiences at the CEA and EDF, implementing of solutions for the disposal), interrogations and certainties (provision for future expenses, public information). (A.L.B.00.

  11. The energy Review: the revision of british the energy policy and the radioactive wastes: the report of Committee on Radioactive Waste Management; L'energy review: la revision de la politique energetique britannique et dechets radioactifs: le rapport du 'Commitee on Radioactive Waste Management'

    Energy Technology Data Exchange (ETDEWEB)

    Daoudi, M

    2006-07-15

    This report presents the british energy policy, in which the nuclear power has a real part. The report details: the reduction of the carbon emission by the energy conservation and the clean energies, the energy safety, the impacts of the Energy Review, the technology part to reach these objectives and some reactions. The second part is devoted to the radioactive wastes and a presentation of the report Committee on Radioactive Wastes. (A.L.B.)

  12. The main evolutions brought by the parliamentary examination to the program law relative to the sustainable management of radioactive materials and wastes; Les principales evolutions apportees par l'examen parlementaire a la loi de programme relative a la gestion durable des matieres et dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    The french law of 1991, decided to define management solutions in the radioactive wastes management policy, is now over. The results of researches led to the promulgation of a new planing act, the law of the 28 June 2006. This law concerns the sustainable management of radioactive materials and wastes. It takes also in account a public debate, organized in September 2005 by the National Commission for Public Debate. The Law project architecture can be described in three main points: the implementing of a national policy of radioactive materials and wastes, a better transparency and democratic control and the implementing of specific modalities for the organization and the financing of spent fuels and radioactive wastes management. After the parliamentary examination, the text prepared by the Government was modified. This document presents the main four themes of modification. (A.L.B.)

  13. Resonant ionization by laser beams: application to ions sources and to study the nuclear structure of radioactive tellurium isotopes; Ionisation resonante par faisceaux laser: application aux sources d'ions et a l'etude de la structure des noyaux radioactifs de tellure

    Energy Technology Data Exchange (ETDEWEB)

    Sifi, R

    2007-07-15

    The radioactive ion beams that are produced through current isotope separators are well separated according to the A mass but not according to the Z parameter. The resonant ionization through laser beams applied to ion sources allows the production of radioactive ion beam in a very selective and efficient way by eliminating the isobaric contamination. The first chapter is dedicated to the resonant ionization by laser beams, we describe the principle, the experimental setting, the lasers used, the ionization schemes and the domain of application. The second chapter deals with the application of resonant ionization to laser ion sources for the production of radioactive ion beams. We present experimental tests performed for getting copper ion beams. Resonant ionization through laser is also used in the spectroscopy experiments performed at the Isolde (isotope separation on-line device) installation in CERN where more than 20 elements are ionized very efficiently. The technique is based on a frequency scanning around the excitation transition of the atoms in order to probe the hyperfine structure. Laser spectroscopy allows the determination of the hyperfine structure as well as the isotopic shift of atoms. In the third chapter the method is applied to the spectroscopy of tellurium atoms. First, we define the 2 parameters on which the extraction is based: charge radius and nuclear moments, then we present several theoretical models that we have used to assess our experimental results. (A.C.)

  14. Cancer mortality and incidence survey around the Aube's low- and medium-activity radioactive waste storage site; Etude de mortalite et d'incidence des cancers autour du site de stockage de dechets radioactifs de faible et de moyenne activite de l'Aube

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-07-01

    This report presents the main results of a survey performed in 2010 to describe the health status of the population around the Aube's low- and medium-activity radioactive waste storage site. The aim of this survey was to determine whether the frequencies of death and hospitalization on account of cancer are different for this population (15 km around the site) with respect to two reference populations (the population of the Champagne-Ardennes region and the French metropolitan population). Results of mortality, hospitalization, and lung cancer are presented under the form of maps and tables giving global data or data for males, females, adults, or children

  15. Nuclear wastes management: the lessons from the C.S.M. disposal site (Centre de Stockage de la Manche). Memory-less Centre, Future-less Centre?; Gestion des dechets radioactifs: les lecons du Centre de Stockage de la Manche (C.S.M.). Centre Sans Memoire, Centre Sans Avenir?

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-05-15

    With its 527 217 m{sup 3} of low and medium activity wastes put in storage between 1969 and 1994, the C.S.M.( center of storage of Manche) is and remains to this day a necessary element to understand the problems posed by the eternal storage of nuclear materials and the limits of the notion of reversibility. There are therefore teachings to be drawn. We cannot repeat past mistakes in particular with high activity wastes which we wish to bury deep underground. This report is based on the analysis of the existing bibliography, of the internal A.N.D.R.A. documents which we released to the public, of the lessons drawn from our participation in the official concerting and work groups, and finally of the data obtained after inquiries were done in the region in the framework of R.I.V.I.E;R.E. (citizens network of radioecological surveillance, information and evaluation). In spite of all efforts produced, many questions remain unanswered regarding this site so it is sometimes difficult to be more precise. (N.C.)

  16. Preliminary experiments on the use of radioactive indicators in macromolecular chemistry; Experiences preliminaires sur l'utilisation des indicateurs radioactifs en chimie macromoleculaire; Predvaritel'nye opyty ispol'zovaniya radioaktivnykh indikatorov v makromolekulyarnoj khimii; Ensayos preliminares sobre el empleo de indicadores radiactivos en quimica macromolecular

    Energy Technology Data Exchange (ETDEWEB)

    De Brouckere, L; Van Leemput, R; Stein, R [Laboratoire de Chimie Generale II, Universite Libre de Bruxelles (Belgium)

    1962-03-15

    In studies of osmotic phenomena with high polymers, two causes of error are particularly important: (a) Diffusion of low-molecular-weight polymers across the membrane; (b) Polymer adsorption on the membrane. For investigations on both these phenomena radiotracer methods present decisive advantages over the classical and far less sensitive gravimetric procedures. The polymer used in the authors' experiments was a hetero-disperse sample of (poly) chloro-butyl acrylate which was ionically chlorinated with Cl{sup 36} starting from a sample of (poly)butyl acrylate. This polymer was dissolved in acetone. Diffusion chambers similar to twin-cell osmometers were set up. Cellophane membranes with permeabilities of 6.7 x 10{sup -5} h{sup -1} to 30.6 x 10{sup -5} h{sup -1} separated the solution from the solvent. It was found that: (a) With our apparatus, about two hundred hours were necessary to reach an equilibrium or steady state in diffusion experiments; (b) The fraction of polymer diffusing through the membrane in a given time was independent of the concentration; (c) The amount of polymer diffusing was related to the permeability of the membrane; (d) A practically irreversible adsorption of polymer on the membrane was observed (30 to 40 {mu}g/cm{sup 2}). (author) [French] Dans les etudes sur les phenomenes osmotiques avec de hauts polymeres, deux causes d'erreurs sont particulierement importants : a) La diffusion des polymeres de faible poids moleculaire a travers la membrane; b) L'adsorption des polymeres sur la membrane. Pour les recherches sur ces deux phenomenes, la methode des radiotraceurs presente des avantages decisifs par rapport aux procedes gravi metriques classiques, beaucoup moins sensibles. Le polymere utilise dans les experiences des auteurs etait un echantillon a dispersion heterogene acrylate de (poly) chloro-butyle, obtenu par chlorruation ionique d'un echantillon d'acrylate de (poly)butyle avec du chlore-36. Ce polymere etait dissous dans de l'acetone. On a utilise des chambres de diffusion analogues aux osmometres a cellules jumelles. Des membranes de cellophane de permeabilite 6,7 {center_dot} 10{sup -5} h{sup -1} a 30,6 {center_dot} 10{sup -5} h{sup -1} separaient la solution du solvant. On a constate: a) Qu'avec l'appareil utilise dans les experiences de diffusion, il fallait environ deux cents heures pour atteindre un etat d'equilibre ou un etat stationnaire; b) Que la fraction de polymere se diffusant a travers la membrane dans un temps donne etait independante de la concentration; c) Que la quantite de polymere diffuse variait en fonction de la permeabilite de la membrane; d) Qu'il se produisait une adsorption pratiquement irreversible du polymere sur la membrane (30 a 40 {mu}g/cm{sup 2}). (author) [Spanish] Las dos principales fuentes de error cuando se estudian fenomenos osmoticos con polimeros de elevado peso molecular son: a) la difusion de polimeros de bajo peso molecular a traves de la membrana; b) la adsorcion de polimeros en la membrana. Los metodos que emplean trazadores radiactivos para la investigacion de estos dos fenomenos ofrecen ventajas decisivas sobre los procedimientos gravimetricos clasicos, que son mucho menos sensibles. El polimero empleado por los autores consistio en una muestra heterodispersa de policloroacrilato de butilo obtenido por el oracion ionica del poliacrilato de butilo con {sup 36}Cl. Este polimero se utilizo disuelto en acetona. Los autores emplearon camaras de difusion, semejantes a osmomotros de celulas gemelas. La solucion quedaba separada del disolvente por membranas de celofan de permeabilidades de 6,7 x 10{sup -5} h{sup -1} a 30,6 x 10{sup -5} h{sup -1}. Han llegado a las conclusiones siguientes: a) con el aparato empleado en los experimentos de difusion, se precisan unas 200 horas para alcanzar un estado de equilibrio o un regimen estacionario; b) la fraccion de polimero que difunde a traves de la membrana en un tiempo determinado es independiente de la concentracion; c) la cantidad de polimero que se difunde depende de la permeabilidad de la membrana; d) se observa una adsorcion practicamente irreversible del polimero en la membrana (30 a 40 {mu}g cm{sup 2}). (author) [Russian] Pri izuchenii osmoticheskikh yavlenij s ispol'zovaniem vysokikh polimerov osoboe znachenie predstavlyayut dve prichiny oshibok: a) diffuziya nizkomolekulyarnykh polimerov cherez membranu; b) adsorbtsiya polimera na membrane. Dlya issledovaniya oboikh ehtikh yavlenij metod radioaktivnykh indikatorov predstavlyaet nesomnennye preimushchestva nad obychnymi i gorazdo menee chuvstvitel'nymi vesovymi metodami. V provedennykh avtorami doklada opytakh byl ispol'zovan geterodispersnyj obrazets polimera (poli)-khlorobutilakrilata, kotoryj byl khlorirovan s pomoshch'yu Cl{sup 36} posredstvom ionizatsii, iskhodya iz obraztsa (poli)-butilakrilata. Ehtot polimer rastvo- ryaetsya v atsetone. Byli postroeny diffuzionnye kamery, analogichnye dvuyacheechnym osmometram. Rastvor otdelyalsya ot rastvoritelya tselofanovymi membranami, obrabotannymi tak, chtoby davat' pronitsaemost' ot 6,7 x 10{sup -5} ch{sup -1} do 30,6 x 10{sup -5} ch{sup -1} Bylo najdeno, chto: a) s nashim oborudovaniem ponadobilos' okolo 200 chasov dlya togo, chtoby v opytakh diffuzii dostich' ravnovesiya ili ustojchivogo sostoyaniya; b) dolya polimera, diffundiruyushchaya cherez membranu v opredelennyj promezhutok vremeni, ne zavisit ot kontsentratsii; c) kolichestvo diffundiruyushchego polimera zavisit ot pronitsaemosti membrany; d) nablyudalas' pochti neobratimaya adsorbtsiya polimera na membrane (30-40 {mu}g/cm{sup 2}). (author)

  17. The IRSN publishes an assessment of doses received in Japan by external irradiation due to radioactive deposits caused by the Fukushima-Daiichi power plant accident; L'IRSN publie une estimation des doses recues au Japon par irradiation externe due aux depots radioactifs provoques par l'accident de la centrale de Fukushima-Daiichi

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This document first describes how dry and wet radioactive deposits are formed. It also indicates their main components: iodine 131 and 132, caesium 134, 136 and 137, tellurium 132, and barium 140. It describes the different exposure ways due to radioactive deposits in the environment. A map indicates dose level assessments few tens of kilometres around the Fukushima power plant. A brief comment of this map is proposed

  18. Coupling between corrosion and biphasic transport in porous media: Application to the evolution of a radioactive wastes disposal; Couplage entre corrosion et comportement diphasique dans un milieu poreux: Application a l'evolution d'un stockage des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Dridi, W

    2005-04-15

    In the actual concepts of geological disposal, high level radioactive wastes are packed in metallic containers surrounded by a partially or totally saturated clay media. In contact with the interstitial water, anoxic corrosion of this container will start producing hydrogen. In the scope of safety assessment, the present study deals with two main topics: prediction of the long-term corrosion of carbon steel with respect to clay water content and evaluation of the risk of damage of the clay barrier related to gas production. Elementary processes controlling the kinetics of corrosion are limited to oxide growth and mass transfer through the porosity of this film. Thanks to a macroscopic description of theses processes, followed by an interfacial kinetic law, a mechanistic modeling of the anoxic corrosion in partially saturated porous media is proposed. This approach is validated when confronted to the long-term corrosion tests performed in saturated clay. Both modeling and laboratory experiments have confirmed that kinetics of anoxic corrosion in partially saturated clay is mainly controlled by the surrounding relative humidity as in the case of aerated or atmospheric corrosion. In the gas generation topic, some numerical simulations are performed concerning the oedometric and triaxial test dealing with gas migration in saturated clay. Finally, long-term calculations are conducted concerning hydro-mechanical impact of corrosion in deep geological repositories. Due to a more realistic prediction of the long-term corrosion, the risks of gas overpressures, local desaturation and mechanical damage are reduced. (author)

  19. Presentation of the program law of the 28 June 2006 relative to the sustainable management of radioactive materials and wastes; Presentation de la loi de programme du 28 juin 2006 relative a la gestion durable des matieres et des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    The french law of 1991, decided to define management solutions in the radioactive wastes management policy, is now over. The results of researches led to the promulgation of a new planing act, the law of the 28 June 2006. This law concerns the sustainable management of radioactive materials and wastes. It takes also in account a public debate, organized in September 2005 by the National Commission for Public Debate. The Law project architecture can be described in three main points: the implementing of a national policy of radioactive materials and wastes, a better transparency and democratic control and the implementing of specific modalities for the organization and the financing of spent fuels and radioactive wastes management. The law sets 2015 as deadline to submit the statutory application in order to commission a deep geological repository for high-level and long-lived radioactive wastes. (A.L.B.)

  20. Study and development of a method allowing the identification of actinides inside nuclear waste packages, by active neutron or photon interrogation and delayed gamma-ray spectrometry; Etude et developpement d'une technique de dosage des actinides dans les colis de dechets radioactifs par interrogation photonique ou neutronique active et spectrometrie des gamma retardes

    Energy Technology Data Exchange (ETDEWEB)

    Carrel, F

    2007-10-15

    An accurate estimation of the alpha-activity of a nuclear waste package is necessary to select the best mode of storage. The main purpose of this work is to develop a non-destructive active method, based on the fission process and allowing the identification of actinides ({sup 235}U, {sup 238}U, {sup 239}Pu). These three elements are the main alpha emitters contained inside a package. Our technique is based on the detection of delayed gammas emitted by fission products. These latter are created by irradiation with the help of a neutron or photon beam. Performances of this method have been investigated after an Active Photon or Neutron Interrogation (INA or IPA). Three main objectives were fixed in the framework of this thesis. First, we measured many yields of photofission products to compensate the lack of data in the literature. Then, we studied experimental performances of this method to identify a given actinide ({sup 239}Pu in fission, {sup 235}U in photofission) present in an irradiated mixture. Finally, we assessed the application of this technique on different mock-up packages for both types of interrogation (118 l mock-up package containing EVA in fission, 220 l mock-up package with a wall of concrete in photofission). (author)

  1. Review of the seismic risk in the design of civil engineering of nuclear installations excepted the long term storage of radioactive wastes; Prise en compte du risque sismique a la conception des ouvrages de genie civil d'installations nucleaires de base a l'exception des stockages a long terme des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    This guide aims to define, for the nuclear installations excepted the long term storage of radioactive wastes, from site data, the design specifications of earthquake resistant civil engineering and the possible methods for: the determination of the seismic response of the buildings, taking into account the interactions with the materials and the evaluation of the associated strains to size the installation; the determination of seismic displacements to be considered to size the materials. (A.L.B.)

  2. Lethal Effect on Bacterium of Decay of Incorporated Radioactive Atoms ({sup 3}H, {sup 14}C, {sup 32}P); Effet Letal de la Desintegration d'Atomes Radioactifs ({sup 3}H, {sup 14}C, {sup 32}P) Incorpores dans une Bacterie

    Energy Technology Data Exchange (ETDEWEB)

    Apelgot, Sonia [Laboratoire Curie, Institut du Radium, Paris (France)

    1968-06-15

    The biological effect of decay of {sup 3}H, {sup 14}C and {sup 32}P incorporated into a bacterium depends on the nature of the organic molecule labelled, on the position of the isotope within it and on the isotope itself. In sum, results obtained to date show that: The decay of {sup 3}H atoms incorporated into certain macromolecules of a bacterium causes sterilization through ionization by the ss{sup -} particle emitted; transmutation is of negligible importance. This self-irradiation is comparable in effect with X-rays and is affected in a similar manner by the same factors: temperature, presence of a radioprotector, radiosensitivity of the strain. Decay of {sup 14}C or {sup 32}P atoms incorporated into bacterial DNA is lethal because of the transmutation effect; ionizations produced by emitted ss{sup -} particles may be disregarded. Survival curves for {sup 32}P transmutations depend on the experimental conditions. Some of the results obtained with {sup 32}P are similar to those obtained with X-rays, e.g. effects of temperature, radical capture and oxygen, while others are similar to those of u.v. light, e.g., effect of growth conditions. Comparative tests made with {sup 32}P indicate that the recoil energy of transmutation is not the phenomenon responsible for the lethal effect observed. Comparison of the results obtained after X-irradiation or decay of {sup 3}H or {sup 32}P incorporated into the DNA of bacteria of the same strain of E. coli shows that the efficiency of a {sup 32}P transmutation is about four times greater than that of an ionization produced at random within the same DNA. (author) [French] L'effet biologique de la desintegration de {sup 3}H, {sup 14}C et {sup 32}P incorpores dans une bacterie depend de la nature de la molecule organique marquee, de l'emplacement de l'isotope sur celle-ci et de la nature de l'isotope lui-meme. L'ensemble des resultats obtenus a ce jour montre que la desintegration des atomes de {sup 3}H incorpores dans certaines macromolecules d'une bacterie provoque sa sterilisation par les ionisations produites par la particule {beta}{sup -} emise; la transmutation ne joue qu'un role negligeable. Cette auto-irradiation est du meme ordre qu'une irradiation X. Elle est influencee d'une facon comparable par les memes facteurs: temperature, radioprotecteur, radiosensibilite des souches. La desintegration des atomes de {sup 14}C ou de {sup 32}P incorpores dans un ADN bacterien est letale par l'effet de la transmutation; les ionisations produites par les particules {beta}{sup -} emises ne jouent qu'un tole negligeable. Les courbes de survie aux transmutations de {sup 32}P dependent des conditions experimentales. Certains des resultats obtenus avec le {sup 32}P se rapprochent d'une irradiation X: action de la temperature, des capteurs de radicaux, de l'oxygene; d'autres rappellent ceux d'une irradiation UV : influencedesconditionsdecroissance. Les experiences de comparaison faites avec le {sup 32}P permettent de dire que l'energie de recul de la transmutation n'est pas le phenomene responsable de l'effet letal observe. La comparaison des resultats obtenus apres irradiation X ou desintegration des atomes de {sup 3}H ou de {sup 32}P incorpores dans l'ADN de bacteries d'une meme souche E. coli indique que l'efficacite d'une transmutation de {sup 32}P est environ quatre fois plus grande que celle d'une ionisation produite au hasard dans ce meme ADN. (author)

  3. Metabolism of fission products in man: Marshallese experience; Metabolisme des produits de fission radioactifs chez l'homme: donnees recueillies aux iles Marshall; Metabolizm radioaktivnykh produktov deleniya v organizme cheloveka. (dannye obsledovaniya zhite- lej marshal'skikh ostrovov); Metabolismo de productos de fision radiactivos en el hombre: datos obtenidos en los habitantes de las islas Marshall

    Energy Technology Data Exchange (ETDEWEB)

    Cohn, S. H. [Brookhaven National Laboratory, Upton, Long Island, NY (United States)

    1963-02-15

    The medical study of the Marshallese accidentally exposed to local fall-out in 1954 is unique in that; along with he Japanese fishermen study, it provides the only data existing on the metabolism of mixed fission products in a human population. Early diagnosis of the internal radioactive contamination was made by radiochemical analysis of the excreta of the exposed people and by radiochemical analysis of the tissues of animals simultaneously exposed. Initially, Sr{sup 89}, Ba{sup 140}, I{sup 131} and its shorter-lived daughters and a number of rare-earth elements contributed the major portion of the internal radiation dose. After a year, the principal radioisotopes were Sr{sup 90}, Cs{sup 137} and Zn{sup 65}. Subsequently these radionuclides and more recently, Co{sup 60}, have been measured periodically. Since 1958, the {gamma}-spectra of a number of Marshallese have been obtained with a portable whole-body counter. The report discusses the findings of these studies for the past eight years. The results of an early attempt o alter the rate of removal of the mixed fission products in the Marshallese with calcium disodium EDTA are presented. The metabolism of die radionuclides and their relationship to levels present in the environment is also discussed. (author) [French] L'enquete medicale a laquelle ont ete soumis les habitants des iles Marshall qui, en 1954, ont ete exposes accidentellement a des retombees locales presente un caractere unique en ce sens que, tout comme l'enquete sur les pecheurs japonais, elle fournit les seules donnees que l'on possede sur le metabolisme d'un melange de produits de fission chez l'homme. Un premier diagnostic de la contamination radioactive interne a ete fait par analyse radiochimique des excreta des sujets exposes et par analyse radiochimique des tissus des animaux exposes simultanement. Au debut, {sup 89}Sr, {sup 140}Ba, {sup 131}I et leurs produits de filiation de courte periode,ainsi qu'un certain nombre de terres rares, produisaient la majeure partie de la dose de rayonnements internes. Apres une annee, les principaux radioisotopes etaient {sup 90}Sr, {sup 137}Cs y {sup 65}Zn. Par la suite, on a mesure periodiquement ces radionucleides et, plus recemment, {sup 60}Co. Depuis 1958, on a pu obtenir, i l'aide d'un appareil portatif de dosage del'activite du corps humain, les spectres gamma d'un certain nombre d'habitants des iles Marshall. L'auteur etudie les resultats de ces enquetes, obtenus au cours des huit dernieres annees. Il presente egalement les resultats d'une tentative faite au debutpour modifier la vitesse d'elimination des produits de fission mixtes chez les autochtones au moyen d'un sel double de calcium et de sodium de l'EDTA. Il etudie enfin le metabolisme des radionucleides et leurs rapports avec les concentrations presentes dans le milieu ambiant. (author) [Spanish] El estudio clinico de los habitantes de las islas Marshall que en 1954 quedaron expuestos accidentalmente a precipitaciones radiactivas posee gran valor cientifico porque, junto con el caso de los pescadores japoneses, constituye la unica fuente de datos sobre el metabolismo de mezclas de productos de fision en el hombre. Al principio, el diagnostico de la contaminacion radiactiva interna se efectuo por analisis radioquimico de los tejidos de animales expuestos simultaneamente. Se encontro que la mayor parte de la dosis de radiacion interna se debia al {sup 89}Sr, {sup 140}Ba, {sup 131}I y sus descendientes de periodo breve, asi como a algunos de los elementos de las tierras raras. Al cabo de un alio,los principales radioisotopos presentes eran el {sup 90}Sr, {sup 137}Cs y {sup 65}Zn. Despues se siguieron midiendo periodicamente estos radionuclidos y, mas recientemente, el {sup 60}Co. Desde 1958, se han obtenido los espectros y de un cierto numero de pobladores de aquellas islas por recuento del organismo entero con un aparato portatil. El informe discute los datos que durante los ultimos ocho anos se han obtenido gracias a estos estudios. Presenta los resultados de un tratamiento con la sal calcico-disodica del EDTA, que se efectuo poco despues de la contaminacion con el proposito de modificar la velocidad de eliminacion de las mezclas de productos de fision en los habitantes de las islas Marshall. Tambien discute el metabolismo de los radionuclidos y su relacion con la radiactividad ambiente en aquella zona. (author) [Russian] Meditsinskoe'obsledovanie zhitelej Marshal'skikh ostrovov, sluchajno podvergshikhsya dejstviyu mestnykh radioaktivnykh osadkov v 1954 godu, yavlyaetsya unikal'nym v tom smysle, chto ono, naryadu s obsledovaniem yaponskikh rybakov, daet vozmozhnost' poluchit' edinstvennye v ehtoj oblasti dannye po metabolizmu smeshannykh produktov deleniya v organizmakh lyudej. Rannyaya diagnostika vnutrennego radioaktivnogo zarazheniya osushchestvlyalas' s pomoshch'yu radiokhimicheskogo analiza vydelenij obluchennykh lyudej i metodami radiokhimicheskogo analiza tkanej zhivotnykh obluchennykh odno-vremenno. Na nachal'noj stadii bol'shuyu chast' vnutrennej dozy radiatsii sostavlyali strontsij-89, barij-140, jod-131, ikh bolee korotkozhivushchie dochernie produkty i ryad redkozemel'nykh ehlementov. Cherez god osnovnymi radioizotopami byli strontsij-90, tsezij-137 i tsink-65. Pozdnee periodi- cheski izmeryalas' aktivnost' ehtikh radioizotopov, a eshche pozdnee i kobal'ta-60. Nachinaya s 1958 goda gamma-spektry u zhitelej Marshal'skikh ostrovov poluchayut s pomoshch'yu portativnogo schetchika dlya izmereniya aktivnosti vsego tela. V doklade obsuzhdayutsya dannye ehtikh issledovanij za prshedshie vosem' let. Privodyatsya rezul'taty rannikh popytok izmenit' skorost' udaleniya smeshannykh produktov deleniya iz organizma s pomoshch'yu dvunatrievogo kal'tsiya EDTA. Obsuzhdaetsya takzhe metabolizm radioizotopov i svyaz'ikh s urovnyami v okruzhayushchej srede. (author)

  4. Modelling of thermo-hydro-mechanical couplings and damage of viscoplastic rocks in the context of radioactive waste storage; Modelisation des couplages thermo-hydro-mecaniques et de l'endommagement des roches viscoplastiques dans le contexte du stockage de dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Kharkhour, H

    2002-12-01

    Trying to develop a model taking into account the complex rheology of a geologic media characterized by visco-plasticity, damage and thermo-hydro-mechanical couplings is unusual in geotechnics. This is not the case for radioactive waste storage that presents specificities from several viewpoints. Indeed, the scales of time and space concerned by this type of storage are disproportionate to those of civil engineering works or mines. Another specificity of the radioactive waste storage lies in the coupled processes involved. No effect likely to compromise the long-term security of the storage could be ignored. For example this is the case of damage, a phenomenon which does not necessarily lead to a major change of the mechanical behavior of the works but can influence the permeability of the medium in relation with a migration of radionuclides. It can be conceived that this phenomenon finds all its importance in the context of the thermo-hydro-mechanical couplings of a waste storage with high activity. However, the interaction between the damage and the THM coupled processes was the object of very few research subject up to now. This. is even more true for viscoplastic media considered as ductile, and therefore, less prone to cracking than brittle media. It is exactly in this 'original' but difficult context that took place the research presented in this report. This study was dedicated to the analysis of the phenomena and the thermal, hydraulic and mechanical couplings occurring in the near and far field of a high activity radioactive waste storage. Two examples of geological media were considered in this report: the clayey rock of Callovo-Oxfordian, called ' Argilites de l'Est ', target rock of the ANDRA project to carry out a subterranean laboratory for the study of long life radioactive waste storage; and the salt rock of the. subterranean laboratory in the old salt mine of Asse in Germany. (author)

  5. Case series

    African Journals Online (AJOL)

    abp

    6 mai 2016 ... during the anatomopathological exam, giving us a 3.38% prevalence. The average age of ... basedowifié, et 1 cas de maladie de basedow. L'âge moyen des ... papillaire. Un traitement par l'iode radioactif a été indiqué chez 5.

  6. The use of 65Zn in the study of Heliothis armigera larva's behavior on tomatoes

    International Nuclear Information System (INIS)

    Saour, George.

    1987-01-01

    Short communication. A summary of a DEA report submitted under the title ''Etude au moyen du Zinc Radioactif 65 Zn du comportement des chenilles d'Heliothis armigera hubner (Lepidoptera, Noctuidae) sur Tomate.'' Univ. de Droit d'Economie et des Sciences d'Aix-Marseille-III. Faculte des Sciences et Techniques de Saint-Jerome. INRA-MONTEAVET, Station de Zoologie

  7. Study of the irradiation given by cylindrical drums containing radioactive sludges; Etude de l'irradiation a proximite d'un fut cylindrique de stockage de boues radioactives

    Energy Technology Data Exchange (ETDEWEB)

    Bourdrez, J.

    1960-05-13

    Some data on shielding are presented concerning irradiation given by drums containing radioactive sludge (fission products). (author) [French] Sont exposes differents resultats de calculs de protection relatifs a l'intensite d'irradiation γ donnee par un fut rempli de boues de produits de fission radioactifs. (auteur)

  8. The Treatment of Cancer by a Radioactive Drug: Tritium-Labelled Tetra-Sodium 2-Methyl-1:4-Naphthaquinol Diphosphate; Traitement du Cancer par un Remede Radioactif: Le Diphosphate Tetrasodique de Methyl-2 Naphtoquinone-1,4 Tritie; 041b 0435 0447 0435 043d 0414 ; Tratamiento del Cancer con la Sal Tetrasodica del Acido 2-Metil-1,4-Naftoquinon Difosforico Marcada con Tritio

    Energy Technology Data Exchange (ETDEWEB)

    Marrian, D. H.; Marshall, Barbara; Mitchell, J. S.; Simon-Reuss, I. [Department of Radiotherapeutics, University of Cambridge, Cambridge (United Kingdom)

    1962-02-15

    The action of tetra-sodium 2-methyl-1: 4-naphthaquinoI diphosphate (''Synkavit''-Roche Products) as a radiosensitizer will be reviewed together with earlier methods of labelling this and similar molecules. The synthesis of this compound labelled with tritium has been accomplished so as to yield a radiochemically pure drug of specific activity 28 c/mmole (1 atom of tritium/molecule). It will be shown that this compound enters the living cell very rapidly both in-vivo and in-vitro and that cultures of malignant cells incorporate the label to a much greater extent than cultures of normal cells under identical conditions. Preliminary investigations on the use of this drug on patients with advanced, and often otherwise, refractory, malignant conditions will be described; uptake by the bone marrow is less than by the tumour, sometimes by a factor of 5. (author) [French] Les auteurs examinent l'action du diphosphate tetrasodique de methyl-2- naphtoquinone-1,4 ('Synkavit'-Produits Roche) comme radiosensibilisateur, ainsi que les methodes plus anciennes de marquage de ces molecules et de molecules analogues. On a fait la synthese de ce compose marque au tritium, de facon a obtenir un produit pharmaceutique radiochimiquement pur, dont l'activite specifique est de 28 curies par millimole (1 atome de tritium par molecule). Les auteurs demontrent que ce compose penetre tres rapidement dans la cellule vivante, tant in vivo qu'in vitro, et que les cultures de cellules malignes fixent l'indicateur dans une mesure beaucoup plus large que ne le feront les cellules normales dans les memes conditions. Les auteurs exposent les resultats de recherches preliminaires sur l'emploi de ce remede pour soigner des malades atteints de tumeurs malignes avancees et souvent refractaires a tout autre traitement. L'absorption par la moelle osseuse est inferieure, parfois de 5 fois, a l'absorption par la tumeur. (author) [Spanish] Los autores describen la accion radiosensibilizadora de la sal tetrasodica del acido 2-metil-l,4-naftoquinon-difosforico (''Synkavit'' Roche), asi como algunos de los metodos que se han empleado para marcar este y otros compuestos analogos. Sintetizaron el compuesto tritiado en forma de obtener una substancia radioquimicamente pura de 28 c/mmol (1 atomo de tritio por molecula) de actividad especifica. Demuestran que este producto penetra muy rapidamente en las celulas vivas, tanto in vivo como in vitro y que, en igualdad de condiciones los cultivos de celulas malignas incorporan en grado mucho mayor el compuesto marcado que los cultivos de celulas normales. Describen las investigaciones preliminares del empleo clinico de ese producto en casos avanzados de tumores malignos que suelen ser refractarios a otros tratamientos, observandose que la medula osea absorbe menor cantidad del compuesto que el tumor (en algunas ocasiones, hasta cinco veces menos). (author) [Russian] Dejstvie tetrasoda - 2-metil-1: 4- naftagidrohinondifosfata (Sinkavit - proizvodstvo Roshe) v kachestve radio- senitajzera obsuzhdaetsja narjadu s bolee rannimi metodami mechenija jetih i podob- nyh molekul. Sintez jetogo soedinenija, mechennogo tritiem, byl sdelan dlja togo, chtoby polu- chit' radiohimicheskoe chistoe lekarstvo s udel'noj aktivnost'ju v 28 kjuri/mil- limol' (odin atom tritija na molekulu). Budet pokazano, chto jeto soedinenie bystro vhodit v zhivuju kletku kak v este- stvennyh, tak i i laboratornyh uslovijah i chto kul'tury zlokachestvennyh kletok pogloshhajut mechenye atomy v gorazdo bol'shem ob{sup e}me, chem kul'tury normal'nyh kletok pri teh zhe uslovijah. Budut opisany predvaritel'nye issledovanija primenenija jetogo lekarstva na pacientah, imejushhih zlokachestvennye opuholi i nahodjashhihsja v tjazhelom ili neizlechimom sostojanii; usvoenie kostnym na kojefficient 5 mozgom nizhe, chem usvoenie opuhol'ju. (author)

  9. Report realized by the commission of the economical Affairs on the law project, adopted by the National Assembly after urgency declaration, of the program relative to the sustainable management of the radioactive materials and wastes; Rapport fait au nom de la commission des Affaires economiques sur le projet de loi, adopte par l'Assemblee Nationale apres declaration d'urgence, de programme relatif a la gestion durable des matieres et des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Revol, H

    2006-07-01

    In the framework of a sustainable development and of the nuclear energy development, the France decided by the law of the 30 December 1991, to study three axis or researches: the radioactive wastes transmutation, their deep underground disposal and their storage during ten years. Today, after evaluation of the researches results a law project on the sustainable management of the radioactive materials and wastes, has been prepared. This document is the approval of the law project and presents some amendments. (A.L.B.)

  10. National assessment board for research and the studies into the management of radioactive waste and materials instituted by the law no.2006-739 of June 28, 2006 - Assessment report No. 5; Commission nationale d'evaluation des recherches et etudes relatives a la gestion des matieres et des dechets radioactifs instituee par la loi no. 2006-739 du 28 juin 2006 - Rapport d'evaluation No. 5

    Energy Technology Data Exchange (ETDEWEB)

    Duplessy, Jean-Claude; Baechler, Jean; Berest, Pierre; Brechet, Yves; Deconinck, Frank; Laurent, Maurice; Ledoux, Emmanuel; Leroy, Maurice; Percebois, Jacques; Roure, Francois; Thegerstroem, Claes; Kerboul, Claire; Tissot, Bernard; Jouvance, Chantal; Ledoux, Florence

    2011-11-15

    The law provides that long-term management of long-lived, high-level waste comprises two aspects, which are not mutually exclusive: the partitioning and transmutation of the actinides present in spent fuel from nuclear reactors, and the geological disposal of long-lived high- and intermediate-level waste. This report is organised to reflect the two complementary aspects of R and D on the management of radioactive waste and materials: partitioning and transmutation (chapter 1), and the storage and disposal of LLHL and LLIL waste (chapter 2). In 2011 the Board decided to go into detail on the subject of the potential impact of transmutation of actinides on the disposal of the waste produced in the future, in a set of reactors suitable for multi-recycling. This question is dealt with in two chapters of the report. The Board continues to observe the overall international situation (chapter 3), and this year devoted an entire hearing to the different visions of the nuclear cycle held throughout the world. This hearing took place a few weeks before the accident in Fukushima. Contents: Chapter 1 - Partitioning and transmutation: scientific and technical context; transmutation and multi-recycling (Three important actinides potentially concerned by transmutation: Plutonium, Americium, Curium; Transmutation rate); demonstration tools; scenarios; ASTRID prototype (Core, Cooling and conversion, Designs and materials for Astrid); Reprocessing and fabrication of fuel (Experience and lessons learned; Pilot reprocessing facility for Astrid); transmutation in ADS; transmutation and disposal (Radiotoxicity of the inventory; Residual thermal power in LLHL waste); other scenarios; conclusion; Chapter 2 - disposal and storage: introduction; inventory; ZIRA (Contributions of the new 3D geophysics campaign; Knowledge of lithostratigraphic variations in the Callovo-Oxfordian layer; Knowledge of regional and local hydrogeology; Hydrogeological modelling situation); ZIIS - Integration of the structures in the surrounding land and the environment: Safety and security constraints; Environmental constraints; Reversibility constraints; Advantages and disadvantages of connecting the bottom to the surface via an inclined drift; moving towards the creation of a geological disposal site: the industrial centre for geological disposal (CIGEO): Brief analysis of the STI project; Design of the Cigeo project draft phase; Development of the Cigeo project; scientific work (Thermodynamics: Thermal disturbances; Thermal experimentation; Thermodynamics and transmutation; Conclusion); Geomechanics: Excavation-Damaged Zone (EDZ): safety issues; Tests conducted in the LLHL waste cavities; Sealing; Geomechanical modelling and conclusions; Underground laboratory experiments: Experiments in the Meuse/Haute-Marne underground laboratory; Experiments aimed at characterising the near field; Experiments aimed at characterising the far field); reversibility (Introduction; Circumstances that may lead to retrieval; Changes in the cavities and packages during the reversibility period; Reversibility and storage; Reversibility exercises; Conclusions); memory of the site; Chapter 3 - international overview: different options for managing LL, IL and HL waste; international legal context; research laboratories and underground disposal facilities; sources of fast irradiation; R and D on ADS; R and D on deep geological disposal (Performance levels of the disposal facility; Environmental impact of the disposal facility; Governance and participation of stakeholders); new technologies for partitioning and transmutation (R and D on partitioning and transmutation; Nuclear databases; Economic and geopolitical aspects); education, training and knowledge management; Appendices: members of the national assessment board - November 2011; bodies heard by CNE2; list of documents provided to the board

  11. Dry corrosion prediction of radioactive waste containers in long term interim storage: mechanisms of low temperature oxidation of pure iron and numerical simulation of an oxide scale growth; Prevision de la corrosion seche des conteneurs de dechets radioactifs en condition d'entreposage: etude des mecanismes d'oxydation du fer a basse temperature et simulation numerique de la croissance d'une couche d'oxyde

    Energy Technology Data Exchange (ETDEWEB)

    Bertrand, N

    2006-10-15

    In the framework of research on long term behaviour of radioactive waste containers, this work consists on the one hand in the study of low temperature oxidation of iron and on the other hand in the development of a numerical model of oxide scale growth. Isothermal oxidation experiments are performed on pure iron at 300 and 400 C in dry and humid air at atmospheric pressure. Oxide scales formed in these conditions are characterized. They are composed of a duplex magnetite scale under a thin hematite scale. The inner layer of the duplex scale is thinner than the outer one. Both are composed of columnar grains, that are smaller in the inner part. The outer hematite layer is made of very small equiaxed grains. Markers and tracers experiments show that a part of the scale grows at metal/oxide interface thanks to short-circuits diffusion of oxygen. A model for iron oxide scale growth at low temperature is then deduced. Besides this experimental study, the numerical model EKINOX (Estimation Kinetics Oxidation) is developed. It allows to simulate the growth of an oxide scale controlled by mixed mechanisms, such as anionic and cationic vacancies diffusion through the scale, as well as metal transfer at metal/oxide interface. It is based on the calculation of concentration profiles of chemical species and also point defects in the oxide scale and in the substrate. This numerical model does not use the classical quasi-steady-state approximation and calculates the future of cationic vacancies at metal/oxide interface. Indeed, these point defects can either be eliminated by interface motion or injected in the substrate, where they can be annihilated, considering sinks as the climb of dislocations. Hence, the influence of substrate cold-work can be investigated. The EKINOX model is validated in the conditions of Wagner's theory and is confronted with experimental results by its application to the case of high temperature oxidation of nickel. (author)

  12. Research strategy and programmes on the management of long-lived high-level radioactive waste (pursuant to article L542 of the environmental code taken from the law of December 30, 1991); Strategie et programmes des recherches sur la gestion des dechets radioactifs a haute activite et a vie longue (au titre de l'article L542 du code de l'environnement, issu de la loi du 30 decembre 1991)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-01

    This report is made of two parts: the first part is a status report which highlights the main achievements of all research activities conducted in 2001 in the global context of national and international efforts on nuclear waste management (partitioning and transmutation, disposal in deep geological formations, conditioning and storage, national and international collaborations, report no 7 of the national review board (CNE), the Global 201 conference and the year 2001 highlights). The second part is the executive summary of the 2002 edition of the 'Research strategy and programmes' document. The new edition has ben reorganized according to previous editions in an effort to make it more concise, clearer and more comprehensive. Chapter 1 now focusses entirely on the methodology followed by all research partners and stakeholders in structuring and implementing research programmes. Chapter 2 is new and provides a summary of the major research results 10 years after the 1991 law became effective. Chapter 3 is also new and highlights the major milestones yet ahead and identified in terms of both objectives to be attained and key steps leading up to 2006. Chapter 4 contains a detailed description and analysis of the programmes envisaged and the last 2 chapters discuss very broadly the coordination of research activities and the way they are being implemented both at national (chapter 5) and international (chapter 6) levels. (J.S.)

  13. Research strategy and programs about the management of high-level and long-lived radioactive wastes (by right of the article L542 of the environment law and belonging to the December 30, 1991 law); Strategie et programmes des recherches sur la gestion des dechets radioactifs a haute activite et a vie longue (au titre de l'article L542 du code de l'environnement, issu de la loi du 30 decembre 1991) 2002-2006

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-01

    This document has been prepared by the French public organizations on charge of the researches about the management of radioactive wastes in the framework of the law from December 30, 1991. It was presented at the national commission of evaluation on March 6, 2002. It comprises 6 chapters dealing with: 1 - the methodology, structuration and implementation of researches: main goals; products of the back-end of the fuel cycle and evaluation of fluxes; technical structuration of programs; researches consistency, complementarity and priority; criteria of appreciation of researches relevance; 2 - the main results after 10 years of researches in the framework of the 1991 law: abatement of wastes noxiousness; wastes conditioning; long-term storage; studies on geological disposal; 3 - the main steps towards 2006: separation and transmutation; underground disposal; conditioning and long-term behaviour; 4 - presentation and analysis of research programs: separation-transmutation; feasibility of a deep geologic disposal (clay, granite); conditioning and storage (containers, storage and long-term behaviour); 5 - coordination: authorities, share of data, research programs; 6 - international collaborations; appendixes. (J.S.)

  14. The Determination of Components of Radioactive Decay Mixtures by Computer Analysis of Count-Rate Data; Determination des Composants de Melanges Radioactifs en Decroissance par Analyse a l'Ordinateur des Resultats du Comptage; Opredelenie komponentov smesej radioaktivnogo raspada posredstvom analiza dannykh skorostej scheta s pomoshch'yu schetno-reshayushchego ustrojstva; Determinacion de los Componentes de Mezclas Radiactivas por Analisis de los Datos de Recuento Mediante Calculadoras

    Energy Technology Data Exchange (ETDEWEB)

    Airman, W. D.F.; Tyler, S. A.; Dipertand, M. H.; Sedlet, J. [Argonne National Laboratory, Argonne, IL (United States)

    1965-10-15

    The components of a mixture of n radioactive isotopes can be determined from the change in activity with time provided that the activity of at least n-1 components changes significantly during the period of observation, either by direct decay or by the growth of decay products. ft is possible to predict a set of possible components for each mixture encountered, based on considerations such as the origin and history of the mixture and the separation chemistry and counting technique(s) used. If such considerations are properly applied, the set of possible components will include all of the actual components in the mixture. The appropriate growth and/or decay equations can then be formulated and solved simultaneously to obtain each component, or the mixture can be resolved graphically by extrapolations of the linear portions of the total decay-growth curve. However, when the number of components is large and/or when complex decay schemes are involved, these two techniques either cannot be applied or the errors associated with the estimates cannot be assessed. Selection of decay components by a least-squares procedure provides better estimates than solution by simultaneous equations alone. Consequently, a least-squares Fortran computer programme (designated CORD) has been developed which solves the general problem: given the times and counts per unit time from a sample, the possible radioisotopic parents and decay schemes and all associated decay constants and detection efficiencies compute the amount of each parent actually present at a predetermined zero time. In addition, the programme yields the amounts of the parents and daughters present at all data times. Initially used with bioassay and environmental samples, the programme has been specifically designed for analysing count-rate data obtained by non-spectroscopic alpha- or beta-counting. However, it should be adaptable to total gamma and spectroscopic data, provided the energy ranges over which these measurements are made permit correlations between the data obtained and the total decay and growth rates. The development of the programme and the results obtained from theoretical and experimental data used to test it are discussed. (author) [French] Les composants d'un melange de n radioisotopes peuvent etre determines d'apres les variations de l'activite avec le temps, a condition que l'activite d'au moins n-1 elements se modifie de maniere appreciable au cours de la periode consideree, soit par la decroissance directe, soit par la croissance des produits de desintegration. Pour chaque melange, il est possible de predire un ensemble d'elements d'apres des facteurs tels que l'origine et l'evolution anterieure du melange et les techniques de separation chimique et de comptage utilisees. Si ces facteurs sont appliques de maniere convenable, l'ensemble suppose contiendra tous les elements que comporte effectivement le melange. On peut alors, soit formuler les equations de croissance ou de decroissance et les resoudre simultanement pour obtenir chaque element, soit determiner le melange sous forme graphique par extrapolation des parties lineaires de la courbe totale decroissance-croissance. Toutefois, lorsque le nombre d'elements est eleve ou que des schemas complexes de decroissance entrent en ligne de compte, il est impossible, soit d'appliquer l'une ou l'autre de ces techniques, soit d'evaluer les erreurs inherentes aux previsions. L'application de la methode des moindres carres permet d'identifier plus exactement les elements en decroissance que la methode consistant a n'utiliser que des equations simultanees. Les auteurs ont donc mis au point un programme d'ordinateur Fortran, fonde sur la methode des moindres carres (designe par le vocable CORD) et destine a resoudre le probleme general, a savoir: etant donne le taux de comptage pour un echantillon, les precurseurs et les schemas de decroissance possibles, toutes les constantes de decroissance et les caracteristiques de detection, calculer la quantite de chaque precurseur effectivement present a un moment zero fixe a l'avance. En outre, le programme iournit les quantites de precurseurs et de produits de filiation presents a tous les moments ob des mesures sont faites. D'abord applique a des specimens biologiques et a des echantillons du milieu ambiant, le programme est essentiellement destine a l'analyse des taux de comptage fournis par les mesures non spectroscopiques des rayonnements alpha ou beta. Toutefois, ce programme devrait permettre de traiter l'ensemble des donnees relatives aux rayonnements gamma et des donnees spectroscopiques pourvu que les gammes d'energie dans lesquelles les mesures sont effectuees permettent d'etablir une correlation entre les donnees obtenues et les taux de decroissance et de croissance totales. Les auteurs decrivent la mise au point du programme et analysent les resultats des essais qui ont ete effectues, a partir de donnees theoriques et de donnees experimentales, pour en verifier l'efficacite. (author) [Spanish] Es posible determinar los componentes de una mezcla de n isotopos radiactivos basandose en la variacion temporal de la actividad, siempre que la actividad de n-1, por lo menos, de los componentes, varfe apreciablemente durante el periodo de observacion, bien por desintegracion directa o bien por acumulacion de los productos de desintegracion. Fundandose en consideraciones tales como el origen, los antecedentes de la mezcla y los metodos de separacion quimica y de recuento aplicados, es posible predecir para cada mezcla una. serie de componentes posibles. Si esas consideraciones se aplican correctamente, la serie de posibles componentes comprendera todos los componentes reales de la mezcla. Entonces pueden formularse las ecuaciones pertinentes de crecimiento y/o desintegracion y resolverse simultaneamente para obtener cada componente, o bien se puede resolver la mezcla graficamente por extrapolacion de las partes lineales de la curva global de desintegracion-crecimiento. De todas formas, cuando el numero de componentes es elevado o cuando se trata de esquemas de desintegracion complejos, es imposible aplicar estas dos tecnicas o evaluar los errores inherentes al calculo. La determinacion de los componentes de desintegracion por cuadrados minimos da mejores resultados que la solucion por ecuaciones simultaneas exclusivamente. Por tanto, se ha preparado un programa de computo Fortran basado en el metodo de los cuadrados minimos (denominado CORD) que resuelve el problema general: Dados los tiempos y el numero de cuentas por unidad de tiempo correspondientes a una muestra, los precursores radioisotopicos y esquemas de desintegracion posibles, asi como todas las constantes de desintegracion y los rendimientos de deteccion asociados, calcular la cantidad de cada precursor realmente presente en un tiempo cero preestablecido. Ademas, el programa permite conocer las cantidades de precursores y descendientes presentes en cada momento de toma de datos. Utilizado en un principio para la determinacion de muestras biologicas y tomadas del medio ambiente, el programa se ha concebido especialmente para analizar los datos de recuento obtenidos en la medicion de actividades alfa o beta por procedimientos distintos de los espectroscopicos. Sin embargo, deberia poder adaptarse a la medicion de la actividad gamma total y al analisis de los datos obtenidos por metodos espectroscopicos, siempre que los intervalos de energia en que estas mediciones se efectuen permitan correlacionar los datos obtenidos y las velocidades totales de desintegracion y crecimiento. Se estudian el perfeccionamiento del programa y los resultados obtenidos con datos teoricos y experimentales utilizados para ensayarlo. (author) [Russian] Predstavljaetsja vozmozhnym opredelit' komponenty smesi, sostojashhej iz p radioaktivnyh izotopov, na osnovanii izmenenija aktivnosti v zavisimosti ot vremeni, odnako pri uslovii, chto aktivnost' po men'shej mere p-1 komponentov izmenjaetsja znachitel'nym obrazom za period vremeni nabljudenija, libo v rezul'tate neposredstvennogo raspada, libo vsledstvie narastanija produktov raspada. Dlja kazhdoj novoj smesi predstavljaetsja vozmozhnym predskazat' sostav vozmozhnyh komponentov na osnovanii takih soobrazhenij, kak proishozhdenie i posledujushhaja jevoljucija smesi, harakter himii otdelenija i metod ili metody scheta. Esli takogo roda soobrazhenija primenjajutsja nadlezhashhim obrazom, to sostav vozmozhnyh komponentov vkljuchit vse dejstvitel'nye komponenty smesi. V takom sluchae mozhno sostavit' nadlezhashhie uravnenija narastanija i raspada i reshit' ih odnovremenno dlja poluchenija kazhdogo komponenta, ili zhe smes' mozhet byt' razlozhena na sostavnye chasti graficheski putem jekstrapoljacii linejnyh otrezkov krivoj obshhego raspada i narastanija. Odnako v sluchae bol'shogo chisla komponentov, esli rech' idet o kompleksnyh shemah raspada, jeti dva metoda libo okazyvajutsja nepriemlemymi, libo ne predstavljaetsja vozmozhnym opredelit' velichiny pogreshnostej, svjazannyh s vychislenijami. Otbor komponentov raspada po metodu naimen'shih kvadratov daet luchshuju ocenku, chem samo po sebe odnovremennoe reshenie uravnenij. Pojetomu na osnovanii metoda naimen'shih kvadratov byla vyrabotana programma po fortranu dlja schetno-reshajushhego ustrojstva (oboznachennaja po kodu {sup K}ORD{sup )}, kotoraja razreshaet sledujushhuju obshhuju problemu: zadajutsja momenty vremeni i otschety za edinicu vremeni dlja proby, vozmozhnye ishodnye radioizo- ' topy i shemy ih raspada, a takzhe vse sootvetstvujushhie konstanty raspada i jeffektivnosti obnaruzhenija; trebuetsja podschitat' kolichestvo kazhdogo ishodnogo izotopa, dejstvitel'no prisutstvujushhego v zaranee opredelennoe nulevoe vremja. V dopolnenie k jetomu programma daet kolichestvo ishodnyh i dochernih produktov v ljuboj moment registracii dannyh. Ispol'zovannaja pervonachal'no dlja bioanalizov i dlja analiza vzjatyh iz okruzhajushhej sredy prob, jeta programma byla zatem special'no prisposoblena k analizu dannyh skorostej al'fa- i beta-scheta, poluchennyh nespektroskopicheskimi metodami. Odnako jetu programmu mozhno prisposobit' dlja obrabotki obshhih gamma- i spektroskopicheskih dannyh pri uslovii, chto diapazony jenergij, v predelah kotoryh delajutsja jeti izmerenija, dajut vozmozhnost' ustanovit' korreljaciju mezhdu jetimi dannymi i skorostjami polnogo raspada i narastanija. Obsuzhdajutsja podrobnosti vyrabotki jetoj programmy, a takzhe rezul'taty, poluchennye na osnovanii teoreticheskih i jeksperimental'nyh dannyh i posluzhivshie dlja proverki jetoj programmy. (author)

  15. European Program 'EVEREST'. Evaluation of the elements producing the effective doses associated to a radioactive waste disposal in deep underground geological formations. Comparative study of the results obtained by IPSN concerning the sedimentary and granite formations; Programme europeen 'EVEREST'. Evaluation des elements responsables des doses efficaces associees a un stockage de dechets radioactifs en formations geologiques profondes. Etude comparative des resultats obtenus par l'IPSN concernant les formations sedimentaire et granitique

    Energy Technology Data Exchange (ETDEWEB)

    Baudoin, Patrick; Serres, Christophe; Certes Catherine [Departement d' evaluation de surete, Inst. de Protection et de Surete Nucleaire, CEA Centre d' Etudes de Fontenay-aux-Roses, 92 (France)

    1996-09-01

    The European exercise EVEREST that was run from 1991 to 1995 was a means of training for IPSN, having in view the expertise studies of ANDRA on the safety of radioactive waste geological disposal. The exercise implied two fictitious waste disposal sites, one inside a granite massif and the other in a clay formation, and had as principal objective identification and establishing a hierarchy of the radiological risk parameters important after the disposal closing. The study has considered the most likely scenario for evolution of the geological environment. As computing tools three codes were utilized: MELODIE, assuming a continuous 2D water flow and transfer of radionuclides from waste disposal to biosphere; TRISEC, assuming a continuous 3D water flow and NEWSAM, assuming a transient water flow in a multi-shell geometry. Results for the water circulation in different geological environment as well as the flux curves of soluble radionuclides are presented. Twenty seven radionuclides were retained as important by their radiological impact in assessing the influential EVEREST parameters. The EVEREST exercise does not prove the feasibility of a given geological disposal. It only contributes to the comprehension of the mechanisms controlling the radionuclide migration and gives a hierarchy of the questions which IPSN must answer in approaching the safety demonstrations required by ANDRA.

  16. Preparation of C{sup 14}-labelled tetrazolium salts and tracer study of the tetrazene-formazan rearrangement; Preparation de sels de tetrazolium marques au carbone-14 et etude de la transposition tetrazene-formazan, au moyen d'indicateurs radioactifs; Izgotovlenie mechennykh C{sup 14} solej tetrazosoedinenij i issledovanie pri pomoshchi indikatorov peregruppirovok tetrazona-formazana; Preparacion de sales de tetrazolio marcadas con {sup 14}C y estudio de la transposicion tetraceno-formazan con ayuda de trazadores

    Energy Technology Data Exchange (ETDEWEB)

    Marton, Joseph; Meisel, Julia [Central Research Institute for Chemistry of the Hungarian Academy of Sciences, Budapest (Hungary); Gosztonyi, Thomas [Institute of Organic Chemical Technology, Technical University, Budapest (Hungary)

    1962-03-15

    The preparation of [5-C{sup 14}]-TTC, [5, 5'-di-C{sup 14}]NT (neotetrazolium) and [5, 5'-di-C{sup 14}]-BT (tetrazolium blue) starting from benzaldehyde- [1-C{sup 14}] has been accomplished. The yields for both mono- and ditetrazolium salts are high, and the products can be obtained with high sp. activity. The purity of the samples was investigated by paper chromatography. In the case of ditetrazolium salts some impurities could be detected and conclusions drawn as to their structure and quantity. A method has been developed to prepare C{sup 14}- labelled ditetrazolium salts of high purity. The formation of the formazan, the precursor of the tetrazolium salt, goes through an unstable intermediate of tetrazene-type structure which rearranges rapidly in basic medium, to yield the formazan. The tetrazene intermediate can be isolated under suitable conditions. By using C{sup 14}-labelled benzaldehyde phenylhydrazone this rearrangement was investigated and a verification of its intramolecular character given. (author) [French] On a procede a la preparation de [5-C{sup 14}]-TTC, de [5,5'-di-C{sup 14}] NT (neotetrazolium) et de [5,5'-di-C{sup 14}]-VT (bleu de tetrazolium), en partant du benzaldehyde-[1-C{sup 14}]. On a pu obtenir un grand rendement, tant pour les sels de monotetrazolium que pour les sels de ditetrazolium, et des produits d'une activite specifique elevee. La purete des echantillons a ete examinee par chromatographie sur papier. Dans le cas des sels de ditetrazolium, on a pu deceler quelques impuretes et tirer des conclusions quant a leur structure et quantite. On a mis au point une methode permettant de preparer des sels de ditetrazolium marques au carbone-14 et presentant une grande purete. Dans la synthese du formazan, precurseur du sel de tetrazolium, on obtient un produit intermediaire instable d'une structure analogue a celle du tetrazene; ce produit se transforme rapidement en milieu alcalin pour donner du formazan. Le tetrazene intermediaire peut etre isole dans des conditions appropriees. On a etudie cette transformation en utilisant du benzaldehyde-phenylhydrazone marque au carbone-14, et l'on a pu verifier ainsi qu'il s'agit d'une reaction intramoleculaire. (author) [Spanish] Partiendo del benzaldehido-(1-{sup 14}C), el autor ha sintetizado el TTC-(5-{sup 14}C), el NT-(5, 5'-di-{sup 14}C) (neotetrazolio) y el BT- (5, 5'-di-{sup 14}C) (azul de tetrazolio). Las sales de mono- o ditetrazolio se obtienen con buen rendimiento y se logran productos de elevada actividad especifica. El autor determino la pureza de las muestras por cromatografia sobre papel. En las sales de ditetrazolio encontro algunas impurezas, que consiguio determinar cuantitativamente; asimismo establecio algunas caracteristicas de sus estructuras. Por otra parte, elaboro un metodo para obtener sales de ditetrazolio marcadas con {sup 14}C de elevada pureza. En la sintesis del formazan, el precursor de la sal de tetrazolio, se obtiene un producto intermedio inestable cuya estructura es similar a la del tetraceno. Este compuesto sufre una rapida transposicion en medio alcalino para dar lugar al formazan. Es posible aislar el producto intermedio si se trabaja en condiciones adecuadas. El autor estudia la transposicion utilizando la fenilhidrazona del benzaldehido marcado con {sup 14}C, y ha podido comprobar que se trata de una reaccion intramolecular. (author) [Russian] Iskhodya iz benzal'degida - [1-C{sup 14}] udalos' izgotovit' [5-C{sup 14}]-TTC, [5,5'di-C{sup 14}]-NT (neoterazolij) [5,5'di-C{sup 14}]-BT (sinij tetrazolij). Vykhody kak dlya monotetrazoliya, tak i dlya ditetrazoliya dostatochno znachitel'ny i produkty mogut byt' polucheny s bol'shoj udel'noj aktivnost'yu. Stepen' chistoty obraztsov byla issledovana pri pomoshchi khromatograficheskoj bumagi. V solyakh ditetrazoliya bylo obnaruzheno nekotoroe kolichestvo primesej, chto pozvolilo vyvesti zaklyucheniya otnositel'no ikh struktury i kolichestva. Byl vyrabotan metod mechennykh C{sup 14} solej ditetrazoliya vysokoj chistoty. Obrazovanie formazana, predshestvennika solej tetrazoliya, prokhodit cherez neustojchivuyu promezhutochnuyu stadiyu strukturnogo tipa tetrazona, bystro peregruppiruyushchegosya v shchelochnoj srede, chtoby dat' formazan. V podkhodyashchikh usloviyakh promezhutochnyj tetrazon mozhet byt' otdelen. Ispol'zovanie mechennogo C{sup 14} benzal'degidfenilgidrazoniya pozvolilo issledovat' ehtu peregruppirovku i proverit' ukazyvaemuyu mezhmolekulyarnuyu strukturu. (author)

  17. Research strategy and programs about the management of high-level and long-lived radioactive wastes (by right of the article L542 of the environment law and belonging to the December 30, 1991 law); Strategie et programmes des recherches sur la gestion des dechets radioactifs a haute activite et a vie longue (au titre de l'article L542 du code de l'environnement, issu de la loi du 30 decembre 1991) 2002-2006

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-01

    This document has been prepared by the French public organizations on charge of the researches about the management of radioactive wastes in the framework of the law from December 30, 1991. It was presented at the national commission of evaluation on March 6, 2002. It comprises 6 chapters dealing with: 1 - the methodology, structuration and implementation of researches: main goals; products of the back-end of the fuel cycle and evaluation of fluxes; technical structuration of programs; researches consistency, complementarity and priority; criteria of appreciation of researches relevance; 2 - the main results after 10 years of researches in the framework of the 1991 law: abatement of wastes noxiousness; wastes conditioning; long-term storage; studies on geological disposal; 3 - the main steps towards 2006: separation and transmutation; underground disposal; conditioning and long-term behaviour; 4 - presentation and analysis of research programs: separation-transmutation; feasibility of a deep geologic disposal (clay, granite); conditioning and storage (containers, storage and long-term behaviour); 5 - coordination: authorities, share of data, research programs; 6 - international collaborations; appendixes. (J.S.)

  18. Strategy and research programs on the long life high activity radioactive wastes management (concerning the article L542 of the environment code, of the law of the 30 December 1991). Knowledge and perspectives; Strategie et programmes des recherches sur la gestion des dechets radioactifs a haute activite et a vie longue (au titre de l'article L542 du code de l'environnement, issu de la loi du 30 decembre 1991). Acquis et perspectives

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    Describing the research strategy and the programs around the three axis, separation and transmutation - deep underground storage - conditioning and long time disposal, this document is a reference concerning the research programs of the law of the 30 December 1991. This 2004 edition presents the historical approach and the main context, the objectives, the methods and criteria followed, the research program organization and implemented coordination structures. It provides also the results of the last ten years. (A.L.B.)

  19. Report realized on behalf of the economic affairs, the environment and the territory commission on the law project, after urgency declaration, of the program relative to the sustainable management of materials and radioactive wastes; Rapport fait au nom de la commission des affaires economiques, de l'environnement et du territoire sur le projet de loi, apres declaration d'urgence, de programme relatif a la gestion des matieres et des dechets radioactifs (n. 2977)

    Energy Technology Data Exchange (ETDEWEB)

    Birraux, C

    2006-03-15

    In 1991 the France decided to intensify its researches in the high activity radioactive wastes management domain. The law of the 30 December 1991 relative to the radioactive wastes management, decided that a period of 15 years would be devoted to the research of very long dated solutions. Taking into account these researches, a law project has been composed. After a recall of the today situation of radioactive materials and wastes in France and the knowledge since 1991, this document presents the law project. (A.L.B.)

  20. Talk of Francois Loos, delegate minister of industry, at the Meuse prefecture (Bar-le-Duc). Visit of the underground laboratory of research on the geologic disposal of radioactive wastes, Bure (Meuse); Intervention de Francois Loos, ministre delegue a l'Industrie, a la Prefecture de la Meuse (Bar-le-Duc). Visite du laboratoire souterrain de recherche sur le stockage geologique des dechets radioactifs, Bure (Meuse)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    In this talk, the French minister of industry recalls, first, the context of the management of radioactive wastes and the research programs launched in the framework of the 'Bataille' law from December 30, 1991. Then, he stresses on the importance of the work carried out so far in the three ways of research on radioactive wastes: separation/transmutation, deep underground disposal and long duration surface storage. He introduces the government will of organizing a public debate about the management of radioactive wastes before the preparation of the law project for the implementation of the technological and scientifical choices (the 'road-map') of France in the domain of radioactive wastes management. He stresses also on the importance of the financing warranties of this management and of the public information in this domain. He concludes on the economical support of the government in consideration of the regions that have accepted or would accept the setting up of waste management research laboratories and industrial facilities. (J.S.)

  1. Adsorption of fission products on mediterranean mud; Adsorption des produits de fission sur des vases de mediterranee

    Energy Technology Data Exchange (ETDEWEB)

    Cohen, P; Gailledreau, C [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1960-07-01

    Partition coefficients of some fission products have been measured in sea water on mud taken from the bottom of the Mediterranean sea. A discussion follows on the behaviour of these radioisotopes. (author) [French] On a mesure les coefficients de partage dans l'eau de mer de quelques produits de fission a longue periode sur des echantillons de vase preleves en Mediterranee. Les valeurs trouvees sont elevees. Le comportement de ces isotopes radioactifs est discutee. (auteur)

  2. 357 Datation des carbonates impurs au Maroc à l'aide de la ...

    African Journals Online (AJOL)

    youness

    Datation des carbonates impurs au Maroc à l'aide de la méthode de déséquilibre radioactif 230Th/234U. A. Choukri1, S. Semghouli1, O. Hakam1, M. Moheidine3 et M. Laatiris4. 1Laboratoire de Physique de la Matière et Rayonnement, Equipe de. Physique et Techniques Nucléaires, Faculté des Sciences, P.B 133,. 14000 ...

  3. Synthesis of the {beta}-phenethyl-mercaptan ({sup 35}S); Synthese du {beta}-phenethylmercaptan ({sup 35}S)

    Energy Technology Data Exchange (ETDEWEB)

    Wolff, R [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1957-07-01

    {beta}-phenethyl-mercaptan ({sup 35}S) has been synthesized by action of elementary radioactive sulphur ({sup 35}S) on {beta}-phenethyl-magnesium-bromide, with a 90 per cent yield. (author) [French] Le {beta}-phenethylmercaptan ({sup 35}S) a ete synthetise par action du soufre radioactif elementaire ({sup 35}S) sur le bromure de {beta}-phenethylmagnesium, avec un rendement de 90 pour cent. (auteur)

  4. Les tumeurs oncocytaires de la thyroide : a propos de 25 cas ...

    African Journals Online (AJOL)

    Conclusion : Les tumeurs oncocytaires de la thyroïde sont reconnues à la lumière des travaux récents comme une entité anatomo-clinique particulière, se différenciant des tumeurs vésiculaires (auxquelles elles ont été longtemps assimilées) par une évolution plus péjorative et par une insensibilité à l'iode radioactif avec ...

  5. The effluent problem in a plutonium production centre; Probleme des effluents d'un centre de production de plutonium

    Energy Technology Data Exchange (ETDEWEB)

    Galley, R; Cantel, J [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1960-07-01

    The first part of the report is devoted to generalities: the geographical situation of the Marcoule Centre, the sources of radio-active effluent, methods of treating this effluent. In the second part the authors gives a detailed description of the various installations in the Radio-active Effluent Treatment Station at the Marcoule Centre, and outline the conditions governing the rejection of treated effluent into the Rhone. A few lines are given to comparisons between the results obtained from the use of these installations up till may 1959 and the expected results published by the same authors at the Brussels Conference (1956). In conclusion the authors lay down some of the essential principles, applicable to the study of new installations. (author) [French] La premiere partie du rapport est consacree a quelques generalites: situation geographique du Centre de Marcoule, provenance des effluents radioactifs, methodes de traitement de ces effluents. Dans la seconde partie, les auteurs presentent une description detaillee des diverses installations de la Station de Traitement des Effluents radioactifs du Centre de Marcoule et precisent les conditions de rejet dans le Rhone des effluents radioactifs traites. Quelques lignes sont consacrees aux comparaisons entre les resultats de l'exploitation des installations jusqu'en mai 1959 et les previsions publiees par les memes auteurs a l'occasion de la Conference de Bruxelles (1956). En conclusion, les auteurs donnent quelques principes essentiels, applicables a l'etude de nouvelles installations. (auteur)

  6. Annular electromagnetic pumps-construction and testing-theory, and comparison with experimental results; Pompes electromagnetiques annulaires - construction et essais - theorie et confrontation avec l'experience

    Energy Technology Data Exchange (ETDEWEB)

    Cambillard, E P; Schwab, B L [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1964-07-01

    This report consists of three sections. The first is concerned with the description of different pumps which have been constructed, tests on these which have been completed and the results obtained. The second section presents a theoretical method for the determination of the coefficients, taking in account the break of the magnetic circuit. It is shown that the preliminary design calculations of the annular pumps can be made, neglecting the break of the magnetic circuit, by further assigning essential magnitudes (pressure, losses) with easily calculated coefficients. The third section of this report uses the theoretical bases exposed in the second section, and develop a new annular pump calculation method which takes-into account both the current out of balance and any type of winding. (authors) [French] Ce rapport comprend trois parties. La premiere est consacree a la description des differentes pompes construites, aux essais,effectues et aux resultats obtenus. La deuxieme partie expose une methode theorique de determination de coefficients tenant compte de l'ouverture du circuit magnetique. On montre que le calcul d'avant-projet des pompes annulaires peut s'effectuer comme si le circuit magnetique n'etait pas coupe, en affectant ensuite toutes les grandeurs essentielles (pression, pertes) de coefficients aisement calculables. La troisieme partie de ce rapport utilise les bases de la theorie exposee dans la deuxieme partie et developpe une nouvelle methode de calcul des pompes annulaires qui tient compte a la fois du desequilibre des courants et d'un bobinage quelconque. (auteurs)

  7. Report realized on behalf of the economic affairs, the environment and the territory commission, on the law project modified by the Senate, after urgency declaration (n. 3121), of program relative to the sustainable management of the radioactive materials and wastes; Rapport fait au nom de la commission des affaires economiques, de l'environnement et du territoire sur le projet de loi, modifie par le Senat, apres declaration d'urgence (n. 3121), de programme relatif a la gestion durable des matieres et des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Birraux, C

    2006-06-15

    This report presents and discusses the modifications realized by the Senate on the law project relative to the sustainable management of the radioactive materials and wastes. It details then the different articles in three main chapters: the national policy for the sustainable radioactive materials and wastes, the organization and the financing of the sustainable management of radioactive materials and wastes, the control and the penalties. (A.L.B.)

  8. 1. contribution of the dynamics on the reactions mechanisms in the heavy ions collisions at the intermediary energies (20-100 MeV/A) for the light systems. 2. management of radioactive wastes by new options: nuclear data measurement programme between 20 and 150 MeV; 1. role de la dynamique sur les mecanismes de reactions dans les collisions d'ions lourds aux energies intermediaires (20-100 MeV/A) pour des systemes legers. 2. gestion des dechets radioactifs par des options nouvelles: programme de mesures de donnees nucleaires entre 20 et 150 MeV

    Energy Technology Data Exchange (ETDEWEB)

    Eudes, Ph

    2000-09-22

    The first part concerns the features of emitted charged particles in heavy ions reactions that have been studied in the framework of the semi classical Landau-Vlasov approach for the light system Ar + Al at 65 MeV/nucleon incident energy. The second part is devoted to the radioactive waste management (transmutation), but it was necessary to increase the data banks evaluated in neutrons up to 150-200 MeV and to create a data bank in protons. In the European framework it was decide to focus on three representative elements: lead (spallation target), iron (structure material) and uranium (actinide). (N.C.)

  9. 1. contribution of the dynamics on the reactions mechanisms in the heavy ions collisions at the intermediary energies (20-100 MeV/A) for the light systems. 2. management of radioactive wastes by new options: nuclear data measurement programme between 20 and 150 MeV; 1. role de la dynamique sur les mecanismes de reactions dans les collisions d'ions lourds aux energies intermediaires (20-100 MeV/A) pour des systemes legers. 2. gestion des dechets radioactifs par des options nouvelles: programme de mesures de donnees nucleaires entre 20 et 150 MeV

    Energy Technology Data Exchange (ETDEWEB)

    Eudes, Ph

    2000-09-22

    The first part concerns the features of emitted charged particles in heavy ions reactions that have been studied in the framework of the semi classical Landau-Vlasov approach for the light system Ar + Al at 65 MeV/nucleon incident energy. The second part is devoted to the radioactive waste management (transmutation), but it was necessary to increase the data banks evaluated in neutrons up to 150-200 MeV and to create a data bank in protons. In the European framework it was decide to focus on three representative elements: lead (spallation target), iron (structure material) and uranium (actinide). (N.C.)

  10. Decree no. 2001-1199 of the 10 december 2001 publishing the resolution MSC. 88 (71) notifying adoption of the international compilation of safety rules for the spent nuclear fuels, plutonium and high level radioactive wastes transport in casks on ships (compilation INF) (annexes), adopted at London the 27 may 1999; Decret no. 2001-1199 du 10 decembre 2001 portant publication de la resolution MSC.88 (71) portant adoption du recueil international de regles de securite pour le transport de combustible nucleaire irradie, de plutonium et de dechets hautement radioactifs en colis a bord de navires (recueil INF) (ensemble une annexe), adoptee a Londres le 27 mai 1999

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-01

    This legislative text concerns the safety rules of spent nuclear fuels, plutonium and high level radioactive wastes transport, in casks on ships. Rules, fire prevention, temperature control of casks, electric supply, radioprotection, management and emergency plans are detailed. (A.L.B.)

  11. Chronology of fluid paleo-circulations in mesozoic formations on the site of Bure by U/Pb dating of secondary calcites

    International Nuclear Information System (INIS)

    Pisapia, C.; Deschamps, P.; Hamelin, B.; Pisapia, C.; Buschaert, S.

    2009-01-01

    The French national agency for the management of radioactive wastes (ANDRA, Agence nationale pour la gestion des dechets radioactifs) has developed an underground research laboratory in mesozoic formations of the eastern Parisian Basin in order to test the design of radioactive waste storage site in sedimentary formations. The authors report an investigation which aims at understanding the site paleo-hydrology. This investigation is based on the disintegration chain of uranium and on U/Th and U/Pb dating methods, and aims at giving a precise chronology of the different phases of precipitation of centimetric and millimetric secondary calcites sampled on this site

  12. Latest developments at GANIL for stable and radioactive ion beam production

    International Nuclear Information System (INIS)

    Jardin, P.; Barue, C.; Bajeat, O.; Canet, C.; Clement, E.; Cornell, J. C.; Delahaye, P.; Dubois, M.; Dupuis, M.; Flambard, J. L.; Fraanberg, H.; Frigot, R.; Leboucher, C.; Lecesne, N.; Lecomte, P.; Leherissier, P.; Lemagnen, F.; Leroy, R.; Maunoury, L.; Mery, A.

    2010-01-01

    In the frame of the SPIRAL II (Systeme de Production d'Ions Radioactifs Acceleres en Ligne Partie II) project, several developments of stable and radioactive ion production systems have been started up. In parallel, GANIL has the ambition to preserve the existing stable and radioactive beams and also to increase its range by offering new ones. In order to identify the best directions for this development, a new group called GANISOL has been formed. Its preliminary conclusions and the latest developments at GANIL are presented.

  13. Application of the chemical properties of ruthenium to decontamination processes; L'application des proprietes chimiques du ruthenium a des procedes de decontamination

    Energy Technology Data Exchange (ETDEWEB)

    Fontaine, A.; Berger, D. [Commissariat a l' Energie Atomique, Centre de Production de Plutonium, Marcoule (France). Centre d' Etudes Nucleaires

    1965-07-01

    The chemical properties of ruthenium in the form of an aqueous solution of the nitrate and of organic tributylphosphate solution are reviewed. From this data, some known examples are given: they demonstrate the processes of separation or of elimination of ruthenium from radioactive waste. (authors) [French] Les proprietes chimiques du ruthenium en solutions aqueuses nitriques et en solutions organiques de tributylphosphate, sont passees en revue. A partir de ces donnees, quelques exemples connus sont cites: ils exposent des procedes de separation ou d'elimination du ruthenium de dechets radioactifs. (auteurs)

  14. Synthesis of 2-mercaptobenzothiazole ({sup 35}S); Synthese du mercapto-2-benzothiazole ({sup 35}S)

    Energy Technology Data Exchange (ETDEWEB)

    Bentov, M [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    The synthesis of 2-mercaptobenzothiazole ({sup 35}S) by the interaction of 2-chloro benzothiazole and sodium hydrosulfide ({sup 35}S) has been studied. Under the conditions determined in this study a pure product with a radioactive yield of 79 per cent can be obtained. (author) [French] La synthese du mercapto-2-benzothiazole ({sup 35}S) par l'interaction du chloro-2-benzothiazole et I'hydrosurfure ({sup 35}S) de sodium a ete etudiee. On a trouve que dans les conditions determinees dans cette etude, on peut obtenir un produit pur avec un rendement radioactif de 79 pour cent. (auteur)

  15. Possibilities of gas-phase radio-chromatography application to permanent-gas analysis; Possibilites de la radiochromatographie en phase gazeuse applications a l'analyse des gaz permanents

    Energy Technology Data Exchange (ETDEWEB)

    Dupuis, M C; Charrier, G; Alba, C; Massimino, D [Commissariat a l' Energie Atomique, Bruyeres-le-Chatel (France). Centre d' Etudes

    1970-07-01

    The gas-phase radio-chromatography technique has been applied to the rapid analysis of permanent gases (H{sub 2}, O{sub 2}, N{sub 2}, A, Kr, Xe, CO, CH{sub 4}) labelled with radioactive indicators ({sup 3}H, {sup 37}A, {sup 85}Kr, {sup 133}Xe). After calibration, the components of such a mixture can be identified and their concentrations measured in less than two hours, using a sample volume of from 0.1 to 10 cm{sup 3}. The minimum detectable activity is of the order of 10{sup -4} {mu}C for each radioactive isotope. The measurements are reproducible to about 2 to 3 per cent. This work has been mainly concerned with the influence of parameters affecting the response of the radioactivity detector (ionization chamber or gas flow proportional counter). The method has very numerous applications both theoretically, for the study of chromatographic phenomena under ideal conditions (infinitesimal concentrations made possible by the use of radioactive tracers), and practically, for rapid and accurate radiochemical analysis of radioactive gas mixtures. (authors) [French] La technique de radiochromatographie en phase gazeuse est appliquee a l'analyse rapide de gaz permanents (H{sub 2}, O{sub 2}, N{sub 2}, A, Kr, Xe, CO, CH{sub 4}) marques par des indicateurs radioactifs ({sup 3}H, {sup 37}A, {sup 85}Kr, {sup 133}Xe). Apres etalonnage, l'identification et la mesure des concentrations des constituants d'un tel melange requierent moins de deux heures, sur un volume d'echantillon de 0.1 a 10 cm{sup 3}. L'activite minimum detectable est de l'ordre de 10{sup -4} {mu}C pour chaque isotope radioactif. La reproductibilite des mesures est de l'ordre de 2 a 3 pour cent. L'etude porte principalement sur l'influence des parametres affectant la reponse du detecteur de radioactivite (chambre d'ionisation, ou compteur proportionnel a circulation). La methode est extremement fertile en applications tant sur le plan theorique pour l'etude du phenomene chromatographique dans les conditions

  16. Application of the chemical properties of ruthenium to decontamination processes; L'application des proprietes chimiques du ruthenium a des procedes de decontamination

    Energy Technology Data Exchange (ETDEWEB)

    Fontaine, A; Berger, D [Commissariat a l' Energie Atomique, Centre de Production de Plutonium, Marcoule (France). Centre d' Etudes Nucleaires

    1965-07-01

    The chemical properties of ruthenium in the form of an aqueous solution of the nitrate and of organic tributylphosphate solution are reviewed. From this data, some known examples are given: they demonstrate the processes of separation or of elimination of ruthenium from radioactive waste. (authors) [French] Les proprietes chimiques du ruthenium en solutions aqueuses nitriques et en solutions organiques de tributylphosphate, sont passees en revue. A partir de ces donnees, quelques exemples connus sont cites: ils exposent des procedes de separation ou d'elimination du ruthenium de dechets radioactifs. (auteurs)

  17. Hydrogen modelling for vitrified wastes repository

    International Nuclear Information System (INIS)

    Voinis, S.; Breton, J.

    1992-01-01

    Safety assessments for High Level Wastes (HLW) have led ANDRA (Agence Nationale pour la gestion des Dechets Radioactifs) to study the occurrence of a gas production rate in a repository. This paper deals with the description of an analytical model used for the gas production rate assessment and brings us the first results. The geometry used is restrained to a single borehole associated with a drift in a crystalline formation. Different concepts were studied in this assessment. First results have been obtained. For example, in the case of a permeable plug, the saturation time of the borehole is about 300 years. 5 refs., 5 figs

  18. Industrial long-term waste management in France

    International Nuclear Information System (INIS)

    Marque, Y.

    1988-01-01

    Long-term industrial management of radioactive waste in France is carried out by the Agence Nationale pour la Gestion des Dechets Radioactifs (ANDRA). ANDRA is in charge of design, siting, construction and operation of disposal centers. The French national program of waste management is running on with the construction of a second near-surface disposal which is expected to be in operation in 1991 and a selection of a site for the construction of an underground laboratory for the qualification of this site for deep disposal

  19. Underground storage. Study of radwaste storage in deep geological formations: environmental protection

    International Nuclear Information System (INIS)

    Hoorelbeke, J.M.

    1993-01-01

    The purpose of the Agence nationale pour la gestion des dechets radioactifs (Andra) is to monitor the management methods and storage of radioactive waste produced in France. The agency has this undertaken a vast study program for the evaluation of the management conditions of long-life radwaste, which cannot be stored indefinitely in shallow-ground repositories. Underground laboratories are investigating the feasibility of a possible solution which is to store radwaste in a deep geological layer. However, there will be no decision on this type of storage before the year 2006. 7 figs

  20. Technical report on the accelerators

    Energy Technology Data Exchange (ETDEWEB)

    Bex, L [ed.

    1996-12-31

    GANIL operation and the technical studies performed in 1994 are described. The milestones for 1994 are: SISSI (Source d`Ions Secondaires a Supraconducteurs Intense) has been in operation and used for secondary beam production with four different primary beams. The 100 kV platform for beam injection in the CO1 has been in operation for production of metallic beams which demand is increasing. Finally the SPIRAL project (Systeme de Production d`Ions Radioactifs Acceleres en Ligne) is in progress. In late 1994 the civil work has started in view of the installation of the machine in the north part of the GANIL machine building. (K.A.). 48 refs.

  1. Final closure of a low level waste disposal facility

    International Nuclear Information System (INIS)

    Potier, J.M.

    1995-01-01

    The low-level radioactive waste disposal facility operated by the Agence Nationale pour la Gestion des Dechets Radioactifs near La Hague, France was opened in 1969 and is scheduled for final closure in 1996. The last waste package was received in June 1994. The total volume of disposed waste is approximately 525,000 m 3 . The site closure consists of covering the disposal structures with a multi-layer impervious cap system to prevent rainwater from infiltrating the waste isolation system. A monitoring system has been set up to verify the compliance of infiltration rates with hydraulic performance objectives (less than 10 liters per square meter and per year)

  2. Possibilities of gas-phase radio-chromatography application to permanent-gas analysis; Possibilites de la radiochromatographie en phase gazeuse applications a l'analyse des gaz permanents

    Energy Technology Data Exchange (ETDEWEB)

    Dupuis, M.C.; Charrier, G.; Alba, C.; Massimino, D. [Commissariat a l' Energie Atomique, Bruyeres-le-Chatel (France). Centre d' Etudes

    1970-07-01

    The gas-phase radio-chromatography technique has been applied to the rapid analysis of permanent gases (H{sub 2}, O{sub 2}, N{sub 2}, A, Kr, Xe, CO, CH{sub 4}) labelled with radioactive indicators ({sup 3}H, {sup 37}A, {sup 85}Kr, {sup 133}Xe). After calibration, the components of such a mixture can be identified and their concentrations measured in less than two hours, using a sample volume of from 0.1 to 10 cm{sup 3}. The minimum detectable activity is of the order of 10{sup -4} {mu}C for each radioactive isotope. The measurements are reproducible to about 2 to 3 per cent. This work has been mainly concerned with the influence of parameters affecting the response of the radioactivity detector (ionization chamber or gas flow proportional counter). The method has very numerous applications both theoretically, for the study of chromatographic phenomena under ideal conditions (infinitesimal concentrations made possible by the use of radioactive tracers), and practically, for rapid and accurate radiochemical analysis of radioactive gas mixtures. (authors) [French] La technique de radiochromatographie en phase gazeuse est appliquee a l'analyse rapide de gaz permanents (H{sub 2}, O{sub 2}, N{sub 2}, A, Kr, Xe, CO, CH{sub 4}) marques par des indicateurs radioactifs ({sup 3}H, {sup 37}A, {sup 85}Kr, {sup 133}Xe). Apres etalonnage, l'identification et la mesure des concentrations des constituants d'un tel melange requierent moins de deux heures, sur un volume d'echantillon de 0.1 a 10 cm{sup 3}. L'activite minimum detectable est de l'ordre de 10{sup -4} {mu}C pour chaque isotope radioactif. La reproductibilite des mesures est de l'ordre de 2 a 3 pour cent. L'etude porte principalement sur l'influence des parametres affectant la reponse du detecteur de radioactivite (chambre d'ionisation, ou compteur proportionnel a circulation). La methode est extremement fertile en applications tant sur le plan theorique pour l

  3. Technical report on the accelerators

    International Nuclear Information System (INIS)

    Bex, L.

    1995-01-01

    GANIL operation and the technical studies performed in 1994 are described. The milestones for 1994 are: SISSI (Source d'Ions Secondaires a Supraconducteurs Intense) has been in operation and used for secondary beam production with four different primary beams. The 100 kV platform for beam injection in the CO1 has been in operation for production of metallic beams which demand is increasing. Finally the SPIRAL project (Systeme de Production d'Ions Radioactifs Acceleres en Ligne) is in progress. In late 1994 the civil work has started in view of the installation of the machine in the north part of the GANIL machine building. (K.A.)

  4. Development of a gas-ionization {beta}-spectrometer; Etude et realisation d'un spectrometre {beta} a ionisation gazeuse

    Energy Technology Data Exchange (ETDEWEB)

    Le Du, R [Commissariat a l' Energie Atomique, Bruyeres-le-Chatel (France). Centre d' Etudes

    1968-05-15

    We intend to develop in our laboratory a {beta}-spectrometer. This apparatus will have two main objectives: 1 - the determination of the nature and the degree of purity of certain {beta}-emitting radioactive substances; 2 - the study of an activity calibration process for {beta}-emitting radioactive sources. (author) [French] Nous nous proposons d'etudier et de realiser dans notre laboratoire un spectrometre {beta}. Cet appareil aura deux buts principaux: 1 - determiner la nature et le degre de purete de certains corps radioactifs emetteurs {beta}; 2 - permettre l'etude d'un procede d'etalonnage en activite de sources radioactives emetteurs {beta}. (auteur)

  5. Synthesis of tetramethylthiuram disulfide ({sup 35}S); Synthese du disulfure de tetramethylthiurame ({sup 35}S)

    Energy Technology Data Exchange (ETDEWEB)

    Bentov, M [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    Tetramethylthiuram disulfide ({sup 35}S) has been prepared by exchange between elementary sulfur ({sup 35}S) and sodium N-dithiocarbamate followed by an oxidation with potassium ferricyanide. The method allows to obtain rapidly a pure product with relatively high activity. The radioactive exchange is 82 per cent. (author) [French] Le disurfure de tetramethylthiurame ({sup 35}S) a ete prepare par echange entre le soufre elementaire ({sup 35}S) et le N-dimethyldithiocarbamate de soude suivi d'une oxydation par le ferricyanure de potasse. La methode permet d'obtenir rapidement un produit pur avec une activite relativement haute. L'echange radioactif effectue est de 82 pour cent. (auteur)

  6. Liver and water metabolism; Foie et metabolisme de l'eau

    Energy Technology Data Exchange (ETDEWEB)

    Fallot, P. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires; Faculte des Sciences de Grenoble, 38 (France)

    1959-07-01

    The causes for the disturbance of hydro-electrolytic equilibrium observed in cirrhosis patients are far from clear. Studies on the static distribution of liquid in the organism and also on anomalies in the distribution of deuterium oxide and tritiated water provide no direct explanation of the nature of the water retaining mechanism. At the period when the illness is established, endocrine factors and electrolytic perturbations contribute to maintaining or increasing oliguresis, but they cannot be held solely responsible in the initial stages of evolution. An explanation of the ascites should therefore be looked for in a non-functioning of the polygonal or Kupffer cells. The hypothesis of an insufficient rejection of water outside the lymph spaces of the liver during cirrhosis is put forward, but the experimental demonstration of such a phenomenon proves very difficult. (author) [French] Les causes du desequilibre hydroelectrolytique observe chez les malades cirrhotiques sont loin d'etre elucidees. Les etudes de la repartition du liquide de l'organisme ainsi que celles des anomalies de la distribution de l'oxyde de deuterium et de l'eau tritiee n'apportent aucune explication directe sur la nature du mecanisme de la retention de l'eau. A la periode d'etat de la maladie, les facteurs endocriniens et les perturbations electrolytiques contribuent a entretenir ou a accroitre l'oligurie mais ils ne peuvent etre seuls invoques lors des stades initiaux de l'evolution. Il faudrait donc rechercher dans un dysfonctionnement des cellules polygonales ou kupfferiennes l'explication de l'ascite. L'hypothese d'une insuffisance du rejet de l'eau hors des espaces lymphatiques du foie au cours de la cirrhose est evoquee mais la demonstration d'un tel phenomene s'avere tres difficile sur le plan experimental. (auteur)

  7. Liver and water metabolism; Foie et metabolisme de l'eau

    Energy Technology Data Exchange (ETDEWEB)

    Fallot, P [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires; Faculte des Sciences de Grenoble, 38 (France)

    1959-07-01

    The causes for the disturbance of hydro-electrolytic equilibrium observed in cirrhosis patients are far from clear. Studies on the static distribution of liquid in the organism and also on anomalies in the distribution of deuterium oxide and tritiated water provide no direct explanation of the nature of the water retaining mechanism. At the period when the illness is established, endocrine factors and electrolytic perturbations contribute to maintaining or increasing oliguresis, but they cannot be held solely responsible in the initial stages of evolution. An explanation of the ascites should therefore be looked for in a non-functioning of the polygonal or Kupffer cells. The hypothesis of an insufficient rejection of water outside the lymph spaces of the liver during cirrhosis is put forward, but the experimental demonstration of such a phenomenon proves very difficult. (author) [French] Les causes du desequilibre hydroelectrolytique observe chez les malades cirrhotiques sont loin d'etre elucidees. Les etudes de la repartition du liquide de l'organisme ainsi que celles des anomalies de la distribution de l'oxyde de deuterium et de l'eau tritiee n'apportent aucune explication directe sur la nature du mecanisme de la retention de l'eau. A la periode d'etat de la maladie, les facteurs endocriniens et les perturbations electrolytiques contribuent a entretenir ou a accroitre l'oligurie mais ils ne peuvent etre seuls invoques lors des stades initiaux de l'evolution. Il faudrait donc rechercher dans un dysfonctionnement des cellules polygonales ou kupfferiennes l'explication de l'ascite. L'hypothese d'une insuffisance du rejet de l'eau hors des espaces lymphatiques du foie au cours de la cirrhose est evoquee mais la demonstration d'un tel phenomene s'avere tres difficile sur le plan experimental. (auteur)

  8. NET.EXCEL - a European thematic network for suggesting and prioritising future joint R and D projects

    International Nuclear Information System (INIS)

    Svemar, C.; Brewitz, W.

    2004-01-01

    The NET.EXCEL project concerns the forming of a network of European end users for analysing the present status and future needs in research, technical development and demonstration (RTD) for the disposal of highly radioactive waste in the three classical rock media: salt, clay/clay sediments and crystalline rock. The aim is to generate values additional to that gained by the individual participants: Svensk Kaernbraenslehantering AB (Sweden), Posiva Oy (Finland), Empresa Nacional de Residuos Radioactivos SA (Spain), Gesellschaft fuer Anlagen- und Reaktorsicherheit mbH (Germany), Agence nationale pour la gestion des dechets radioactifs (France), Nationale Genossenschaft fuer die Lagerung radioaktiver Abfaelle (Swizerland), Organisme National des Dechets Radioactifs et des Matieres Fissiles Enrichies (Belgium) and United Kingdom Nirex Limited (UK). The practical way to carry out the needed RTD-activities and the principles behind the process to establish priorities for the necessary RTD-work is quite similar among the participants. Common ground has been analysed for the role/responsibilities of the participating organisations, for the establishment of priorities for the RTD work and for the modus operandi of the organisations to carry out the RTD. The issue of prioritising the potential RTD activities and the factors taken into account by the participating organisations have been summarised and analysed with respect to the common denominator in the project. (orig.)

  9. Ventilation of radioactive enclosures; Ventilation des enceintes radioactives

    Energy Technology Data Exchange (ETDEWEB)

    Caminade, F; Laurent, H [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1957-07-01

    Mechanical, physical and chemical manipulations on radioactive products must be carried out in properly ventilated enclosed places. The air extracted can only be discharged into the atmosphere after a correct filtration. The power of the ventilation systems is a function of the dimensions and purpose of the enclosure? The choice of types of filter is determined by the physical state and chemical nature of the radioactive materials to be manipulated. This study deals with the individual equipment of small installations: glove boxes, manipulation boxes with outside control and, if necessary, production chambers (maximum useful volume: 5 m{sup 3}). The performances of three types of 'ventilators', and the modifications provided by the addition of filters, are measured and compared. (author) [French] Les manipulations oceaniques, physiques et chimiques sur des produits radioactifs doivent s'effectuer dans des enceintes convenablement ventilees. L'air extrait ne peut etre rejete dans l'atmosphere qu'apres une filtration correcte. La puissance des installations de ventilation est fonction des dimensions de l'enceinte et de son utilisation. Le choix des types de filtres est determine par l'etat physique et la nature ehimique des corps radioactifs manipules. Notre etude porte sur l'equipement individuel d'installations de petites dimensions: boites a gants, boites a pinces et, a la rigueur, enceintes de production (volume maximum utilisable 5 m{sup 3}). Nous mesurons et comparons les performances de trois types de 'ventilateurs' et les modifications apportees par l'adjonction de filtres. (auteur)

  10. Comparison of methods for measuring the ion exchange capacity of a soil. Development of a quick method; Comparaison des methodes de mesure de la capacite d'echange d'ions d'un sol. Mise au point d'une methode rapide

    Energy Technology Data Exchange (ETDEWEB)

    Amavis, R [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1959-07-01

    In the course of a study on the movement of radioactive ions in soil we had to measure the cationic exchange capacity of various soil samples, this parameter being one of the most important in the appreciation of the extent of fixation of radioactive ions in the ground. The object of this report is to describe the various methods used and to compare the results obtained. A colorimetric method, using Co(NH{sub 3}){sub 6}{sup 3+} as exchangeable ion, was developed. It gives results comparable to those obtained with conventional methods, whilst considerably reducing the time necessary for the operations. (author) [French] A l'occasion de l'etude du mouvement des ions radio-actifs dans un sol, nous avons ete amenes a mesurer la capacite d'echange cationique de differents echantillons de sols; ce parametre etant un des plus importants pour apprecier la valeur de la fixation des ions radioactifs dans un terrain. L'objet de ce rapport est d'exposer les diverses methodes utilisees et de comparer les resultats obtenus. Une methode calorimetrique, utilisant Co(NH{sub 3}){sub 6}{sup 3+} comme ion echangeable, a ete mise au point: elle donne des resultats comparables a ceux obtenus avec les methodes habituelles et permet de reduire considerablement la duree des manipulations. (auteur)

  11. Study of the on line radioactive multicharged ion production

    International Nuclear Information System (INIS)

    Lecesne, N.

    1997-01-01

    This work is directly related to the SPIRAL project (Systeme de Production d'Ions Radioactifs Acceleres en Ligne) which will start at GANIL at the end of 1998. The aim of the thesis was to study the on line radioactive multicharged ion beam production stages, i.e. the production and diffusion of the radioactive nuclei in a thick target, their possible transfer up to an ECR ion source and their ionisation. Production cross sections of radioactive neutron rich nuclei, formed by fragmentation of a heavy ion beam in a thick target, were measured. An external target-ECR source system, dedicated to the radioactive noble gases production, and two internal target-ECR source systems, dedicated to the radioactive condensable element production, were built and tested on the SIRa tests bench (Separateur d'Ions Radioactifs). Different detection configurations were elaborated in order to identify the radioactive nuclei and estimate their production yields. Finally, a new method for measuring the overall efficiency of the separator was developed and allowed to study the diffusion properties of radioactive noble gases in various targets. (author)

  12. Treatment and storage of contaminated materials; Traitement et stockage des materiels contamines

    Energy Technology Data Exchange (ETDEWEB)

    Cerre, P; Pomarola, J [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1959-07-01

    The ultimate disposal of radioactive wastes sets an important problem which has been partly solved. France has temporarily adopted the following method: 1) Volume reduction, 2) Fixation of the activity in non leakable solids standing all temporarily or ultimate kinds of storing. According to those two basic principles the authors have presented: - a decontamination plant allowing maximum recovery of materials, - the plans of an installation devised for carrying out radioactive waste volume reduction and conditioning. Both of them are being built at Saclay. (author) [French] La destination finale des residus radioactifs pose un probleme imparfaitement resolu. La France a adopte, comme solution d'attente, le processus ci-dessous: 1) Reduction des volumes, 2) Confinement de l'activite dans des solides non lechables et pouvant resister a tous modes de stockage provisoire ou definitif. A partir des idees directrices, MM. CERRE et POMAROLA ont presente: - un batiment de decontamination permettant de recuperer le maximum de materiaux, - un projet d'installation visant a la reduction du volume des dechets radioactifs et leur conditionnement. Ces deux installations sont en cours d'execution a Saclay. (auteur)

  13. Caesium absorption by barley - influence of its retention by the soil - competitive action of potassium; Absorption du cesium par l'orge - influence de sa retention dans le sol - action competitive du potassium

    Energy Technology Data Exchange (ETDEWEB)

    Ferron-Trosseau, F. [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1964-06-01

    plants such as rice and cress growing on flooded soils. Radio-active caesium however incorporated without carrier into a soil of medium-exchange capacity (of about 150 milli-equivalents per kilo) presents relatively little danger because of the close interdependence of the radioactive caesium take-up from the soil by the plants and its retention by the soil. Our research has made it possible furthermore to examine the value of various partial decontamination methods for soils proposed by certain atomic scientists: just as isotopic dilution appears totally inadequate for this purpose, so does it seems that the addition of potassium salts in amounts greater than nutritive optimum is incapable of reducing the absorption of radioactive caesium by the plant. (author) [French] Nous avons recherche, dans divers milieux de culture, comment l'absorption du cesium par l'orge varie avec sa concentration et comment cette absorption peut etre concurrencee par un cation alcalin voisin,le potassium. En outre, nous avons considere la distribution du cesium dans le sol - notamment du cesium radioactif - entre terre et solution, en fonction du taux de cesium. De notre etude ressort une nette opposition entre le comportement de l'orge vis a vis du cesium d'une solution nutritive et vis a vis du cesium d'un sol: sur solution nutritive, la fraction du cesium (radioactif et stable) absorbee par l'orge demeure pratiquement constante en presence de proportions croissantes (relativement petites) de cesium stable; sur sol, la fraction du cesium radioactif absorbee par l'orge a augmente en meme temps que le taux (relativement petit) de cesium stable du sol, en relation avec une selectivite rapidement decroissante du sol pour Cs. La difference entre ces resultats est donc expliquee par une tres forte selectivite du sol illitique experimente pour Cs{sup +} tant que la proportion da cesium reste tres petite, de l'ordre de celle de la plupart des sols naturels

  14. Caesium absorption by barley - influence of its retention by the soil - competitive action of potassium; Absorption du cesium par l'orge - influence de sa retention dans le sol - action competitive du potassium

    Energy Technology Data Exchange (ETDEWEB)

    Ferron-Trosseau, F [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1964-06-01

    as rice and cress growing on flooded soils. Radio-active caesium however incorporated without carrier into a soil of medium-exchange capacity (of about 150 milli-equivalents per kilo) presents relatively little danger because of the close interdependence of the radioactive caesium take-up from the soil by the plants and its retention by the soil. Our research has made it possible furthermore to examine the value of various partial decontamination methods for soils proposed by certain atomic scientists: just as isotopic dilution appears totally inadequate for this purpose, so does it seems that the addition of potassium salts in amounts greater than nutritive optimum is incapable of reducing the absorption of radioactive caesium by the plant. (author) [French] Nous avons recherche, dans divers milieux de culture, comment l'absorption du cesium par l'orge varie avec sa concentration et comment cette absorption peut etre concurrencee par un cation alcalin voisin,le potassium. En outre, nous avons considere la distribution du cesium dans le sol - notamment du cesium radioactif - entre terre et solution, en fonction du taux de cesium. De notre etude ressort une nette opposition entre le comportement de l'orge vis a vis du cesium d'une solution nutritive et vis a vis du cesium d'un sol: sur solution nutritive, la fraction du cesium (radioactif et stable) absorbee par l'orge demeure pratiquement constante en presence de proportions croissantes (relativement petites) de cesium stable; sur sol, la fraction du cesium radioactif absorbee par l'orge a augmente en meme temps que le taux (relativement petit) de cesium stable du sol, en relation avec une selectivite rapidement decroissante du sol pour Cs. La difference entre ces resultats est donc expliquee par une tres forte selectivite du sol illitique experimente pour Cs{sup +} tant que la proportion da cesium reste tres petite, de l'ordre de celle de la plupart des sols naturels. Par ailleurs, l'ion K{sup +} n'a concurrence l

  15. Action of neuro-hypophysis hormones on sodium exchanges of Carassius auratus L; Action des hormones neurohypophysaires sur les echanges de sodium de Carassius auratus L.

    Energy Technology Data Exchange (ETDEWEB)

    Julien, Monique

    1960-06-25

    This academic work reports the use of radio-sodium as indicator of sodium exchanges to simultaneously measure the gill input flow and the output gill and urinary flows. This technique has been applied in the case of a common soft water fish (Carassius auratus L.) to study the possible action of neuro-hypophysis extracts on these flows, and the action of these hormones on urinary excretion [French] Nous avons mesure les echanges de sodium de Carassius auratus a l'aide de radiosodium 24. L'action d'extraits neuro-hypophysaires d'origine diverse a ete comparee a celle d'injection temoin de chlorure de sodium isotonique, aussi bien sur les flux d'entree et de sortie de sodium que sur l'excretion urinaire. De ces experiences faites in vivo, nous pouvons tirer les conclusions suivantes: 1 - L'extrait neurohypophysaire de Carassius auratus provoque une augmentation du flux d'entree de sodium au niveau de la branchie de cet animal alors que le flux de sortie reste inchange. Cet extrait semble plus actif qu'une dose d'ocytocine egale a son activite ocytocique propre. Parmi les hormones neurohypophysaires de mammiferes, seule l'ocytocine (a forte dose) produit une action analogue a celle decrite ci-dessus. L'extrait de Rana esculenta reste sans action. Nous en avons conclu a l'existence dans la neurohypophyse de Carassius auratus d'un facteur hormonal agissant au niveau de la branchie pour controler l'osmoregulation de ce poisson. 2 - Les extraits neurohypophysaires de Carassius auratus entrainent chez l'animal une augmentation de la diurese et de la concentration de sodium de l'urine. Cependant cette action reste discrete et fugace. Les hormones de mammiferes, et les extraits neurohypophysaires d'amphibiens restent sans action. 3 - D'autres auteurs ont montre que chez les amphibiens, l'action des hormones neurohypophysaires se traduit a la fois par une augmentation du transport actif de sodium a travers la peau et par un desequilibre de la balance hydrique (augmentation du

  16. Study with radio-sulphur of the kinetics of the process SO{sub 2} + 0.5 O{sub 2} {r_reversible} SO{sub 3} in a state of chemical equilibrium on a platinum catalyst; Etude, a l'aide du soufre radioactif, de la cinetique de la reaction SO{sub 2} + 0,5 O{sub 2} {r_reversible} SO{sub 3} en equilibre chimique, en presence d'un catalyseur de platine; Issledovanie pri pomoshchi radioaktivnoj sery kinetiki protsessa SO{sub 2} + 0,5 O{sub 2} {r_reversible} SO{sub 3}, nakhodyashchegosya v sostoyanii khimicheskogo ravnovesiya, na platinovom katalizatore; Estudio, con ayuda de azufre radiactivo, de la cinetica de la reaccion SO{sub 2} + 0,5 O{sub 2} {r_reversible} SO{sub 3} en equilibrio quimico en presencia de un catalizador de platino

    Energy Technology Data Exchange (ETDEWEB)

    Rojter, V A; Stukanovskaya, N A; Kornejchuk, G P

    1962-03-15

    The authors describe an attempt to use radioisotopes in the study of the kinetics of heterogeneous catalytic processes in a state of equilibrium. The investigation was carried out by the circulation method. After establishment of equilibrium, a small amount of S{sup 35}O{sub 2} was introduced into the system as a tracer and its conversion rate into S{sup 35}O{sub 3} was measured. From that rate the speed of the direct and inverse processes of oxidation of SO{sub 2} on the catalyst was calculated. Possible sequence patterns for the process are suggested and discussed. (author) [French] Le memoire expose un essai d'application des radioisotopes a l'etude de la cinetique des reactions catalytiques heterogenes en equilibre chimique. Les recherches ont ete effectuees par la methode a circulation. Apres etablissement de l'equilibre, on a introduit comme indicateur une petite quantite de {sup 35}SO{sub 2} et mesure la vitesse de sa transformation en {sup 35}SO{sub 3}. En partant de cette vitesse, on a calcule celle du processus d'oxydation directe et inverse du SO{sub 2} sur le catalyseur. Les auteurs proposent et etudient differentes formules selon lesquelles la reaction peut se derouler. (author) [Spanish] Los autores describen un experimento sobre el empleo de radioisotopos en el estudio de la cinetica de procesos cataliticos heterogeneos en estado de equilibrio. La investigacion se llevo a cabo por el metodo de circulacion. Una vez establecido el equilibrio, se introdujo en el sistema una pequena cantidad de {sup 35}SO{sub 2} como trazador y se midio su indice de conversion en {sup 35}SO{sub 3}. De dicho indice se dedujo la velocidad de los procesos directo e inverso de oxidacion del SO{sub 2} en presencia del catalizador. Los autores proponen y examinan diversos tipos posibles de cinetica para el proceso. (author) [Russian] Izlagaetsya opyt primeneniya radioaktivnykh izotopov dlya izucheniya kinetiki geterogennykh kataliticheskikh protsessov, nakhodyashchikhsya v sostoyanii ravnovesiya. Issledovanie provodilos' tsirkulyatsionnym metodom. Posle ustanovleniya ravnovesiya v sistemu vvodilos' v kachestve metki maloe kolichestvo S{sup 35}O{sub 2} i izmeryalas' skorost' perekhoda ego v S{sup 35}O{sub 3}. Iz ehtoj skorosti vychislyalas' skorost' pryamogo i obratnogo protsessov okisleniya SO{sub 2} na katalizatore. Predlozheny i obsuzhdeny vozmozhnye skhemy protekaniya protsessa. (author)

  17. Production of C{sup 14}-labelled compounds from C{sup 14}O{sub 2} accelerated in an electric field - Physico-chemical analysis of some radioactive compounds obtained; Production de composes marques au {sup 14}C a partir de {sup 14}CO{sub 2} accelere dans un champ electrique - Analyse physico-chimique de quelques composes radioactifs obtenus; Proizvodstvo mechennykh uglerodom-14 soedinenij iz C{sup 14}O{sub 2}, uskorennogo v ehlektricheskom pole - Fiziko-khimicheskij analiz neskol'kikh poluchennykh radioaktivnykh soedinenij; Obtencion de compuestos marcados con {sup 14}C a partir de {sup 14}CO{sub 2} acelerado en un campo electrico - Analisis fisicoquimico de algunos de los compuestos radiactivos obtenidos

    Energy Technology Data Exchange (ETDEWEB)

    Guillaume, M [Universite de Liege, Belgique (Belgium)

    1962-03-15

    This paper describes a method of labelling which is based on the acceleration by an electric field of C{sup 14}O{sub 2}, which can then react with an organic target in its path. The discharge cell described operates at 500 Y, 150 {mu}A, and the organic products to be labelled are exposed to this field for about three hours with CO{sub 2} having a specific activity of 24mc/mmole. The maximum yield remains low (about 6%), and 60% of the C{sup 14}O{sub 2} is destroyed. This maximum activity is obtained only for aliphatic chains (50 {mu}c/g for glutaric acid) or for aromatic substances with an aliphatic chain (acetyl-salicylic acid). (author) [French] Le present memoire expose une methode de marquage basee sur l'acceleration par un champ electrique de {sup 14}CO{sub 2}, qui est alors susceptible d'entrer en reaction avec une cible organique se trouvant dans sa trajectoire. La cellule a decharge decrite fonctionne sous 500 V, 150 {mu}A, et les produits organiques a marquer sont soumis a ce champ pendant environ trois heures, avec du CO{sub 2} d'activite specifique 24 mc/mmole. Le rendement maximum obtenu reste faible (6% environ), et 60% du {sup 14}CO{sub 2} est detruit. Ce rendement maximum n'est obtenu que pour les chaines aliphatiques (50 {mu}c/g pour l'acide glutarique) ou pour des substances aromatiques presentant une chaine aliphatique (acide acetylsalicylique). (author) [Spanish] La memoria describe un metodo de marcacion que consiste en acelerar {sup 14}CO{sub 2} en un campo electrico para que pueda reaccionar con blancos constituidos por sustancias organicas colocadas en su trayectoria. La celda de descarga que describe la memoria funciona a 500 V y 150 {mu}A, y los productos organicos que se desean marcar se exponen al campo asi creado durante unas tres horas a CO{sub 2} de una actividad especifica de 24 mc/mmol. El rendimiento maximo obtenido es bajo (aproximadamente 6%) y el 60% del {sup 14}CO{sub 2} queda destruido. Este rendimiento maximo solo se alcanza con cadenas alifaticas (50 {mu}c/g para el acido glutarico) o con moleculas ciclicas que presenten una cadena alifatica (acido acetilsalicilico). (author) [Russian] V dannoj rabote izlagaetsya metod mecheniya, osnovannyj na uskorenii ehlektricheskim polem C{sup 14}O{sub 2}, kotoryj v ehto vremya poddaetsya vstupleniyu v reaktsiyu s organicheskoj mishen'yu, nakhodyashchejsya na ego traektorii. Opysyvaemaya razryadnaya kamera dejstvuet pod napryazheniem 500 v, 150 mka, a podlezhashchie mecheniyu organicheskie veshchestva vvodyatsya v ehto pole i nakhodyatsya tam okolo 3 chasov vmeste s CO{sub 2} udel'noj aktivnosti v 24 mkyuri/mmol'. Maksimal'nyj vykhod poluchennykh produktov ostaetsya slabym (okolo 6%), a 60% C{sup 14}O{sub 2} - razrusheno. EHtot maksimal'nyj vykhod poluchaetsya tol'ko dlya alifaticheskikh tsepej (50 mkkyuri/r dlya glutarovoj kisloty) ili dlya aromaticheskikh veshchestv, predstavlyayushchikh alifaticheskuyu tsep' (atsetilgalitsilovuyu kislotu). (author)

  18. Proposition of resolution aiming at the creation of an inquiry commission relative to the safety of the french nuclear installations and the protection of inhabitants face to the risks of radioactive contaminations coming to uranium leakages or any other product used in the nuclear power plants and the radioactive waste storage facilities; Proposition de resolution tendant a la creation d'une commission d'enquete relative a la securite des installations electro-nucleaires francaises et la protection des habitants face aux risques de contaminations radioactives dues aux fuites d'uranium ou de tout autre produit utilise dans les centrales nucleaires et les installations de stockage de dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    This commission will have for mission to establish the facts relative to the Tricastin accident and the previous pollutions around this site; to appreciate the delay, the transparency and the public information modalities, both by the company and by the authorities; to establish a systematic and precise statement of the radioactive contaminations on the sites and around the french nuclear facilities ( included the waste storage sites); to measure the ecological damages on the ecosystems and the sanitary risks for the populations; to evaluate the prevention programmes management and the safety of these facilities; to identify the dysfunctions of the french nuclear sector and give propositions to improve the safety of these facilities. (N.C.)

  19. The HAW project: demonstration facility for the disposal of high-level waste in salt

    International Nuclear Information System (INIS)

    Rothfuchs, T.

    1991-01-01

    This report is the so-called Synthesis report 1985-1989 of the international HAW project performed in the 800 m level of the ASSE salt mine in the Federal Republic of Germany. The major objective of this project is the pilot testing and demonstration of safe methods for the final disposal of high-level radioactive waste in geological salt-deposits. The HAW-project is carried out by the GSF-Institut fuer Tieflagerung (IFT) in cooperation with the French Agence Nationale pour la Gestion des Dechets Radioactifs (ANDRA); the Spanish Empresa Nacional de Residuos Radioactivos S.A (ENRESA) and the Netherlands Energy Research Foundation (ECN). During the years 1985 to 1989 the underground test field was excavated and after some delays in the licensing procedure, the emplacement of 30 vitrified highly radioactive canisters (containers) is now envisaged for early 1991. 32 refs; 76 figs., 11 tabs

  20. The role of the operator of nuclear power plants in disposal of nuclear waste

    International Nuclear Information System (INIS)

    Chaussade, J.P.

    1995-01-01

    Public opinion polls show that the French have largely understood the importance of our nuclear programme in maintaining French independence with regard to power supply and its security and that they have confidence in the technicians for the proper construction and operation of these power plants, but that they retain many questions concerning the disposal of nuclear waste. They have the impression that solutions remain to be found, and especially that the Electricite de France (EDF) devised the nuclear power programme without concern for the disposal of waste. This lack of information is fortunately far from reality, EDF, under the supervision of the security authorities, manages the waste produced in the nuclear power plants. Final stocking of waste is handled by a body that is independent of the waste producer, the ''Agence nationale pour la gestion des dechets radioactifs'' (Andra) (National Agency for the Management of Radioactive Waste). (author). 7 refs., 1 tab

  1. Méthodologie d’analyse des signaux et caractérisation hydrogéologique : application aux chroniques de données obtenues aux laboratoires souterrains du Mont Terri, Tournemire et Meuse/Haute-Marne

    OpenAIRE

    Fatmi, Hassane

    2009-01-01

    Ce rapport présente des méthodes de prétraitement, d'analyse statistique et d'interprétation de chroniques hydrogéologiques de massifs peu perméables (argilites) dans le cadre d'études sur le stockage profond de déchets radioactifs. Les séries temporelles analysées sont la pression interstitielle et la pression atmosphérique, en relation avec différents phénomènes (marées terrestres, effet barométrique, évolution de l'excavation des galeries). Les pré-traitements permetten...

  2. 2006-2009: 4 years of research at the ANDRA for storage projects

    International Nuclear Information System (INIS)

    2010-01-01

    This report gives an overview of research activities performed by the ANDRA (Agence nationale pour la gestion des dechets radioactifs, the French national agency for the management of radioactive wastes). These activities concern several axis: the consolidation of previously obtained data and the performance of long duration experimentations to support modelling studies, technological tests and implementation of storage control and survey means, a more precise assessment of safety margins through a finer assessment of the behaviour and evolution of the storage and of its components, development of numerical simulations, and the definition of a precise location for a possible storage. These activities are here reported according to different themes: storage reversibility as it is perceived by social and human sciences, conceptualisation of the geological media and of the associated biosphere, storage and its interactions with the environment, transfer phenomena within a storage, survey and control of a storage and of its environment, storage performance assessment, publications and scientific valuation

  3. Presentation the national Plan of management of radioactive materials and wastes. Friday, the 4. of June 2010

    International Nuclear Information System (INIS)

    2010-01-01

    After a synthesis of the national plan of management of radioactive materials and wastes (PNGMDR for Plan national de gestion des matieres et des dechets radioactifs), this document contains the main conclusions of this plan for the period 2010-2012, a presentation of its elaboration modalities, a presentation of the basic principles regarding radioactive materials and wastes (definitions, origins, waste types and categories, waste management types), a presentation of the main actors of their management (agencies, ministries, authorities, research organizations, institutional bodies, associations). A glossary and other documents are provided, notably a presentation of the ASN (the French Nuclear Safety Authority), a report by the ANDRA agency giving an inventory of radioactive materials and wastes, and a chapter of a report on nuclear safety and radioprotection status in France in 2009

  4. Study of the migration of radioactive elements in soils ''in-place''

    International Nuclear Information System (INIS)

    Bovard, P.; Grauby, A.

    The problems of medium protection against radioactive contamination hazards have led the Commissariat a l'Energie Atomique--Service de Controle des Radiations et de Genie Radioactif to study the behavior of ions in soils. There are many theoretical researches and laboratory studies on the movement of radioelements in soil. But, with the difficulties for obtaining a similar result in field, we have developed a simple direct method of in place soil contamination. However, a principal drawback remains, the necessity to extrapolate from one or two reduced size samples to a large area. This is all the problem of sampling, which is not specific of our method. However, a choice justified by classical data, let us obtain a sufficient number of results and an accuracy which is suitable

  5. The Waste Negotiator's mission

    International Nuclear Information System (INIS)

    Bataille, Christian

    1993-01-01

    The mission of the Waste Negotiator is to seek out sites for deep underground laboratories to study their potential for disposal of high level radioactive waste. Although appointed by the government, he acts independently. In 1990, faced by severe public criticism at the way that the waste disposal was being handled, and under increasing pressure to find an acceptable solution, the government stopped the work being carried out by ANDRA (Agence nationale pour la gestion des dechets radioactifs) and initiated a full review of the issues involved. At the same time, parliament also started its own extensive investigation to find a way forward. These efforts finally led to the provision of a detailed framework for the management of long lived radioactive waste, including the construction of two laboratories to investigate possible repository sites. The Waste Negotiator was appointed to carry out a full consultative process in the communities which are considering accepting an underground laboratory. (Author)

  6. Study of the migration of radioactive elements in soils ''in-place''

    Energy Technology Data Exchange (ETDEWEB)

    Bovard, P.; Grauby, A.

    The problems of medium protection against radioactive contamination hazards have led the Commissariat a l'Energie Atomique--Service de Controle des Radiations et de Genie Radioactif to study the behavior of ions in soils. There are many theoretical researches and laboratory studies on the movement of radioelements in soil. But, with the difficulties for obtaining a similar result in field, we have developed a simple direct method of in place soil contamination. However, a principal drawback remains, the necessity to extrapolate from one or two reduced size samples to a large area. This is all the problem of sampling, which is not specific of our method. However, a choice justified by classical data, let us obtain a sufficient number of results and an accuracy which is suitable.

  7. Upgrade of the SPIRAL identification station for high-precision measurements of nuclear β decay

    Science.gov (United States)

    Grinyer, G. F.; Thomas, J. C.; Blank, B.; Bouzomita, H.; Austin, R. A. E.; Ball, G. C.; Bucaille, F.; Delahaye, P.; Finlay, P.; Frémont, G.; Gibelin, J.; Giovinazzo, J.; Grinyer, J.; Kurtukian-Nieto, T.; Laffoley, A. T.; Leach, K. G.; Lefèvre, A.; Legruel, F.; Lescalié, G.; Perez-Loureiro, D.

    2014-03-01

    The low-energy identification station at SPIRAL (Système de Production d'Ions Radioactifs Accélérés en Ligne) has been upgraded for studying the β decays of short-lived radioactive isotopes and to perform high-precision half-life and branching-ratio measurements for superallowed Fermi and isospin T=1/2 mirror β decays. These new capabilities, combined with an existing Paul trap setup for measurements of β-ν angular-correlation coefficients, provide a powerful facility for investigating fundamental properties of the electroweak interaction through nuclear β decays. A detailed description of the design study, construction, and first results obtained from an in-beam commissioning experiment on the β+ decays 14 O and 17F are presented.

  8. Storage of plugs and experimental devices from reactors; Stockage des bouchons et dispositifs experimentaux en provenance des reacteurs (1961)

    Energy Technology Data Exchange (ETDEWEB)

    Cerre, P; Mestre, E [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1961-07-01

    - Within the general programme of storage and treatment of radioactive waste produced by the various operations carried out in an atomic center, it is useful to consider separately the problem of certain waste from reactors, which, because of its size and physical nature, has to be stored with a view to being later treated and finally evacuated. The solution which we propose for this storage problem is presented in this paper. (authors) [French] - Dans le cadre du stockage et du conditionnement des dechets radioactifs provenant des diverses manipulations effectuees dans un centre atomique, il y a lieu de considerer a part certains dechets des reacteurs qui, par leur dimension et leur nature physique doivent etre stockes en vue de leur reprise ulterieure pour un conditionnement et une evacuation definitifs. La solution que nous avons apportee a ce stockage fait l'objet de l'expose qui suit. (auteurs)

  9. La catastrophe nucléaire de Tchernobyl entre erreurs humaines et défauts techniques

    CERN Document Server

    Perrineau, Aude

    2015-01-01

    Découvrez enfin tout ce qu'il faut savoir sur la catastrophe nucléaire de Tchernobyl en moins d'une heure ! Le 26 avril 1986 à 1 h 23, une catastrophe d'un nouveau genre ébranle le monde : un réacteur de la centrale nucléaire de Tchernobyl explose. Alors que les autorités soviétiques camouflent l'accident, puis en minimisent l'importance, un nuage radioactif se forme et se propage sur toute l'Europe…Ce livre vous permettra d'en savoir plus sur : Le contexte de l'époque Les acteurs majeurs qui ont participé à l'événement La catastrophe nucléaire de Tchernobyl Les répercussions du drameLe mot

  10. Synthesis of a polycyclic aromatic hydrocarbon marked with carbon-14: (b, d e f) dibenzo-chrysene {sup 14}C-7,14; Synthese d'un hydrocarbure aromatique polycyclique marque au carbone 14: le dibenzo (b, d e f) chrysene {sup 14}C-7,14

    Energy Technology Data Exchange (ETDEWEB)

    Chatelain, G [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1965-07-01

    (b, d e f) dibenzo-chrysene C-7,14 has been synthesized from radioactive carbon dioxide and the organic magnesium compound derived from 1,5 dibromo naphthalene. The product has been purified by a very precise series of fractionated chromatographs on alumina having a chromatographic activity. This has necessitated the development of a special technique. (author) [French] Le dibenzo (b, d e f) chrysene 14C-7,14 a ete synthetise au depart de gaz carbonique radioactif et de bis-organomagnesien derive du dibromo-1,5 naphtalene. Le produit a ete purifie par une serie de chromatographies fractionnees sur alumine d'activite chromatographique tres precise. Ceci a fait l'objet d'une mise au point de technique. (auteur)

  11. Health physics during work on the G. 2 and G. 3 reactor exchanges; La radioprotection des travaux sur les echangeurs des piles G. 2 et G. 3

    Energy Technology Data Exchange (ETDEWEB)

    Rodier, J; Chassany, J; Guillermin, P [Commissariat a l' Energie Atomique, Centre de Production de Plutonium, Marcoule (France). Centre d' Etudes Nucleaires

    1965-07-01

    During this work and its preparation, which took place first at G. 2 and then at G. 3 over a period of 11 months, 15000 measurement results were obtained. Their analysis, together with a consideration of the organisation on the site and of the conclusions drawn from the experiment, shows the various factors which determine the importance of the radio-active dangers. (authors) [French] Au cours de ces travaux et de leur preparation, qui ont eu lieu successivement a G. 3 puis a G. 2, pendant 11 mois, 15 000 resultats de mesures ont ete obtenus. Leur etude, mise en parallele avec l'organisation du chantier et les enseignements tires de l'experience, met en evidence les divers facteurs conditionnant les niveaux de risques radioactifs. (auteurs)

  12. Research strategies and programs related to the National Plan of Management of Radioactive Materials and Wastes. Issue 2008

    International Nuclear Information System (INIS)

    2008-01-01

    After having recalled the legal context defining the requirements of the PNGMDR (Plan national de gestion des matieres et dechets radioactifs, national plan of management of radioactive materials and wastes), this report presents several research programs which address various domains: waste packaging and behaviour (decontamination, waste characterization, waste processing, the storage sizing inventory model, parcel behaviour, used fuel evolution, future wastes), warehousing and storage in deep geological formation (characterization of the Meuse/Haute-Marne site, scientific program, simulation programs, measurement means for storage monitoring, knowledge base, security and reversibility options for storage design, security studies, warehousing options), storage of radiferous and graphite wastes, investigation of separation/transmutation scenarios, investigations related to separation, investigations related to fuel fabrication, investigations related to the transmutation of minor actinides, researches in social and human sciences

  13. Characterization of conditioned low- and intermediate-level wastes

    International Nuclear Information System (INIS)

    Alexandre, D.; Pottier, P.; Billon, A.; Bourdrez, J.; Nomine, J.C.; Tassigny, C. de

    1983-01-01

    All radioactive wastes must be conditioned to satisfy the criteria for disposal of them in the ground. In accordance with the specifications laid down by the Agence nationale pour la gestion des dechets radioactifs (French National Agency for Radioactive Waste Management - ANDRA), waste characterization records must be drawn up, with the relevant tests being carried out under approved conditions. The paper summarizes the principal results acquired in laboratories of the French Atomic Energy Commission (CEA) under the characterization programme, which was initiated by ANDRA and to which the Commission of European Communities (CEC) has contributed within the framework of its five-year indirect-action programme (1980-84). The principal aspects of these characterization tests are concerned with leaching from normal-sized packages, techniques measuring the radioisotope diffusion rate in thermosetting resins, study of the chemical forms of the radioisotopes released and assessment of the resistance of the coatings to the action of micro-organisms in the soil. (author)

  14. The HAW project: demonstration facility for the disposal of high-level waste in salt

    International Nuclear Information System (INIS)

    Rothfuchs, T.

    1991-01-01

    This publication is the interim report 1988-89 of the international HAW project performed in the 800 m level of the Asse salt mine in the Federal Republic of Germany. The major objective of this project is the pilot testing and demonstration of safe methods for the final disposal of high-level radioactive waste in geological salt deposits. The HAW-project is carried out by the GSF-Institut fuer Tieflagerung (IFT) in cooperation with the French Agence Nationale pour la Gestion des Dechets Radioactifs (ANDRA); the Spanish Empresa Nacional de Residuos Radiactivos S.A. (ENRESA) and the Netherlands Energy Research Foundation (ECN). After some delays in the licensing procedure the emplacement of 30 vitrified highly radioactive canisters (containers) is now envisaged for early 1991. 20 refs.; 92 figs.; 14 tabs

  15. Hearing of Mrs Marie-Pierre Comets and Mr Marc Sanson, commissioners of the Nuclear Safety Authority (ASN), as well as Mrs Marie-Claude Dupuis, general manager of the National Agency for the management of radioactive wastes (ANDRA), on the nuclear events in Cadarache

    International Nuclear Information System (INIS)

    2009-01-01

    Representatives of the French Nuclear Safety Authority (ASN, Autorite de Surete Nucleaire) and of the French National Agency for the Management of Radioactive Wastes (ANDRA, Agence nationale pour la gestion des dechets radioactifs) answer questions about an incident which occurred in a workshop, where MOx fuel was produced and which is now being dismantled. It appeared that the amount of plutonium present in the gloveboxes has been largely under-assessed: 8 kg were expected, 22 kg of plutonium have already been recovered, and finally 39 kg might be recovered by the end the dismantling operations. Other issues are addressed like the ANDRA's projects of radioactive material geological storage, their technical and institutional aspects, and then again about the late declaration of the Cadarache incident

  16. {beta} {gamma} porch detector; Detecteur portique {beta} {gamma}

    Energy Technology Data Exchange (ETDEWEB)

    Roulet, R [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

    1963-07-01

    This device is to be placed at the outside of reactors, hot laboratories and others where radioactive products are treated; it is intended to give the alarm when someone, passing through the porch is greatly contaminated, or carries, without his knowing, a radioactive substance. Being to be used in places where there might be an important ground noise, this device is provided with an automatic offset of this noise; an adjusting system of sensitivity allows to obtain a 15 {mu}Ci in {gamma} and 10 {mu}Ci in {beta} radioactive source, passing through the porch at the normal speed at which man is walking. A battery, set in buffer, allows working of the device, even when current is off. (author) [French] Cet appareil est destine a etre place a la sortie des reacteurs, laboratoires chauds ou autres laboratoires travaillant sur des produits radioactifs; son but est de donner une alarme lorsque quelqu'un, passant sous le portique, presente une forte contamination, ou surtout transporte par inadvertance un corps radioactif. Cet appareil devant etre utilise dans les lieux ou peut regner un bruit de fond important, possede une compensation automatique de ce bruit de fond; un reglage de la sensibilite permet d'obtenir au mieux un declenchement pour une source. de 15 {mu}Ci en {gamma} et 10 {mu}Ci en {beta} passant sous le portique a la vitesse normale d'un homme qui marche. Une batterie montee en tampon permet a l'appareil de fonctionner meme en cas de coupure de courant. (auteur)

  17. Problems presented by the filtration and sampling of aerosols in the atomic energy programme; Problemes poses par la filtration et le prelevement des aerosols dans le cadre de l'energie atomique

    Energy Technology Data Exchange (ETDEWEB)

    Cochinal, R [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1959-07-01

    The maximum permissible limits for radioactive aerosols are much lower than those for aerosols encountered in the non-nuclear industries. These limits depend on numerous factors such as: nature of the radiation, half-life, etc. The radioactive aerosols can be prepared by various methods. The filtering of the air in high activity laboratories or in plutonium treatment factories necessitates an installation consisting of: - aspiration filters, - extraction filters of very high efficiency (those used for {alpha} emitter cells: designed to be replaced without incurring contamination risks; those used for {gamma} emitter cells: designed to be replaced by remote control). The filtering in nuclear reactors is also effectuated by filter papers: - the G1 reactor with open circuit: the air coolant is entirely filtered at the entry and on leaving; - the G2, G3 and EDF1 reactors with closed circuits: filtering under pressure of a small portion of the coolant gas. (author) [French] Les limites maxima permises des aerosols radioactifs sont beaucoup plus faibles que celles des aerosols rencontres dans l'industrie classique. Elles dependent de nombreux facteurs tel que: nature du rayonnement, periode radioactive, etc... La formation des aerosols radioactifs est de nature diverse. La filtration des laboratoires de haute activite, ou d'usines d'elaboration de plutonium conduit a des types d'installations comportant: - des filtres d'aspiration; - des filtres d'extraction a rendement extremement eleve (type pour cellules emettrices {alpha} concu pour etre change sans risque de contamination, type pour cellules emettrices {gamma}: concu pour etre change a distance) La filtration des reacteurs nucleaires sont egalement effectuee par des papiers filtres: - reacteur G1 a circuit ouvert: air de refroidissement totalement filtre a l'aspiration et a l'extraction; - reacteurs G2, G3, EDF1: a circuit ferme: filtration sous pression d'une faible partie du gaz de refroidissement. (auteur)

  18. Fast neutron distributions from Be and C thick targets bombarded with 80 and 160 MeV deuterons

    International Nuclear Information System (INIS)

    Pauwels, N.; Laurent, H.; Clapier, F.; Brandenburg, S.; Beijers, J. P .M.; Zegers, R. G. T.; Lebreton, H.; Saint-Laurent, M.G.; Mirea, M.

    2001-01-01

    Production of fast neutron studies have come to the fore in the past few years because of the great interest for the possible applications of induced fission to produce neutron rich ion beams. In this context, the main objective of the SPIRAL II (Systeme de Production d'Ions Radioactifs Acceleres en Ligne) and PARRNe (Production d'Atomes Radioactifs Riches en Neutrons) R and D projects is the investigation of the feasibility and of the optimum parameters for a neutron rich isotope source. Special attention is dedicated to the energy and angular distributions of the neutrons obtained through deuteron break--up in different types of converters and different incident energies. Analysis and modelling of such behaviors, together with the study of the yields of neutron induced fission, can be used to optimize the productivity of the fissioning target its geometry and designing it accordingly. The present report continues our previous studies realised for 17, 20, 28 and 200 MeV deuteron energies and it is focused on deuteron incident energies of 80 and 160 MeV. In the experiment, the double differential cross section for neutron production induced by 80 and 160 MeV deuterons impinging on thick C and Be targets, in which the incident deuterons were complete stopped, have been measured. The energy of the neutrons was determined from the time--of--flight (TOF) measurement. To obtain an energy resolution of about 4% for the fastest, forward--emitted neutrons, which have approximately beam velocity, the length of the flightpath for the detectors at angles up to 30 angle was chosen to be 6 m. At backward angles, where the neutron energies are lower, a shorter flightpath was chosen. A schematic drawing of the setup is shown. A 100 mm thick Be target and a 70 mm thick C target were used. Results are exemplified with the angular and energy distributions of neutron obtained for Be target at 80 MeV. (authors)

  19. Why the search for uranium should continue; Pourquoi continuer a chercher de l'uranium

    Energy Technology Data Exchange (ETDEWEB)

    Mabile, J; Gangloff, A [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1964-07-01

    production suppriment les soucis immediats d'approvisionnement. Cependant, le potentiel en uranium de la France aux cours raisonnablement envisageables semble limite, n'assurant que quelques decennies de production. Ce desequilibre est plus grave encore pour l'ensemble de l'Europe, au moment meme ou on assiste au debut de l'expansion rapide de l'energie atomique. Sur un plan mondial, on peut envisager qu'a la suite des fermetures des mines, l'equilibre entre production et consommation sera atteint dans dix ans, l'augmentation de la production etant alors aisement satisfaite par les reouvertures des mines momentanement fermees. Mais, des 1980, la demande depassera la capacite de production maxima installee en 1960-1961. Enfin, vers la fin du siecle, il y a disproportion entre les reserves d'Urnnium necessaires et celles qui ont ete decouvertes jusqu'a present dans le monde au prix des efforts considerables des annees 1948-1958. On ne saurait trop tot se preoccuper de la decouverte de nouvelles ressources: soit dans des pays non encore prospectes, soit par l'utilisation de methodes plus fines, faute de quoi le marche de l'uranium, durement secoue par la surproduction actuelle, subira de nouvelles secousses si l'industrie miniere n'est pas preparee longtemps a l'avance a une progression exponentielle rapide apres 1975-1980. (auteur)

  20. Study of the age of uranium-containing mineral deposits in the Limouzat, the bois-noir mountains (12963); Etude des ages des mineralisations uraniferes du gisement du Limouzat, Massif des bois-noirs (1963)

    Energy Technology Data Exchange (ETDEWEB)

    Durand, G [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1963-07-01

    The present work is concerned with 7 different samples taken at various levels in the Limouzat mine in the Bois-Noirs mountains. It has been possible to show that the uranium dates from 265 M.Y. and that a rearrangement occurred 65 M.Y. ago. A {gamma}-spectrometer study which was originally intended to show the existence of the lack of balance in the radon circulation, has made it possible to show that the {gamma} spectra recorded on various samples could be erroneous. We observed in effect that the presence of lead, iron, etc., had a strong influence on the {gamma} spectrum of the radium family, whereas all research workers have considered that concentrations in the uranium ore were negligible and had no significant effect on the study of the {gamma} spectra of the samples. It is obvious that an interesting study has to be undertaken on the screen effects of the different cations existing in the ores. We believe that it is possible to show the presence of certain elements directly by {gamma}-spectrometry. The ages measured with the mass spectrometer present two types of disagreement but these have been explained by considering that there occurred a first arrival of lead followed by a rearrangement and, at certain points, a second arrival at this date. Finally, the deposit studied undergoes a circulation of uranium and of radon. (author) [French] La presente etude a porte sur 7 prelevements differents effectues a divers niveaux de la mine du Limouzat, massif des Bois-Noirs. Elle a permis de mettre en evidence une premiere venue d'uranium il y a 265 M.A., suivie d'un remaniements il y a 65 M.A. Une etude au spectrometre {gamma} destinee, a l'origine, a prouver les desequilibres dus aux circulations de radon a permis de montrer que les spectres {gamma} enregistres sur divers echantillons pouvaient etre entaches d'erreurs. Nous nous sommes apercus en effet que la presence de plomb, de fer..., avait une forte influence sur le spectre {gamma} de la famille du radium

  1. Radioprotection problems resulting from the presence of experimental devices around an atomic reactor; Problemes de radioprotection poses par l'implantation de dispositifs experimentaux aupres d'une pile atomique

    Energy Technology Data Exchange (ETDEWEB)

    Fitoussi, L; Lebouleux, Ph; Bricard, Ph; Moreau, A [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1965-07-01

    The setting up of experimental devices around a reactor produces dangers of irradiation and radioactive contamination which can become very great in the case of an accident, especially if the in-pile portion contains fissile matter. This may result in irradiation of personnel, prohibition of access to the experimental zones until the sources of irradiation and contamination have been eliminated, and a prolonged stoppage of the reactor. The plans for an in-pile experiment should take into account radioprotection factors; the aim of these is to reduce to a minimum the radioactive risks normally encountered during the experiment and to eliminate any risks of bad accidents and their consequences. In this report are classified the various types of experiments requiring installations outside the pile itself; for each of these experiments the particular radioprotection factors are given. In order to make possible a study of the radioactive dangers likely to arise during a projected experiment, the authors summarize the physical and technical data required by radioprotection specialists and give the rules and general advice concerning radioprotection which should be useful during the planning of an in-pile experiment and the setting-up of the equipment. (authors) [French] L'implantation de dispositifs experimentaux aupres des reacteurs cree des risques d'irradiation et de contamination radioactive qui peuvent devenir importants en cas d'accident, surtout si la partie en pile comprend des matieres fissiles. Il peut en resulter des irradiations de personne, l'interdiction des aires experimentales jusqu'a elimination des sources d'irradiation et de contamination, un arret prolonge de la pile. L'etude d'un projet d'experience en pile doit donc tenir compte des considerations de radioprotection dont le souci est de reduire aux niveaux tolerables les risques radioactifs inherents au fonctionnement normal de l'experience et d'eliminer les risques d'accidents graves et leurs

  2. The cholesterol space of the rat; L'espace cholesterol du rat

    Energy Technology Data Exchange (ETDEWEB)

    Chevallier, F [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1959-07-01

    The experiments consisted in feeding daily to rats the same mass of radioactive cholesterol, over variable time intervals. From the evolution of the specific radioactivity of cholesterol carbon-14 in the organs as a function of time, information relative to the transport of cholesterol in the organism may be obtained. 1) The cholesterol space, defined as the group of molecules capable of being transferred from the organs into the serum and vice versa, represents at the most 50 per cent of the total cholesterol of the adult rat. 2) The incessant interchange between the tissual and the serum cholesterol renews entirely or for the most part the cholesterol molecules contained in the following organs: spleen, heart, adipose tissue, suprarenal glands, lungs, bone marrow, liver, erythrocytes. For a second group of organs: skin, testicles, kidneys, colon, bones, muscles, only a fraction of their cholesterol is renewable by this process. No transfer can be detected at the level of the brain. 3) The relative speeds of the various means of appearance (absorption, synthesis) and disappearance (excretion, transformation) of the cholesterol from its space are such that a stationary isotopic state is established around the eighth day, when the animal absorbs 5 milligrams of radioactive cholesterol daily. (author) [French] Les experiences ont consiste a faire ingerer quotidiennement une meme masse de cholesterol radioactif a des rats, durant des laps de temps variables. L'evolution de la radioactivite specifique du carbone-14 du cholesterol des organes en fonction du temps permet d'obtenir des renseignements relatifs au transport du cholesterol dans l'organisme. 1) L'espace cholesterol defini comme l'ensemble des molecules susceptibles d'etre transferees des organes dans le serum, et vice-versa, represente au plus 50 pour cent du cholesterol total du rat adulte. 2) Le va et vient incessant entre le cholesterol tissulaire et le cholesterol serique renouvelle en totalite ou en

  3. Application of radioactivity to subterranean hydraulic engineering (1961); Application de la radioactivite a l'hydraulique souterraine (1961)

    Energy Technology Data Exchange (ETDEWEB)

    Hours, R [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1961-07-01

    The search for radioactive tracers for water capable of percolating through permeable grounds without significant absorption has led to the choosing of two isotopes, bromine 82 (half-life 36 hours) and iodine (half-life 8 days), both {gamma} emitters; various combinations of other {gamma} emitters with longer half-lives have been tried but with only partial success. The recent progress in the dosage of tritium should make it possible to widen the field of application of this tracer which is unique in its kind. Being detectable at concentrations of 10{sup -6} to 10{sup -8} curies per cubic meter, the radioactive tracers are suitable for all the usual applications of conventional tracers; furthermore, some original techniques have been devised for measurements of flow, of reservoir capacity, of porosity and of permeability. Techniques based on the absorption and scattering of {gamma}-rays have also been developed for the measurement of the density, the humidity and the porosity of soils, and also for their analysis. Up to the present, radioactivity has been mainly applied to the study of oil-bearing formations. Furthermore, the study of the distribution of natural of thermonuclear tritium has contributed greatly to the study of the hydrological cycle. (author) [French] La recherche de traceurs radioactifs de l'eau susceptibles de circuler a travers les terrains permeables sans retention notable a abouti a la selection de deux isotopes, le brome 82 (periodes 36 heures) et l'iode (periode 8 jours), tous deux emetteurs {gamma}; diverses combinaisons mettant en jeu des emetteurs {gamma} de periode plus longue ont ete essayees, mais avec un succes partiel. Les progres recemment accomplis dans le dosage du tritium doivent permettre une rapide extension de l'emploi de ce traceur unique en son genre. Decelables a des concentrations de 10{sup -6} a 10{sup -8} curies par metre cube, les traceurs radioactifs se pretent a toutes les applications des traceurs classiques; de plus

  4. Security problems arising from the use of radioactive sources in the study of the wear in refractory linings; Les problemes de securite dans l'emploi de sources radioactives pour l'etude de l'usure de revetements refractaires

    Energy Technology Data Exchange (ETDEWEB)

    Courtois, G; Hours, R; Le Clerc, P; Pons, A [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1960-07-01

    The determination of the wear in refractories is a problem to which these are at present only a few solutions, and these limited or delicate to use. That is the reason why the use of radioactive tracers contained in the refractory has met with rapid success. Unfortunately, the development of the method has been retarded by the need to limit severely the amounts of radioelement incorporated and also by the observation that diffusion of the radioactive product occurred in the refractory. As a result, the limiting amount of 1 mc/500 metric tons of cast-iron has been adopted in France, with the proviso that no single source exceeds 3 mc. Further, we have made special sources with a view to avoiding diffusion phenomena. The essential feature of these sources is that they use pyro-ceramic a non porous material having a high melting point and being, very inert chemically. In these sources, the radioelement can either be entirely encased in the pyro-ceramic or be an integral part of its composition. A comparative study of the two types of sources is actually under way. (author) [French] La determination de l'usure des refractaires est un probleme dont les solutions sont jusqu'a maintenant peu nombreuses, limitees ou delicates d'emploi. C'est pour cela que l'utilisation de traceurs radioactifs noyes dans le refractaire a connu un vif succes. Malheureusement, le developpement de la methode a ete freine par la necessite de limiter severement la teneur des radioelements incorpores aux produits metallurgiques et egalement par des constatations de diffusion dans le refractaire du produit radioactif. Par suite, la teneur limite de 1 mc/500 tonnes de fonte est maintenant adoptee en France, sans qu'une source individuelle puisse depasser 3 mc. De plus, nous avons realise des sources particulierement etudiees en vue d'eviter des phenomenes de diffusion. Le caractere essentiel de cette realisation est l'utilisation de pyrocerame, materiau non poreux, a haut point de fusion et de

  5. Decontamination of material in the Marcoule plutonium producing centre (1961); La decontamination du materiel dans le centre de production du plutonium de Marcoule (1961)

    Energy Technology Data Exchange (ETDEWEB)

    Rodier, J; Bouzigues, H; Boutot, P [Commissariat a l' Energie Atomique, Centre de Production de Plutonium, Marcoule (France). Centre d' Etudes Nucleaires

    1961-07-01

    The decontamination of material in an atomic centre is an essential operation in view of the cost and the difficulties of replacement. It also makes it possible to reduce the storage of radio-active materials always an expensive task. Surfaces are contaminated by retention of radioactive products and the mechanism of the bounding forces can be explained in terms of chemical, mechanical, electrostatic and surface tension phenomena. The methods used for decontamination are either physical (section, abrasion, steam, ultrasonics) or chemical (acids, alkalis, detergents, reducing and oxidising agents). At Marcoule, chemical methods of treatment are used. This is effected in tanks, the exact composition of the liquids being regulated from a control panel. Working experience has shown that the fact of operating in humid conditions eliminates all problems of atmospheric contamination; as a result it is possible for the personnel to work without any special protective devices. Almost all the material can be re-utilized and the operations produce only a small volume of liquid waste. The decontamination workshop is operated by a small number of workers. The working costs, including capital repayment and treatment of the waste, do not exceed 15 per cent of the value of the apparatus treated. (authors) [French] La decontamination du materiel dans un centre atomique est une operation indispensable etant donne le cout et les difficultes du remplacement. Elle contribue aussi a diminuer les stockages toujours onereux des materiaux radioactifs. Les surfaces se contaminent par retention de corps radioactifs, l'origine des forces de liaison devant etre recherchee dans les phenomenes chimiques, mecaniques, electro-statiques ou de tensions superficielles. Les methodes de decontamination peuvent etre physiques (aspiration, abrasion, vapeur, ultra-sons) ou chimiques (acides, alcalins, detergents, reducteurs, oxydants). Sur le centre de Marcoule, la methode des traitements chimiques a ete

  6. Operating Experience with the BR-5 Reactor; Experience acquise aupres du reacteur BR-5; Opyt ehkspluatatsii reaktora BR-5; Experiencia practica con el reactor BR-5

    Energy Technology Data Exchange (ETDEWEB)

    Lejpunskij, A. I.; Kazachkovskij, O. D.; Pinkhasik, M. S.; Aristarkhov, N. N.; Karpov, A. V.; Larin, E. P.; Efimov, I. A.

    1963-10-15

    The paper discusses the carrying-out of repair and maintenance work on the radioactive liquid-metal circuit of the BR-5 fast neutron reactor. Attention is also given to problems of reactor operation after achievement of the planned 2% fuel burn-up with some disturbance of leak-tightness in individual fuel elements. An account is given of experience in discharging the active section, examining the condition and leak-tightness of the fuel elements, and decontaminating the equipment and piping of the first radioactive circuit after reaching 5% fuel burn-up. (author) [French] Dans ce memoire les auteurs decrivent l'execution des reparations et des travaux d'entretien dans le circuit radioactif liquide-metal du reacteur a neutrons rapides BR-5. Ils etudient egalement les problemes lies au fonctionnement du reacteur au taux de combustion de 2% prevu avec quelques defauts d'etancheite dans des elements combustibles particuliers. Ils decrivent le dechargementen zone active et examinent les conditions d'etancheite des elements combustibles. Ainsi que la decontamination de l'appareillage et des tuyauteries du premier circuit radioactif apres avoir atteint un taux de combustion de 5%. (author) [Spanish] En la memoria se examinan los problemas planteados por el mantenimiento del circuito radiactivo de metal liquido del reactor de neutrones rapidos BR-5. Se tratan cuestiones relacionadas con la explotacion del reactor una vez alcanzado el grado de combustion de 2%, previsto en el proyecto y luego de producirse ciertas alteraciones de la densidad de determinados elementos combustibles. Se describen la experiencia adquirida durante la descarga del cuerpo del reactor, las investigaciones del estado general y de la hermeticidad de los elementos combustibles y las operaciones de descontaminacion de la instalacion y de las tuberias del circuito radiactivo primario despues de alcanzado un grado de combustion de 5%. (author) [Russian] V doklade rassmatrivayutsya voprosy proizvodstva

  7. Fixation of Radioactive Waste in Glass. Part II. The Experimental Evaluation of Phosphate and Borosilicate Glasses; Fixation des Dechets Radioactifs dans le Verre, Deuxieme Partie: Evaluation Experimentale des Verres au Phosphate et au Borosilicate; 0424 0418 041a 0421 0410 0426 0418 042f 0420 0410 0414 0418 041e 0410 041a 0422 0418 0412 041d 042b 0425 041e 0422 0425 041e 0414 041e 0412 0412 0421 0422 0415 041a 041b 0415 . 0427 0410 0421 0422 042c Ii. 042d 041a 0421 041f 0415 0420 0418 041c 0415 041d 0422 0410 041b 042c 041d 0410 042f 041e 0426 0415 041d 041a 0410 041a 0410 0427 0415 0421 0422 0412 0424 041e 0421 0424 0410 0422 041d 042b 0425 0418 0411 041e 0420 041e 0421 0418 041b 0418 041a 0410 0422 041d 042b 0425 0421 0422 0415 041a 041e 041b ; Fijacion de Desechos Radiactivos en Vidrio, Parte II: Evaluacion Experimental de los Vidrios al Fosfato y al Borosilicato

    Energy Technology Data Exchange (ETDEWEB)

    Elliot, M. N.; Grover, J. R.; Hardwick, W. H. [Atomic Energy Research Establishment, Harwell (United Kingdom)

    1963-02-15

    A glass suitable for long-term storage of fission-product wastes must be chosen firstly with regard to the method of storage, and secondly with regard to reliability of manufacture in a highly radioactive plant. The factors that are relevant to storage include leach resistance, thermal and radiation stability and die percentage of waste that can be incorporated, while the physical and chemical nature of glass-forming additives together with the melting point and viscosity of the glass relate to the manufacturing process. The relative importance of these factors is discussed. Experimental studies of the borosilicate glasses that have been chosen for pilot-plant work are described, including the effect of radiation doses of up to 10{sup 12}rad on their physical and chemical properties. Glasses of other kinds have also been examined and their potential value as storage media is compared with the borosilicate glasses. (author) [French] Un verre convenant au.stockage de longue duree des dechets de produits de fission doitetre choisi: premierement, en fonction de la methode de stockage et deuxiemement, eu egard a la securite des operations de traitement dans une usine de haute activite. En ce qui concerne le stockage, les facteurs importants sont la resistance a la corrosion, la stabilite thermique, la stabilite vis a-vis des rayonnements et le pourcentage de dechets pouvant etre incorpores. Au point de vue de la securite des manutentions, il faut tenir compte de la nature physique et chimique des elements intervenant dans la composition du verre, du point de fusion et de la viscosite du verre. Les auteurs examinent l'importance relative de ces facteurs. Ils decrivent les etudes experimentales faites sur les verres au borosilicate choisis pour l'usine pilote, de meme que l'influence des rayonnements sur leurs proprietes chimiques et physiques pour des doses allant jusqu'a 10{sup 12} rad. Ils ont etudie d'autres especes de verre et examine la possibilite de les employer comme milieu de stockage, en les comparant aux verres au borosilicate. (author) [Spanish] El principal factor que es preciso tener en cuenta al proceder a la eleccion de un vidrio adecuado para almacenar por largos periodos desechos de productos de fision es el metodo de almacenamiento que se va a aplicar; el segundo factor es el grado de seguridad que ofrece la elaboracion del vidrio en un establecimiento de alta actividad. A su vez, los factores que interesan para el almacenamiento son la resistencia a la lixiviacion, la estabilidad termica y a las radiaciones y la proporcion de desechos que se pueden incorporar a la masa vitrea, mientras que las propiedados fisicas y quimicas de los aditivos vitrificantes, asi como el punto de fusion y la viscosidad del vidrio mismo, son factores que intervienen mas bien en el proceso de elaboracion. Los autores examinan la importancia relativa de todos estos factores. Exponen luego los resultados del estudio experimental de los vidrios al borosilicato que se han elegido para, los ensayos en instalacion piloto, incluso el efecto de dosis de radiacion hasta 10{sup 12} rad sobre sus propiedades fisicas y quimicas. Tambien examinaron vidrios de otras composiciones y compararon su posible utilidad, como medio de almacenamiento, con la de los vidrios al borosilicato. (author) [Russian] Steklo dlja dlitel'nogo hranenija othoDov, soderzhashhih produkty delenija, dolzhno vybirat'sja, vo-pervyh s uchetom predpolagaemogo metoda hranenija i , vo-vtoryh, s uchetom vozmozhnosti ego poluchenija na vysokoradioaktivnyh ustanovkah. Vazhnymi faktorami s tochki zrenija hranenija javljajutsja: stojkost' protiv vyshhelachivanjja, teplostojkost' i radiacionnaja stojkost', a takzhe predel'naja dolja vvodimyh othodov; chto zhe kasaetsja fizicheskogo haraktera i himicheskih svojstv jelementov, dobavljaemyh dlja stekloobrajeovanija, a takzhe tochki plavlenija i vjazkosti stekla, to jeti faktory kasajutsja processa izgotovlenija. Obsuzhdaetsja otnositel'naja vazhnost' jetih faktorov. Privodjatsja dannye issledovanija borosilikatnyh stekol na jeksperimental'noj ustanovke; sjuda vhodjat takzhe issledovanija vlijanija dozy obluchenija (do 101grad) na ih fizicheskie i himicheskie svojstva. Byli issledovany takzhe i stekla drugih sortov. Potencial'nye vozmozhnosti ispol'zovanija jetih stekol v kachestve sredy dlja hranenija radioaktivnyh othodov sopostavljajutsja s vozmozhnostjami v otnoshenii borosilikatnyh stekol. (author)

  8. Use of ion exchange and early treatment of radioactive contamination in the digestive tract; Utilisation des echangeurs d'ions et traitement precoce de la contamination radioactive par voie digestive

    Energy Technology Data Exchange (ETDEWEB)

    Michon, G; Guilloux, M J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    The efficiency of cation exchange resins for the treatment of digestive contamination with strontium has been studied on rats. The results obtained show that the most efficient resins are those of sulfonic type when administered in the ammonium form. The treatment is still efficient when applied 45 minutes after the ingestion of strontium. In the most favourable cases, the radioactivity of the skeleton was lower by a factor 6 in the treated animals than in controls. This easily applicable, rather safe and non specific treatment deserves to be retained for use. (author) [French] Une etude de l'efficacite des resines echangeuses de cations dans le traitement d'une contamination digestive par le strontium a ete entreprise chez le rat. Les resultats montrent que parmi les resines, les plus efficaces sont celles de type sulfonique, administrees sous forme ammonium. Le traitement est encore efficace 45 minutes apres l'ingestion du strontium. Dans les meilleurs cas, le squelette des rats traites etait six fois moins radioactif que celui des temoins. Ce traitement d'emploi facile, peu dangereux, non specifique, merite d'etre retenu. (auteur)

  9. Control panel for radiation around reactors (1963); Tableaux de controle des radiations aupres des piles (1963)

    Energy Technology Data Exchange (ETDEWEB)

    Candes, P; Barthoux, A [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1964-07-01

    This report outlines the general philosophy of radiation control in French reactors and their annexes. The supervision is carried out continuously from a central control panel on which appear all the measurements made and the alarm signals. The equipment is described; one item makes it possible to measure simultaneously the radioactive dusts and gases. The specifications of the alarm system, which is considered to be the most important are given. Finally a new measuring technique is proposed which makes it possible to reduce considerably the cost of radiation control while at the same time providing the results in a form in which they can be easily treated, in particular in the case of the calculation of total doses. (authors) [French] Ce rapport definit la philosophie generale du controle des radiations dans les piles francaises et dans leurs annexes. La surveillance se fait d'une maniere continue a partir d'un tableau de controle centralise ou sont reportees toutes les mesures et les signalisations d'alarme. On decrit les appareils utilises, dont un permet la mesure simultanee des poussieres et gaz radioactifs, et on definit les specifications de la fonction alarme qui est consideree comme la plus importante. Enfin on propose une nouvelle technique de mesure qui permettrait de reduire considerablement le cout du controle des radiations tout en fournissant des resultats plus facilement exploitables, en particulier pour le calcul des doses integrees. (auteurs)

  10. Adsorption studies in a fluorinated atmosphere; Etude de l'adsorption en atmosphere fluorante

    Energy Technology Data Exchange (ETDEWEB)

    Abassin, J J; Barberi, P; Guillouet, Y; Hartmanshenn, O; Lambard, J; Machefer, J; Michel, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1966-03-01

    This CEA report deals with the adaptation of conventional or non-conventional apparatus to the measurement of the physical and chemical adsorption of corrosive fluorine-containing gases. Various techniques are reviewed, in particular: - thermogravimetry; - volumetry; - use of radio-active tracers; - calorimetry; - hertzian spectroscopy; - infrared spectroscopy. In each of these cases, problems of corrosion call for the use of special techniques which require the extensive use of pure nickel and aluminium or certain of their alloys. Diagrams of the apparatus and some examples of applications are given, together with some details of the performances obtained and of the main drawbacks. (authors) [French] Ce rapport CEA traite de l'adaptation d'appareillages classiques ou non a la mesure de l'adsorption physique et chimique de derives fluores gazeux corrosifs. Differentes techniques sont passees en revue, en particulier: - la thermogravimetrie; - la volumetrie; - l'utilisation de traceurs radioactifs; - la calorimetrie; - la spectroscopie hertzienne; - la spectroscopie infra-rouge. Dans chacun des cas, les problemes de corrosion conduisent a une technologie specialement adaptee et utilisant tres largement le nickel et l'aluminium purs ou certains de leurs alliages. Des schemas d'appareils et quelques exemples d'application sont proposes, ainsi que quelques precisions sur les performances obtenues et les principaux defauts. (auteurs)

  11. Experiments with SIRA - the radioactive ion separator

    International Nuclear Information System (INIS)

    Angelique, J.C.; Orr, N.A.

    1998-01-01

    There are two main techniques to obtain radioactive ion beams. One, consisting in the fragmentation of projectile in a thin target followed by a separation carried out with LISE or SISSI type spectrometers or by an alpha spectrometer is used currently at GANIL. The second one, the ISOL (Isotope Separator One-Line) is presently under study on the SIRa benchmark, as part of the SPIRaL (Source de Production d'Ions Radioactifs en Ligne). A high energy light ion beam is stopped by a thick target to produce radioactive nuclei by various reactions in the target. The target, usually of carbon, is heated at around 1800 deg. C in order to accelerate the migration of the atoms produced at the target surface. These atoms are then diffused by a transfer tube up to plasma region where they are ionized and then accelerated. As projectiles the GANIL project makes use of a large variety of heavy ions. A table containing the radioactive ion beam characteristics (charge state and lifetime), the primary beams, the yields and the expected intensities to be obtained with SPIRaL is presented. Also, data concerning the production rates of rare gases obtained during 1993 to 1994 are given

  12. The Effect of Fission Products on the Radioactivity of some Hydrobionts of the Pacific Ocean; Effet des Produits de Fission sur la Radioactivite de Certains Organismes Marins de l'Ocean Pacifique; 0412 041b 0418 0414 ; Influencia de los Productos de Fision en la Radiactividad de Algunos Organismos Marinos del Oceano Pacifico

    Energy Technology Data Exchange (ETDEWEB)

    Moiseev, P. A.; Kardashev, A. V. [All-Union Marine Fisheries and Oceanographical Scientific Research Institute, Moscow, USSR (Russian Federation)

    1960-07-01

    The paper emphasizes the fact that currents in the water masses disperse radioactive elements over large distances, with the result that many marine fauna and flora far removed from the centres of contamination may accumulate dangerous concentrations of such elements. (author) [French] Dans ce memoire, on souligne que les masses d'eau des courants marins transportent les elements