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Sample records for des dechets radioactifs

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

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    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)

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

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    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)

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

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    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)

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

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    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)

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

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    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

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

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    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)

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

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    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

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

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    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

  9. 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

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    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)

  10. 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

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    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

  11. 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)

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    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)

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

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    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

  13. 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

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    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)

  14. 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

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    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)

  15. 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

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    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

  16. 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

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    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

  17. 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

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    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

  18. 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

  19. 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

  20. 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)

  1. 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

  2. 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)

  3. 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

  4. 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

  5. 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

  6. 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

  7. 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

  8. 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

  9. 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

  10. 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

  11. 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

  12. 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

  13. 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

  14. 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

  15. 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

  16. 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

  17. 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

  18. 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

  19. 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

  20. 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

    Hanford consiste a intercaler le plus grand nombre possible de structures geologiques entre les lieux d'elimination et les points les plus proches d'irradiation eventuelle des populations. Selon la decontamination de Simpson, ce procede fait appel aux notions de temporisation et de desintegration. Les problemes qui se posent a Hanford pour l'elimination des dechets portent sur les points suivants : - 1. l'inexactitude des donnees geologiques quantitatives; 2. l'absence de terrains isotropes et homogenes; 3. la necessite de determiner l'importance quantitative de l'ecart des caracteristiques geologiques et hydrologiques, par rapport a la jnpyexmejj ,4. la necessite de determiner et de mesurer les parametres interessants. Le memoire donne des exemples, pris a Hanford, qui illustrent les points ci-dessus. On a fore 557 puits d'une profondeur totale de 33.000 metres, mais les indications obtenues doivent etre utilisees avec prudence. Les etudes courantes des proprietes aquiferes des sols n'ont qu'une valeur limitee, car les donnees relatives a la permeabilite des differentes structures dans toutes les directions sont presentees globalement sous forme de valeurs moyennes. Les etudes fondees sur les echangea d'ions fournissent des donnees quantitatives d'un interet immediat qui peuvent aider a interpreter les caracteristiques geologiques. Les etudes hydrologiques, associees aux recherches geochimiques et aux donnees geologiques, permettent d'expliquer logiquement l'influence des structures geologiques sur les mouvements des eaux souterraines. L'enfouissement des dechets radioactifs n'est ni une panacee ni une pratique a redouter. A Hanford, en combinant les donnees obtenues par les geologues, les-hydrologistes, les geochimistes et les mathematiciens, on a pu parvenir a de bons resultats en matiere d'enfouissement sans danger des dechets. Il reste neanmoins beaucoup a faire. (author) [Spanish] La evacuacion de desechos radiactivos en el subsuelo depende de la estructura

  1. 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

  2. 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

  3. 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.)

  4. 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.

  5. 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.

  6. 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.)

  7. 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

  8. 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)

  9. 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

  10. 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

  11. 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

  12. 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.

  13. 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

    '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

  14. 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.)

  15. 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.)

  16. 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

  17. Problematique de gestion des dechets de campagne electorale ...

    African Journals Online (AJOL)

    La méthode utilisée est basée sur les interviews et la caractérisation des déchets ... Les données collectées ont été traitées à l'aide de quelques outils de la ... la sensibilisation à la prévention et la promotion des instruments économiques, ...

  18. 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.)

  19. 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)

  20. 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.)

  1. 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.)

  2. 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.)

  3. 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.)

  4. 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).

  5. 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)

  6. 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.)

  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. 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

  10. 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)

  11. Disposal into the Sea and into Geological Structures of Wastes Resulting from the Peaceful Uses of Atomic Energy; Rejet en Mer et dans les Formations Geologiques de Dechets Provenant des Utilisations Pacifiques de l'Energie Atomique; 0423 0414 ; Eliminacion en el Mar y en Estructuras Geologicas de Desechos Procedentes del Uso Pacifico de la Energia Atomica

    Energy Technology Data Exchange (ETDEWEB)

    Carritt, Dayton E. [Department of Oceanography, Johns Hopkins University, Baltimore, MD (United States)

    1960-07-01

    Practices which lead to safe disposal of radioactive wastes permit the return of the wastes to man only at levels below maximum permissible concentrations, and do not prevent the development of resources which in the absence of disposal could make a significant contribution to man's well-being. The design of safe disposal procedures for any selected marine location is at present limited by our knowledge of several parts of the system which is involved in the return of radioactivity from the disposal site to man. Because of our present lack of knowledge, disposal procedures now being considered in the United States contain an unknown amount of ''over-design'' and, although they are believed to be conservative, are not unduly restrictive at present levels of waste generation. A better understanding of (a) turbulent mixing processes in the oceans, (b) the physical and chemical states of waste-product elements when in equilibrium with sea-water, and (c) the interaction of waste-product elements with the marine biota, their biological half-life, and the extent of their concentration or rejection by marine organisms in all trophic levels, will provide the basis for a more efficient and safer utilization of the marine environment for the disposal of radioactive wastes. (author) [French] Les pratiques qui assurent une elimination sans danger des dechets radioactifs ne permettent le retour de ces dechets a l'homme qu'a des activites d'un niveau inferieur aux concentrations maxima tolerees et n'empechent pas le developpement de ressources qui, en l'absence de toute elimination, pourraient constituer une contribution importante au bien-etre de l'homme. La mise au point de procedes d'evacuation pour tout endroit choisi de la mer est a present limitee par le niveau de nos connaissances en ce qui concerne plusieurs elements du processus par lequel la radioactivite des dechets retourne vers l'homme. Du fait qu'a l'heure actuelle ces connaissances sont insuffisantes, les

  12. 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.)

  13. 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

  14. 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)

  15. 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.)

  16. 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)

  17. 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)

  18. 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)

  19. 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)

  20. 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)

  1. 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.)

  2. 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)

  3. 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.)

  4. 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)

  5. 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.

  6. 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.)

  7. 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.)

  8. 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.)

  9. 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)

  10. 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-dechets

  11. Radioactive contamination of aquatic media and organisms; La contamination radioactive des milieux et des organismes aquatiques

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

    After a brief account of the radioactive wastes produced by peaceful or military uses of Atomic Industry, the author first describes a series of observations carried out 'in the field' on the extent of contamination in aquatic organisms with respect to that of the medium. The experimental studies are then analysed, with reference both to the radioisotope metabolism and to the factors and types of contamination of aquatic organisms by wastes from atomic industry. A precise experimental project is presented at the end of the paper, including almost 300 references. (author) [French] Apres une courte etude des dechets radioactifs produits par les utilisations pacifiques ou militaires de l'Industrie Atomique, l'auteur fait etat d'abord des observations effectuees 'sur le terrain' concernant l'extension de la contamination des organismes aquatiques en rapport avec celle du milieu. L'auteur analyse ensuite les etudes experimentales se rapportant aussi bien au metabolisme des radioisotopes qu'aux facteurs et aux modalites de la contamination des organismes aquatiques par les dechets de l'industrie atomique. Un projet de travail experimental precis est presente a la fin de cette revue qui comporte pres de 300 references bibliographiques. (auteur)

  12. Radioactive contamination of aquatic media and organisms; La contamination radioactive des milieux et des organismes aquatiques

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

    After a brief account of the radioactive wastes produced by peaceful or military uses of Atomic Industry, the author first describes a series of observations carried out 'in the field' on the extent of contamination in aquatic organisms with respect to that of the medium. The experimental studies are then analysed, with reference both to the radioisotope metabolism and to the factors and types of contamination of aquatic organisms by wastes from atomic industry. A precise experimental project is presented at the end of the paper, including almost 300 references. (author) [French] Apres une courte etude des dechets radioactifs produits par les utilisations pacifiques ou militaires de l'Industrie Atomique, l'auteur fait etat d'abord des observations effectuees 'sur le terrain' concernant l'extension de la contamination des organismes aquatiques en rapport avec celle du milieu. L'auteur analyse ensuite les etudes experimentales se rapportant aussi bien au metabolisme des radioisotopes qu'aux facteurs et aux modalites de la contamination des organismes aquatiques par les dechets de l'industrie atomique. Un projet de travail experimental precis est presente a la fin de cette revue qui comporte pres de 300 references bibliographiques. (auteur)

  13. 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

  14. 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)

  15. 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

  16. Problems Arising from Disposal of Low-Activity Radioactive Waste in the Coastal Waters of the Netherlands; Problemes Poses par l'Evacuation des dechets de Faible Radioactivite dans les Eaux Cotieres des Pays-Bas; 041f 0420 041e 0414 ; Problemas que Plantea la Evacuacion de Desechos Radiactivos de Baja Actividad en las Aguas Costeras de los Paises Bajos

    Energy Technology Data Exchange (ETDEWEB)

    Korringa, P. [Netherlands Institute for Fishery Investigations, Ijmuiden (Netherlands)

    1960-07-01

    Low-activity waste discharged in coastal waters will find its way into the marine food chain in two entirely different ways: 1. Adsorption to the surface of plankton organisms and adsorption to silt particles. In the latter case, fish and other creatures may ingest the loaded particles with their regular food. If the elements under consideration are not of primary biological importance to the organisms concerned, accumulation will not increase geometrically. Much of the radioactive material attached to ingested silt particles will leave the organisms later. 2. Accumulation through active uptake of elements collected in dissolved state by shell-bearing organisms. Copper, zinc, manganese, cobalt and the like are accumulated very strongly by shell-forming creatures like molluscs, and are stored in the connective tissues. If a part worth mentioning of these elements is of a radioactive nature, accumulation could attain alarming levels. Shrimps, Dover soles, plaice, and mussels being the main fishery products in the vicinity of the pipeline planned for the Netherlands centre for reactor research, noticeable accumulation of radioactive waste in these organisms should be prevented. The special international position of the Netherlands fish market requires extra care, and migration of fishes and shrimps makes it impossible to avoid a contaminated area. (author) [French] Les dechets de faible radioactivite evacues dans les eaux cotieres atteindront le milieu biologique marin par deux voies totalement distinctes: 1. Adsorption par le plancton et adsorption par les particules sedimentaires. Dans ce dernier cas, les poissons et autres animaux peuvent ingerer les particules chargees avec leur nourriture habituelle. Si les elements en question ne presentent pas pour ces organismes une grande importance biologique, la quantite accumulee ne croitra pas dans une proportion geometrique. Une grande partie des produits radioactifs fixes sur les particules sedimentaires ingerees sera

  17. 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.)

  18. 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.)

  19. 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.)

  20. 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.)

  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. 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.)

  3. 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)

  4. 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)

  5. 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)

  6. 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)

  7. 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)

  8. 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.)

  9. 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

  10. 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)

  11. 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)

  12. 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)

  13. 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)

  14. 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)

  15. 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)

  16. 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.)

  17. 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.)

  18. 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.)

  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. 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.

  1. 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)

  2. 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

  3. 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)

  4. 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

  5. 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)

  6. 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)

  7. Current Practice in the Management of High-Bevel Radioactive Wastes in the United States of America; La Pratique Courante de Gestion des Dechets de Haute Activite aux Etats-Unis d'Amerique; 0421 041e 0412 0420 0415 041c 0415 041d 041d 042b 0414 0 ; Metodos Corrientes de Tratamiento y Evacuacion de Desechos de Elevada Actividad Aplicados en los Estados Unidos de America

    Energy Technology Data Exchange (ETDEWEB)

    Campbell, Bruce F.; Doud, Edward; Tomlinson, R. E. [General Electric Company, Hanford Atomic Products Operation, Richland, WA (United States)

    1963-02-15

    steel tanks are constructed within concrete vaults. No operational problems or tank failures have been encountered. While the current practice of storing radioactive solutions has been completely successful in preventing significant amounts of radioactivity from escaping to the environment, the feeling persits that a better way at reasonable cost should be found to assure the long-term containment of radioactive materials. (author) [French] Il est necessaire d'enfermer les produits de fission radioactifs et les elements transuraniens dans des recipients donnant toutes les garanties voulues et les premieres solutions de ce probleme ont consiste a construire de grands reservoirs souterrains. Cette methode tres simple est encore appliquee de nos jours et plus de 70 millions de gallons de solution radioactive sont stockes dans pres de 200 citernes souterraines, pour l*ensemble des installations de la CEA-EU. On utilise une grande variete de reservoirs de conception differente suivant le volume et la composition des dechets a stocker, les conditions du milieu au site d'entreposage et les particularites techniques prises en consideration. Dans chaque cas, le choix du type de reservoir tient compte a la fois de sa securite d'utilisation, de sa duree probable et de son prix de revient. Les depenses d'investissement pour les installations de stockage utilisees varient de 0,47 a 2,66 dollars/ gallon. On doit tenir compte egalement des frais de surveillance, de traitement ou de tfansport des dechets et de l'amortissement du materiel pour calculer le cout a long terme. Les donnees dont on dispose sont encore insuffisantes pour permettre des-predictions precises. A Hanford, les solutions radioactives sont stockees dans des reservoirs en beton arme, revetu d'aciei ordinaire. Sur 145 de ces reservoirs mis en service a divers moments depuis 1945, quatre ont presente des fuites apres stockage, pendant 8 a 12 ans,, de dechets ne degageant pas de chaleur. A chaque fois, on a pompe le

  8. 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)

  9. 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

  10. 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)

  11. 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.)

  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. 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.

  14. 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)

  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. 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.

  19. Facilities for Waste Management at Chalk River, Canada; Les Installations d'Elimination et d'Utilisation des Dechets a Chalk River, Canada; 041e 0411 041e 0420 0423 0414 041e 0412 ; Instalaciones Utilizadas para el Provechamiento y Evacuacion de Desechos Radiactivos en Chalk River, Canada

    Energy Technology Data Exchange (ETDEWEB)

    Mawson, C. A.; Russell, A. E. [Environmental Research Branch, Atomic Energy of Canada Ltd. (Canada)

    1960-07-01

    The waste disposal areas used by the Atomic Energy of Canada Limited are situated in a rock basin filled with glacial till and sand, draining into the Ottawa River. Low-activity liquid effluent is run into pits in the sand, which are filled with small rocks to prevent contact of liquid with the air. Medium- level liquid is mixed with cement in drums which are stacked and totally enclosed in concrete trenches; medium-level solids are buried in concrete-lined trenches; high-level solids are placed in holes lined with steel or concrete piping. Special facilities are provided for organic liquids and bottled wastes. Details will be given of the structural work and procedures, with an outline of the results of environmental monitoring. (author) [French] Les zones d'elimination utilisees par l'Atomic Energy of Canada Limited sont situees dans un bassin rocheux, rempli de blocs erratiques et'de sable, dont les eaux s'ecoulent dans la riviere Ottawa. Les effluents liquides de faible activite sont verses dans des puits creuses dans le sable, qui sont ensuite remplis de petites pierres pour prevenir le contact du liquide avec l'air. Les dechets liquides d'activite moyenne sont melanges a du ciment dans des barils qui sont entasses et completement enfermes dans des tranchees betonnees; les dechets solides d'activite moyenne sont enfouis dans des tranchees bordees de beton; les dechets solides de haute activite sont places dans des trous bordes de conduites d'acier ou de ciment. Des installations speciales sont prevues pour les liquides organiques et les dechets enfermes dans des recipients en forme de bouteilles. Le memoire expose en detail les travaux d'amenagement et les methodes suivies; il donne un apercu des resultats du controle du milieu ambiant. (author) [Spanish] Las zonas utilizadas por la Atomic Energy of Canada Limited para la evacuacion de desechos radiactivos estan situadas en una cuenca rocosa recubierta de limo y arena del periodo glacial, que desemboca en el

  20. Caracterisation des dechets solides des grandes manifestations ...

    African Journals Online (AJOL)

    This situation aggravates the structural inadequacy of the city managers and leads to unsanitary. The content of a pilgrim's trash behaves like a mirror reflecting his consumption habits, his attitude towards a manifestation of piety in the public space considered as private area as well as a no man's land. Keywords: Dassa ...

  1. Legal and Administrative Problems of Controlling the Disposal of Nuclear Wastes in the Sea; Problemes Juridiques et Administratifs Poses par le Controle de l'Elimination des Dechets Nucleaires dans la Mer; 041f 0420 041e 0414 ; Problemas Juridicos y Administrativos que Plantea el Control de la Evacuacion de Desechos Nucleares En El Mar

    Energy Technology Data Exchange (ETDEWEB)

    Hydeman, Lee M.; Berman, William H. [Atomic Energy Research Project, University of Michigan Law School (United States)

    1960-07-01

    The basic purpose of the paper is to present some approaches to multinational control of the sea disposal of nuclear wastes, considering both the type of international .control which may be appropriate and the means for accomplishing such control. First, the authors give a brief description of the kind of control which appears to be necessary in protecting public health against the hazards of the disposal of wastes in the sea. The second part consists of a general analysis of the legal problems posed by nuclear wastes. Emphasis is placed on the authority of coastal states to impose unilateral control on the disposal of wastes by other nations if such disposal might adversely affect their interests. The authors inquire into the adequacy of legal remedies as well as the possible rule of law regarding the prevention of damage from waste disposal and the apportionment of liability in the event that such damage does occur. The third part is an analysis of how other problems of control have been handled, both unilaterally and multilaterally. The final part consists of an inquiry into various means of internationally controlling the sea disposal of nuclear wastes. The role of existing international bodies in the maintenance of continuing administrative control at the international level is mentioned. (author) [French] Le but essentiel du memoire est d'exposer diverses facons d'envisager le probleme du controle multinational de l'evacuation des dechets nucleaires dans l'eau de mer, en examinant a la fois le type de controle international approprie et les moyens de le mettre en oeuvre. La premiere partie contiendra une description succincte du genre de controle qui semble necessaire pour la protection de la sante publique contre les effets de l'evacuation des dechets dans la mer. La deuxieme partie consistera en une analyse generale des problemes juridiques poses par. l'elimination des dechets nucleaires. Les auteurs traiteront particulierement du droit des Etats riverains

  2. 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)

  3. 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)

  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. 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

  6. Fixation of Simulated Highly Radioactive Wastes in Glassy Solids; Fixation de Dechets Simules de Haute Activite dans des Soudes Vitreux; 0424 0418 041a 0421 0410 0426 0418 042f 0418 041c 0418 0422 0418 0420 041e 0412 0410 041d 041d 042b 0425 0420 0410 0414 0418 041e 0410 041a 0422 0418 0412 041d 042b 0425 041e 0422 0425 041e 0414 041e 0412 0412 042b 0421 041e 041a 041e 0419 0410 041a 0422 0418 0412 041d 041e 0421 0422 0418 0421 0422 0415 041a 041b 041e 041e 0411 0420 0410 0417 041d 042b 041c 0418 0422 0412 0415 0420 0414 042b 041c 0418 0412 0415 0429 0415 0421 0422 0412 0410 041c 0418 ; Fijacion de Desechos Simulados de Elevada Radiactividad en Solidos Vitreos

    Energy Technology Data Exchange (ETDEWEB)

    Clark, W. E.; Godbee, H. W. [Oak Ridge National Laboratory, Oak Ridge, TN (United States)

    1963-02-15

    on TBP-25 waste and from 8 to 140 mil/ month on Purex waste. Operation above 900 Degree-Sign C with Purex waste plus fluxing agents may result in catastrophic local corrosion. (author) [French] Le Laboratoire national d'Oak Ridge s'efforce actuellement de mettre au point un methode d'incorporation des dechets de haute activite dans des verres insolubles de densite elevee, tous les elements radioactifs se trouvant contenus dans la partie solide. Des experiences avec des dechets simules resultant des procedes TBP-25 (aluminium, HNO{sub 3}), Purex et Darex (acier inoxydable, HNO{sub 3}) montrent qu'une telle methode est techniquement realisable. Des solides denses, de structure microcristalline, peuvent convenir aussi bien que de veritables, verres; leur meilleure conductibilite thermique compense dans une certaine mesure le fait que la surface doit etre plus grande que dans le cas des verres. Avec les types de dechets susmentionnes, on a prepare des verres au phosphate et au borophosphate. La volatilite du cesium etait limitee a 0,1% environ du fait de l'entrainement mecanique et la volatilite du ruthenium a ete abaissee a moins de 0,5% par addition de phosphite ou d'hypophosphite. Parmi les autres additifs figuraient PbO, Ca(OH){sub 2}, NaOH et MgO. Les densites brutes variaient entre 2,36 et 2,90 g/cm{sup 3} pour les dechets du procede TBP-25 et entre 2,63 et 2,80 g/cms pour les dechets du procede Purex. Les reductions de volume correspondantes, a partir des solutions concentrees de dechets, etaient comprises entre 7,2 et 9,3 et entre 5,7 et 8,3; le passage initial a l'etat pateux se produisait entre 875 et 1000 Degree-Sign C et entre 830 et 975 Degree-Sign C respectivement. Les essais avec les dechets Darex en sont encore au stade preliminaire. En operant de maniere semi-continue a l'echelle semi-industrielle' on a obtenu un verre veritable a partir de dechets TBP-25 et un solide microcristallin a partir de dechets Purex. La conductibilite thermique du verre variait

  7. 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)

  8. 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

  9. 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.

  10. 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.)

  11. 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.)

  12. 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.)

  13. 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.)

  14. 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.)

  15. 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.

  16. 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)

  17. 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

  18. 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)

  19. 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.

  20. From the coupling between ion beam analysis techniques and physico-chemical characterization methods to the study of irradiation effects on materials behaviour; Du couplage des techniques d'analyse par faisceaux d'ions et des methodes de caracterisation physico-chimique a l'etude des effets d'irradiation sur le comportement des materiaux

    Energy Technology Data Exchange (ETDEWEB)

    Millard-Pinard, N

    2003-07-01

    The general purpose of my research work is to follow and to interpret the surface evolution of materials, which have received several treatments. During my PhD and my post-doc work, my field of research was tribology. Since I arrived in the 'Aval du Cycle Electronucleaire' group of the Institut de Physique Nucleaire de Lyon, my research activities are in line with the CNRS program 'PACE ' (Programme sur l'Aval du Cycle Electronucleaire) within the ACTINET network. They are coordinated by the PARIS (Physico-chimie des actinides et autres radioelements en solution et aux interfaces) and NOMADE (NOuveaux MAteriaux pour les DEchets) GDR with ANDRA (Agence Nationale pour la gestion des Dechets RAdioactifs), EDF and IRSN (Institut de Radioprotection et de Surete Nucleaire) as partner organisations. My work focused on the study of fission products and actinides migration in barrier materials, which may be capable of assuring the long term safety of deep geological repositories. Until now, it was necessary to use the coupling of ion beam analysis techniques and physico-chemical characterization techniques. During the last few months, I have became interested in understanding radiolytic effects. This new orientation has led us to use ion beams as an irradiating tool. These irradiation experiments are pursued in three major projects. The study of cobalt sulfide inhibition effects of radiolysis gas production during the irradiation of model organic molecules. This is a collaboration with the IRSN, the Institut de Recherche sur la Catalyse and the Ecole Nationale Superieure des Mines de Saint-Etienne. A PhD, co-directed by M. Pijolat from ENSMSE and myself, concerning this study will start in October 2003. Water radiolysis effects on iron corrosion are also studied in the particular case of vitrified nuclear waste containers, which will be stored in deep geological repositories. One ANDRA financed PhD, co-directed by Nathalie Moncoffre and myself, is dedicated to this study

  1. From the coupling between ion beam analysis techniques and physico-chemical characterization methods to the study of irradiation effects on materials behaviour; Du couplage des techniques d'analyse par faisceaux d'ions et des methodes de caracterisation physico-chimique a l'etude des effets d'irradiation sur le comportement des materiaux

    Energy Technology Data Exchange (ETDEWEB)

    Millard-Pinard, N

    2003-07-01

    The general purpose of my research work is to follow and to interpret the surface evolution of materials, which have received several treatments. During my PhD and my post-doc work, my field of research was tribology. Since I arrived in the 'Aval du Cycle Electronucleaire' group of the Institut de Physique Nucleaire de Lyon, my research activities are in line with the CNRS program 'PACE ' (Programme sur l'Aval du Cycle Electronucleaire) within the ACTINET network. They are coordinated by the PARIS (Physico-chimie des actinides et autres radioelements en solution et aux interfaces) and NOMADE (NOuveaux MAteriaux pour les DEchets) GDR with ANDRA (Agence Nationale pour la gestion des Dechets RAdioactifs), EDF and IRSN (Institut de Radioprotection et de Surete Nucleaire) as partner organisations. My work focused on the study of fission products and actinides migration in barrier materials, which may be capable of assuring the long term safety of deep geological repositories. Until now, it was necessary to use the coupling of ion beam analysis techniques and physico-chemical characterization techniques. During the last few months, I have became interested in understanding radiolytic effects. This new orientation has led us to use ion beams as an irradiating tool. These irradiation experiments are pursued in three major projects. The study of cobalt sulfide inhibition effects of radiolysis gas production during the irradiation of model organic molecules. This is a collaboration with the IRSN, the Institut de Recherche sur la Catalyse and the Ecole Nationale Superieure des Mines de Saint-Etienne. A PhD, co-directed by M. Pijolat from ENSMSE and myself, concerning this study will start in October 2003. Water radiolysis effects on iron corrosion are also studied in the particular case of vitrified nuclear waste containers, which will be stored in deep geological repositories. One ANDRA financed PhD, co-directed by Nathalie Moncoffre and myself, is

  2. 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

  3. 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)

  4. 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

    ) [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

  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. 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)

  7. Nuclear wastes management; Gestion des dechets nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    This document is the proceedings of the debate that took place at the French Senate on April 13, 2005 about the long-term French policy of radioactive wastes management. The different points tackled during the debate concern: the 3 axes of research of the 1991 law, the public acceptance about the implementation of repositories, the regional economic impact, the cost and financing, the lack of experience feedback, the reversibility or irreversibility of the storage, the share of nuclear energy in the sustainable development policy, the European Pressurized Reactor (EPR) project, the privatization of Electricite de France (EdF) etc. (J.S.)

  8. 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)

  9. 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)

  10. 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.)

  11. 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.)

  12. 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)

  13. 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

  14. 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

  15. 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)

  16. 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)

  17. 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.)

  18. 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.)

  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. 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)

  2. 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)

  3. The reprocessing of irradiated fuels improvement and extension of the solvent extraction process; Le traitement des combustibles irradies amelioration et extension du procede utilisant les solvants

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

    . Le traitement au solvant est egalement utilise pour les combustibles de la pile convertisseuse du plutonium (Rapsodie). On expose et commente le schema du traitement, les premiers resultats experimentaux et le projet d'une installation pilote de 1 kg/jour. L'utilisation de la tn-laurylamine dans le cycle de purification du plutonium est envisagee dans l'usine de traitement de La Hague. On presente le schema adopte et les performances du procede. On envisage la vitrification comme traitement definitif des dechets radioactifs concentres des Centres de Marcoule (uranium-irradie) et La Hague (uranium-molybdene irradie). Trois procedes possibles sont decrits et commentes, ainsi que les resultats d'exploitation des installations correspondantes sur elements traceurs. (auteurs)

  4. 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)

  5. 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)

  6. Hanford High-Level Waste Management; Gestion des Dechets de Haute Activite a Hanford; 041e 0411 0420 0410 0411 041e 0422 041a 0410 0412 042b 0421 041e 041a 041e 0420 0410 0414 0418 041e 0410 041a 0422 0418 0412 041d 042b 0425 041e 0422 0425 041e 0414 041e 0412 0412 0425 042d 041d 0424 041e 0420 0414 0415 ; Tratamiento y Evacuacion de Desechos de Elevada Radiactividad en Hanford

    Energy Technology Data Exchange (ETDEWEB)

    Tomlinson, R. E. [Hanford Laboratories, General Electric Co., Richland, WA (United States)

    1963-02-15

    During the 17-year history of Hanford operations, a high degree of safety has been provided at reasonable cost by storing high-level radiochemical wastes as alkaline slurries in underground tanks. Since this operation has been regarded as an interim measure only, a programme is being developed to decrease the mobility of the stored materials in order to achieve an increased assurance of continued containment of the stored materials. As currently visualized the large volumes of essentially non-heating dejacketing wastes will be evaporated to salt cakes in existing underground tanks. Laboratory studies and prototype operation in a 5000-gal tank indicate that the passage of heated air through the solution can remove enough water that, with controlled carbonation to convert free caustic to sodium carbonate, a non-hydroscopic salt cake can be formed. The self-heating wastes will be fractionized to permit the separate storage of the long-lived heat emitters in small volume, high-integrity containers. These materials could be made available for beneficial use on request. After 5 to 10 years decay of the short-lived heat emitters, the residual salt wastes will be combined with current dejacketing wastes and evaporated to salt cakes. Assuming the concurrence of the United States Atomic Energy Commission an obsolete canyon-type building will be reactivated and revised to conduct the chemical processing operations required. Solvent extraction (D2EHPA) will probably be used to isolate strontium and cerium from acid waste. A choice has not yet been made between solvent extraction, ion exchange and precipitation for caesium isolation. The integrated operation is anticipated to be in operation about 1966. (author) [French] Pedant les dix-sept annees de fonctionnement des installations de Hanford, on a obtenu un degre de securite eleve a un cout raisonnable en stockant les dechets radiochimiques de haute activite, sous forme de boues alcalines, dans des reservoirs souterrains

  7. 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.)

  8. 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)

  9. 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.)

  10. 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)

  11. 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.)

  12. 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.)

  13. 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.)

  14. 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.)

  15. 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.)

  16. 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?.

  17. 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)

  18. 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.)

  19. 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.)

  20. 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.)

  1. 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

  2. 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.)

  3. 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)

  4. 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.)

  5. 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

  6. 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.

  7. 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.)

  8. 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

  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. 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)

  11. Nuclear waste management; La gestion des dechets nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Nifenecker, H.

    2008-07-01

    The author gives an overview of the main issues related to the use of nuclear energy: the management and the environmental impact of wastes. After having outlined the different radiological consequences of different radionuclides, he proposes an approximate assessment of waste production which may depend on reactor technology, and which needs a distinction between low level, intermediate level, and high level wastes. He discusses the differences between primary energies and final energies, and how to consider nuclear energy and its wastes within this classification. Then, considering the deep geological storage, he describes how contamination may occur and the risks for the population as well as for the environment. After having evoked the use of breeder reactors and its separation-transmutation issues, the author briefly comments the nuclear waste financing issue

  12. 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)

  13. 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)

  14. 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.)

  15. 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)

  16. 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.)

  17. 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.)

  18. 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.)

  19. 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.)

  20. 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.)

  1. 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.)

  2. 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.)

  3. Concentration and Storage of Highly-Active Wastes from the First Stages of the United Kingdom Civil Nuclear Power Programme; Concentration et Stockage des Dechets de Haute Activite au Cours des Premiers Stades du Programme Civil de Production d'Energie d'Origine Nucleaire au Royaume-UNL; КОНЦЕНТРИРОВАНИЕ И ХРАНЕНИЕ ВЫСОКОАКТИВНЫХ ОТХОДОВ НА ПЕРВЫХ СТАДИЯХ ОСУЩЕСТВЛЕНИЯ ПРОГРАММЫ СОЕДИНЕННОГО КОРОЛЕВСТВА ПО ПРОИЗВОДСТВУ ЯДЕPHОЙ ЭЛЕКТРОЭНЕРГИИ ДЛЯ ГРАЖДАНСКИХ ЦЕЛЕЙ; Concentracion y Almacenamiento de Desechos de Elevada Radiactividad en las Primeras Etapas del Programa Civil de Energia Nucleoelectrica del Reino Unido

    Energy Technology Data Exchange (ETDEWEB)

    Clelland, D. W. [United Kingdom Atomic Energy Authority, Production Group, Risley, Warrington (United Kingdom)

    1963-02-15

    The general problems of highly-active waste disposal are discussed and in particular the United Kingdom system of concentrating and storing highly-active waste as an acidic liquid concentrate is described. A speculative estimate is made of the amount of highly- active waste which will arise from reprocessing during the first two decades of the United Kingdom Civil Nuclear Power Programme and engineering design and technical problems associated with the safe and economic confinement of this material are examined. (author) [French] L'auteur analyse les problemes generaux que pose l'elimination des dechets de- haute activite; il decrit plus particulierement la methode appliquee au Royaume-Uni pour concentrer et stocker des dechets de haute activite sous forme d'un liquide concentre acide. U evalue la quantite des dechets de haute activite qui seront produits au cours du traitement de combustibles irradies pendant les deux premieres deconnies du programme civil de production d'energie d'orgine nucleaire et il examine les problemes techniques que pose l'isolement economique et sur de ces substances. (author) [Spanish] El autor examina los problemas generales de la evacuacion de desechos de elevada radiactividad y, en particular, el procedimiento que se aplica en el Reino Unido para concentrar y almacenar desechos muy radiactivos en forma de concentrados liquidos de reaccion acida. Efectua un calculo aproximado de la cantidad de desechos de elevada radiactividad que se orginaran en las operaciones de regeneracion de combustibles durante las dos primeras decadas de ejecucion del programa civil de energia nucleoelectrica en el Reino Unido y analiza los problemas tecnicos y constructivos relacionados con el confinamiento seguro y economico de estas sustancias. (author) [Russian] Obsuzhdajutsja obshhie problemy udalenija radioaktivnyh othodov vysokoj aktivnosti i, v chastnosti, prinjatyj v Soedinennom Korolevstve metod koncentrirovanija i hranenija takih othodov v vide

  4. 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)

  5. 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)

  6. 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)

  7. 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

  8. 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)

  9. 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.)

  10. 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.)

  11. 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.)

  12. 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.)

  13. Ultimate Storage of High-Level Waste Solids and Liquids in Salt Formations; Stockage Definitif de Dechets Solides et Liquides de Haute Activite dans des Formations Salines; 041e 041a 041e 041d 0427 0410 0422 0415 041b 042c 041d 041e 0415 0425 0420 0410 041d 0415 041d 0418 0415 0422 0412 0415 0420 0414 042b 0425 0418 0416 0418 0414 041a 0418 0425 0412 042b 0421 041e 041a 041e 0410 041a 0422 0418 0412 041d 042b 0425 041e 0422 0425 041e 0414 041e 0412 0412 0421 041e 041b 042f 041d 042b 0425 041e 0411 0420 0410 0417 041e 0412 0410 041d 0418 042f 0425 ; Almacenamiento Definitivo de Desechos Solidos y Liquidos de Elevada Radiactividad En Formaciones de Rocas Salinas

    Energy Technology Data Exchange (ETDEWEB)

    Bradshaw, R. L.; Boegly, Jr., W. J.; Empson, F. M.; Kubota, H.; Parker, F. L.; Perona, J. J.; Struxness, E. G. [Oak Ridge National Laboratory, TN (United States)

    1963-02-15

    , calculations, based on an infinite array of line sources, showed that, in general, for wastes cooled longer than three years the space requirements are the same as for solids above the floor. Current studies are primarily concerned with the disposal of packaged solids and will culminate with a demonstration in a salt mine, probably during 1965. (author) [French] Les formations salines presentent beaucoup d'interet pour le stockage definitif de dechets liquides et solides de haute activite. Elles sont impermeables, elles sont resistantes et elles offrent une bonne conductibilite thermique. Des experiences en laboratoire et des essais dans une mine du Kansas ont montre que: a) les valeurs de la conductibilite thermique et du coefficient de diffusion de la roche saline impure in situ (0.011 cal/cm. s. Degree-Sign C et 0,026 cm{sup 2}/s pour une temperature de pointe du sel de 60 Degree-Sign C) ne representent que de 10 a 20% des valeurs mesurees en laboratoire pour des monocristaux; b) le fait de porter a 65 Degree-Sign C la temperature d'un volume d'enviroo 12 000 l de dechets places dans une cavite carree de 2,25 m de cote n'a pas compromis la stabilite de la chambre de mine, bien que la distance entre le sol et le plafond ait diminue de 1,25 cm a 1,50 m de la cavite; c) l'evaporation de la solution suivie d'une condensation sur les parois provoque certaines alterations de la cavite; d) l'adsorption d'une solution de dechets par du sel ecrase retarde a la fois l'alteration de la cavite et la production de gaz provenant de la decomposition radiolytique; e) les doses de rayonnement auxquelles ilfaut s'attendre dans une operation reelle d'elimination de dechets ne sera pas suffisamment grande pour affecter sensiblement la stabilite des chambres de mine. Le point principal sur lequel il subsiste encore des doutes est l'influence sur la stabilite de la mine d'une elevation de la temperature de grandes surfaces. Des recherches.theoriques et experimentales sur ce point sont en cours

  14. 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 ...

  15. 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)

  16. 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)

  17. 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.

  18. 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)

  19. Continuous Calcination of High-Level Radioactive Wastes by Means of a Rotary-Ball Kiln; Calcination Continue de Dechets de Haute Activite dans un Four Rotatif a Billes; 041d 0415 041f 0420 0415 0420 042b 0412 041d 041e 0415 041a 0410 041b 042c 0426 0418 041d 0418 0420 041e 0412 0410 041d 0418 0415 0412 042b 0421 041e 041a 041e 0410 041a 0422 0418 0412 041d 042b 0425 041e 0422 0425 041e 0414 041e 0412 0412 041e 0412 0420 0410 0429 0410 042e 0429 0415 0419 0421 042f 0428 0410 0420 041e 0412 041e 0419 041f 0415 0427 0418 ; Calcinacion Continua de Desechos de Elevada Radiactividad en un Horno de Bolas Rotatorio

    Energy Technology Data Exchange (ETDEWEB)

    Regan, W. H.; Hatch, L. P.; Domish, R. F. [Brookhaven National Laboratory, Upton, Long Island, NY (United States)

    1963-02-15

    in in diam., has a heated length of 7 ft and is designed to calcine approximately 6 gal/hr of waste. The paper presents an outline of the essential features of the Brookhaven calciner, with particular emphasis on the development of a rotary gas seal, together with a discussion of the results of operation of the pilot plant with simulated non-radioactive aluminium nitrate waste feed. (author) [French] calcination de dechets liquides de haute activite et a forte teneur en sels, qui permet de convertir des melanges de sels en des solides compacts presente d'importants avantages pour l'elimination definitive des dechets,savoir une reduction considerable du volume et une simplification generale des problemes que pose l'emmagasinage a long term Parmi les types de dechets que l'on soumet habituellement a la calcination, on peut citer ceux qui resultent du traitement aqueux des combustibles comportant des alliages d'aluminium ou des alliages de zirconium, ou du traitement de combustibles gaines d'acier inoxydable ou munis de matrices en acier inoxydable. La decomposition en leurs oxydes respectifs des melanges de sels ainsi formes (nitrate d'aluminium, fluorure de zirconium et nitrate ferrique,) pose un certain nombre de problemes delicats, dont plusieurs ont pour origine la formation de solides fortement radioactifs contenant, en proportions considerables,des particules de Tordre de quelques microns. Un dispositif de calcination interessant, actuellement a l'etude au Laboratoire national de Brookhaven, est fonde sur le principe du four rotatif a billes. Il consiste essentiellement en un four en forme de tube horizontal, tournant lentement et chauffe exterieurement par des resistances electriques. Les matieres a calciner, introduites dans le four par une tuyere de distribution, tombent sur un lit chaud de billes metalliques qui facilitent la transmission de la chaleur et empechent la formation d'agglomeres volumineux lors de la calcination. Les solides calcines debordent par

  20. Some Hydrographic Studies Required for Assessing the Effects of Atomic Waste Disposal; Quelques Etudes Hydrographiques Necessaires pour Evaluer les Effets de l'Evacuation des Dechets Atomiques; 0413 0418 0414 ; Algunos Estudios Hidrograficos que se Precisan para Determinar los Efectos de la Evacuacion de Desechos Atomicos

    Energy Technology Data Exchange (ETDEWEB)

    Gordon, D. L. [F.R.I.C.S., R.N. (United Kingdom)

    1960-07-01

    In order to be ab]e to assess the probable movement of effluent discharged into the sea, a sound knowledge of the cause of water movements and a practical knowledge of their measurements are essential. This paper emphasizes the considerations which should be borne in mind when those measurements and studies are carried out. Tidal streams, residual current, oceanic currents and eddies are discussed, as well as the scope of the observations which are considered necessary. (author) [French] Pour pouvoir determiner les mouvements probables des effluents evacues dans la mer, il est essentiel de bien connaitre les causes des mouvements des eaux et de savoir comment mesurer ces mouvements dans la pratique. L'auteur souligne les considerations dont il faut tenir compte en procedant a ces etudes et mesures. Il traite des marees, des courants residuels, des courants oceaniques et des remous, ainsi que de la nature des observations qui sont jugees necessaires. (author) [Spanish] Para poder determinar el movimiento probable de los efluentes que se vierten en el mar es imprescindible conocer a fondo las causas de los movimientos del agua y poseer nociones practicas de su medicion. El autor destaca la importancia de las consideraciones que han de tenerse en cuenta al efectuar estas mediciones y estudios. Se discuten las corrientes de las mareas, las corrientes residuales, las corrientes y los torbellinos oceanicos, asi como la finalidad de las observaciones que se consideran necesarias. (author) [Russian] Dlja togo, chtoby poluchit' vozmozhnost ocennt' verojatnoe dvizhenie jefljuenta, spushhennogo v more, neobhodimo imet' tverdye znanija prichin, vyzyvajushhih dvizhenie vody, a takzhe ochen' vazhno imet' prakticheskie znanija v otnoshenii metodov ih izmerenija. V jetom dokumente udeljaetsja vnimanie soobrazhenijam, kotorye neobhodimo imet' v vidu pri provedenii takogo roda izuchenij i izmerenij. V dokumente obsuzhdajutsja takie voprosy, kak prilivy i otlivy, techenija

  1. 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)

  2. 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)

  3. 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)

  4. 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)

  5. 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.)

  6. 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

  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. 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

  11. 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

    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

  12. 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)

  13. 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)

  14. Investigations in French battery and recycling plants; Traitement des dechets des piles et accumulateurs usages. Enquete dans des entreprises specialisees

    Energy Technology Data Exchange (ETDEWEB)

    Peltier, A.; Elcabache, J.M. [Institut National de Recherche et de Securite -INRS, Lab. de Chimie Analytique Minerale, Dept. Metrologie des Polluants, Centre de Lorraine, 54 - Vandoeuvre (France)

    2003-07-01

    The Analytical Chemistry laboratory of INRS assessed the occupational exposure of 380 employees in 15 enterprises specialized in the reprocessing of electrochemical generators accepting to take part in this study (2 firms sorting and preparing batteries for shipment to reprocessing centres, 7 recycling plants for alkaline, nickel-cadmium and zinc-carbon batteries, 5 spent lead accumulator processing plants). Assessments were also carried out in an enterprise with a workforce of 180 producing 'mercury free' zinc-carbon batteries. These assessments highlighted: - a high potential risk of lead impregnation in the milling and fusion phases of spent lead accumulator processing; - a potential risk of mercury intoxication during the use of pyrometallurgical processes allowing other mercury waste products to be processed simultaneously to spent batteries; - that during the processing of nickel-cadmium batteries the air cleaning systems of the workshops are largely inefficient and must be improved. The constant wearing of filtering respirators is a solution that must remain temporary, the prevention measure to be applied as early as possible being the capture of the cadmium dust fume emissions at source. (authors)

  15. 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)

  16. 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

  17. 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.)

  18. 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.)

  19. 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)

  20. 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

  1. Nuclear wastes: status and perspectives; Les Dechets nucleaires: etat des lieux et perspectives

    Energy Technology Data Exchange (ETDEWEB)

    Barre, B.; Bazile, F.; Bonin, B.; Marvy, A.; Ouzounian, G.; Wizsenfeld, B.

    2011-07-01

    Radioactive wastes are considered by the large public as a problem which mortgages the future of nuclear industry. Today, the main principles of radioactive wastes management are defined: separation, conditioning, storage and disposal are the main elements of a strategy allowing to protect the man and the environment from the impacts of the inevitable ultimate wastes. In a period of debate concerning the future of these wastes, this book aims at supplying to the public the elements which will allow him to build his own opinion about this hot topic. (J.S.)

  2. Industrial wastes guide for Alsace; Guide des dechets de l`entreprise Alsace

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-01-01

    This guide is aimed for industrial plant managers and gives comprehensive information on industrial waste management: effects of wastes on the environment (water, air, soil), waste processing limitations in Alsace, new regulations, taxes and incentives concerning waste processing in France, and references of national and regional (Alsace) administration and industrial agencies that are related with pollution abatement and control and waste management. The different types of wastes are reviewed, from papers to toxic solvents, with information given on volumes, processes, operators, processing equipment and equipment distributors

  3. Simulation applied to innovative waste management options; Simulation appliquee aux options innovantes de gestion des dechets

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-10-01

    The aim of this workshop is to share experience and methods in the domains of neutronics, spallation, thermo-hydraulics, corrosion, materials, mechanics; to define the needs for the other domains in order to improve the evaluation of concepts: ADS, MSR, Gas cooled reactors; and to determine the necessity or not to couple codes and tools for the concepts studied in the frame of GEDEON activities. This document groups together the transparencies of 6 presentations given at this workshop: design and performances of CEA spallation targets; simulation of spallation; the neutronic benchmark on the Megapie spallation target; the core physics of fast spectrum gas cooled reactors; the study and modeling of the thermal-mechanical behaviour of composite fuel in reactor. (J.S.)

  4. The management of industrial wastes in hydrology; La gestion des dechets industriels en hydrologie

    Energy Technology Data Exchange (ETDEWEB)

    Elbaz-Seboun, V.

    1998-07-08

    The industrial wastes are made of different kind of wastes: the inert wastes, the banal wastes (municipal wastes), the special wastes containing noxious elements with respect to human health and environment, and the radioactive wastes. Each industry generates its own effluents (sludges from water treatment plants and leachates from rubbish dumps). The main water pollutions are due to the fermentescible organic matters, nitrates and heavy metals from the industrial waste waters. The aim of the public water agencies is to better protect the environment and to give help to the industrialists in the management of their wastes: reduction at the source, selective collection, valorization, transportation and processing. Non-valorizable wastes must be processed: physico-chemical and biological processing (bio-filtering, coagulation-flocculation, membranes and industrial gases), incineration (organic wastes), disposal in class 1 technical burial centres after stabilization (ultimate wastes). Since July 2002, only the ultimate wastes will be disposed off and all class 2 and 3 dumps must have been rehabilitated. This work is divided into 2 parts: part 1 gives a presentation of the different types of industrial wastes and of their management (origin of wastes, effluents, heavy metals, environmental impact, legal aspects, wastes management, valorization). The second part describes the different processes for the treatment of industrial wastes (conventional processes, physico-chemical and biological processes, incineration, tipping, processing of radioactive wastes). (J.S.)

  5. The CEA's waste management strategy; La strategie de gestion des dechets du CEA

    Energy Technology Data Exchange (ETDEWEB)

    Behar, Ch. [CEA Saclay, Dir. de l' Energie Nucleaire, 91 - Gif-sur-Yvette (France); Dall' ava, D. [CEA Saclay, Dir. de l' assainissement et du demantelement nucleaire, 91 - Gif-sur-Yvette (France); Fillion, E. [CEA Fontenay-aux-Roses, Direction de la protection et de la surete nucleaire, 92 (France)

    2011-02-15

    The CEA is tasked with carrying out certain research activities: within the Military Applications Division (DAM), research is focused on the nuclear deterrence and, within the Nuclear Energy Division, on developing the industrial nuclear systems of the future and optimising existing nuclear systems in partnership with EDF and AREVA. These major research and development themes entail a need for nuclear research and support facilities which must be maintained at a high level of performance and safety and, also, constantly upgraded to handle the research activities and programmes for which they are used. The CEA strategy is based on the right packaging of the radioactive liquid or solid waste into a form required for its transport, storage or disposal. The Caraibes software allows an efficient traceability of the waste packages. Most of the radioactive effluent processing stations of CEA are being upgraded

  6. When wastes valorization rhymes with environment; Quand valorisation des dechets rime avec environnement

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    In the framework of the Eco-Industries 2000 meeting, the ATEE organized a colloquium on the wastes valorization facing the environmental quality. This book presents the five papers proposed at this colloquium showing examples of wastes valorization in many domains: the organic wastes valorization for the compost, the cement industry, the packaging industry, the heat valorization of industrial sludges and old electric or electronic products collecting and processing. (A.L.B.)

  7. The recycling of wastes in Japan; Le recyclage des dechets au Japon

    Energy Technology Data Exchange (ETDEWEB)

    Georgel, O.

    2004-04-01

    The Japan economic growth of the second half of the 20. century and the increase of the internal consumption, led to the continuous increase of the wastes volume. The government took into account this problem only during the years 1990 because of the landfills saturation, and decided large legislative measures. Hopeful the japanese industry voluntarism, results have reach beyond the limits and rate fixed by the law. After a presentation of the wastes recycling policy in Japan, this report described the new techniques applied and the tendencies in the research development. Then the treatment of specific products are presented. (A.L.B.)

  8. 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...

  9. 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

  10. 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

  11. 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

  12. 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

  13. 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)

  14. 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

  15. 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.)

  16. 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

  17. 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

  18. 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)

  19. 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)

  20. Transformations of highly enriched uranium into metal or oxide; Etudes des procedes de transformation des composes d'uranium a fort enrichissement isotopique

    Energy Technology Data Exchange (ETDEWEB)

    Nollet, P; Sarrat, P [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1964-07-01

    described successively, together with the studies which led to their development The civil engineering construction was begun in June 1962. The workshops are to start production in may 1964. (authors) [French] Les ateliers de traitement d'uranium enrichi de Cadarache ont pour but: d'une part, de transformer l'hexafluorure d'uranium en metal, ou en oxyde, et d'autre part, de recuperer l'uranium contenu dans les dechets divers produits lors des operations de transformation metallurgique. Les principes qui ont ete suivis pour la conception et la securite de ces ateliers sont exposes. La securite nucleaire est basee sur la geometrie des appareils de traitement. Pour mettre au point les procedes et la technologie de ces ateliers, de nombreuses etudes ont ete conduites depuis 1960, dont certaines ont abouti a des realisations originales. La transformation de l'hexafluorure d'uranium a fort enrichissement isotopique s'effectue, soit par injection en phase gazeuse dans l'ammoniaque, soit par un procede original de reduction directe en tetrafluorure d'uranium par l'hydrogene. La recuperation de l'uranium contenu dans les dechets metalliques d'uranium-zirconium s'operera par attaque par l'acide chlorhydrique, puis traitement du chlorure d'uranium par le fluor afin d'obtenir l'uranium sous forme d'hexafluorure. La recuperation de l'uranium contenu dans les dechets divers s'opere par un procede classique de raffinage: grillage des dechets metalliques, dissolution de l'oxyde obtenu dans l'acide nitrique, purification par solvant au tributyl-phosphate, precipitation a l'ammoniaque, calcination reduction fluoruration, calciothermie et traitement des scories. Deux ateliers separes fonctionnent suivant ce procede: l'un traite l'uranium d'un enrichissement isotopique inferieur ou egal a 3 p. 100, l'autre est reserve aux forts enrichissements. La mise en oeuvre, d'une maniere nucleairement sure, de chacune des etapes du procede a pose des problemes technologiques particuliers et a conduit a

  1. 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)

  2. 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)

  3. 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.

  4. 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

  5. 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)

  6. 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.)

  7. 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)

  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. 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)

  12. 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.

  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. Ameliorer les performances environnementales des centrales a charbon pulverise via la co-combustion de combustible derive de dechets

    Science.gov (United States)

    Vekemans, Odile Geraldine

    Coal supplies around 28% of the world's energy needs and produces some 40% of the world's electricity. In the United States, close to 650 coal power plants currently produce electricity from coal, the majority of witch are equipped with pulverized coal boilers build in the 80's. Due to coal's intrinsic content in nitrogen and sulfur, its combustion is associated with high levels of NOx and SO2 emissions, that are responsible, among other thing, for acid rains. In order to help reduce SO2 emissions of coal power plant, this thesis focuses on the behaviour of a novel feedstock called ReEF(TM) or ReEngineered Feedstock(TM), developed by the company Accordant Energy LLCRTM, that combines non recyclable waste and alkaline sorbent. Since waste have a high calorific value and do not contain sulfur, and since alkaline sorbents (such as limestone) are able to react with SO2 and capture it in solid state, co-combustion of ReEF(TM) and coal could reduce SO2 emissions inside the furnace chamber itself. This technology easy to implement, as it requires a limited initial investment and limited additional space, could help avoid the construction of costly flue gas treatment unit downstream from the furnace. However, careless combustion of this engineered fuel could have disastrous consequences for the coal power plant owners. This thesis, then, deliver one among the first experimental study of co-combustion of coal and ReEF(TM) in conditions characteristic of pulverized coal boilers. As a first step, in order to get familiarize with the feedstock under study, the thermal degradation of a ReEF(TM) without sorbent and of its components is analyzed by thermogravimetry. With the analysis of more than 70 samples at heating rates ranging from 5°C/min to 400°C/min we are able to conclude that ReEF(TM) thermal degradation can be seen as the independent thermal degradation of its components, as long as heat transfer limitations are taken into account. Thus, no substantial chemical interactions between ReEF(TM) components take place during its devolatilization. During the second step of this study, performances of the co-firing of coal and sorbent are compared to that of co-combustion of coal and ReEF(TM) without sorbent. This is carried out in a reactor specially build for this study, capable of reproducing the contact mode between gas and particles, the concentrations, the temperature gradient and the pressure typical of pulverized coal boiler. SO2 emissions reduction around 20% are observed in presence of CaCO3 and of Ca(OH)2 compared to the coal baseline, reduction that generally increased with the increase of sorbent molar ratio compared to sulfur (also called stoic). As for the co-combustion of 20%th of ReEF(TM) and coal, a SO2 emission reduction around 20% is also measured, with no clear effect of ReEF(TM) composition (fiber to plastic ratio). On the other hand, the HCl level that is negligible during coal combustion with and without sorbent, reaches around 20ppm in presence of ReEF(TM), and increases proportionally with the ReEF(TM) plastic content. The first step of this work consists in the study of the co-combustion of coal and ReEF(TM) containing limestone (CaCO3), a mix of sodium bicarbonate (NaHCO3) and limestone, as well as a mix of trona (Na2CO3.NaHCO3.H2O) and limestone. The amount of sorbent in the ReEF(TM) as well as the feeding parameters are adjusted to reach a 20%th feeding of ReEF(TM) compared to coal, to inject sorbents at a stoic of 1, 2 and 2.5 and to obtain Na/Ca molar ratios of 0, 0.1 with trona and NaHCO3, and 0.5 with NaHCO 3 only. Globally, as in the case of sorbent alone, the increase of the total stoic of the feed leads to increased SO2 capture. For a given stoic, to combine waste and limestone in the ReEF(TM), compared to using limestone alone, allows to reach higher levels of SO2 emissions reduction. The combination of sodium-based and calcium-based sorbent even leads to record SO2 emissions reduction of more than 50% with trona, and more than 40% with NaHCO3, at gas residence time in the reactor four time smaller than typical residence time of PCB. Furthermore, the lower fuel-N content of the ReEF(TM), compared to coal, also leads to lower NOx emissions. Combustion of ReEF(TM) with trona is even associated with NOx emissions reduction of more than 50%, possibly due to sodium induced NO reduction. Finally, regarding HCl emissions, chlorine capture by the sorbents leads to HCl levels comparable to that of coal alone. Even if, from the point of view of pollutant emissions, the results are promising, co-feeding ReEF(TM) with sorbent was nonetheless associated with heavy formation of melted ash deposits in the reactor. Deposition probes are used to compare the magnitude of the deposition in function of the ReEF(TM) sorbent composition. With those probes, we are able to figure out that slag formation is quite severe in presence of NaHCO3, and all the more that the Na/Ca ratio is high, but is less severe in presence of limestone alone, and isn't at all problematic in presence of trona. Those results all seem to indicate that co-combustion of coal and 20%th ReEF(TM) containing limestone and trona at a Na/Ca ratio of 0.1 and at a total stoic of 2 is the most adequate composition for application in existing PCB. In all those experiments a single measure of the emissions at the exit of the reactor is conducted, the emissions being associated with a federate of gas and solid and a temperature profile along the reactor. In order to gain insight regarding the behaviour of the gas and the particles inside the reactor, a phenomenological model combining more than 30 reaction kinetics is developed. This model allows us, without any fitting parameter, to predict the CO2, SO2 and NOx emissions measured at the outlet of the reactor. This model is easily adapted to the different ReEF(TM) compositions and was able to take into account the various particle sizes. The model is then used to evaluate potential SO2 emissions reduction that could be obtain with ReEF(TM) co-combustion for a residence time and a temperature profile measured in an existing pulverized coal boiler. Those simulations indicate that SO2 emissions reduction up to 85% could be obtain at the exit of the furnace chamber with a 20%th coal feed substitution by ReEF(TM) containing limestone and trona. Co-combustion of ReEF(TM) in pulverized coal boiler is therefore sensible from the point of view of pulverized coal boiler environmental performances, as long as the ReEF(TM) composition is chosen wisely and is tested beforehand in conditions similar to that of PCB. Furthermore, since ReEF(TM) co-combustion allows electricity production at high efficiency from waste, it is also sensible in terms of waste energetic valorization.

  15. Departmental plans of domestic wastes management - evaluation 2002; Plans departementaux d'elimination des dechets menager assimiles - bilan 2002

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-03-01

    The departmental plans of domestic wastes management are official documents which manage the actions needed to realize the legislative and regulation objectives concerning the domestic wastes and related wastes. A first evaluation has been realized in 1997 for 47 edited plans. In the context of the new wastes policy a new evaluation has been realized by the ADEME in 2002 for 98 plans. It provides the methodology of the study, the analysis of the plans, the sites and management of wastes, economic data, the equipment and investments. (A.L.B.)

  16. The storage center of very-low level radioactive wastes; Le centre de stockage des dechets de tres faible activite

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    The low level radioactive wastes have a radioactivity level as same as the natural radioactivity. This wastes category and their storage has been taken into account by the french legislation. This document presents the storage principles of the site, containment, safety and the Center organization. (A.L.B.)

  17. Energy recovery from waste processing; La recuperation de l'energie issue du traitement des dechets

    Energy Technology Data Exchange (ETDEWEB)

    Prevot, H.

    2000-07-15

    This report discusses the feasibility of energy production by waste reprocessing. After an analysis of the situation, the different steps of the methane and gas production, are detailed. Many scenari of energy efficiency are compared. The report proposes also solutions to enhance the treatment units of energy production. Propositions are discussed around five main axis: the energy improvement and the product improvement, the safety and the public health, the compensation by economical tools of the greenhouse effect impacts, the competition equilibrium between energy produced by the wastes and other energy forms and the decrease of the processing cost of wastes producing energy. (A.L.B.)

  18. Industrial solid and liquid waste treatment processes; Les procedes de traitement des dechets industriels solides et liquides

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    1995-11-01

    This catalogue gives information on 68 chemical, mechanical, magnetic, electrical, thermal, etc. techniques for the processing of solid, viscous and liquid, common or special, industrial wastes. The various processes are presented as files, which are easily retrievable through keywords, waste type or industry codes, processing types, distributors. Technologies, performances and applications of each techniques are presented, together with references and company contacts

  19. Strategy for nuclear wastes incineration in hybrid reactors; Strategies pour l'incineration de dechets nucleaires dans des reacteurs hybrides

    Energy Technology Data Exchange (ETDEWEB)

    Lelievre, F

    1998-12-11

    The transmutation of nuclear wastes in accelerator-driven nuclear reactorsoffers undeniable advantages. But before going into the detailed study of a particular project, we should (i) examine the possible applications of such systems and (ii) compare the different configurations, in order to guide technological decisions. We propose an approach, answering both concerns, based on the complete description of hybrid reactors. It is possible, with only the transmutation objective and a few technological constraints chosen a posteriori, to determine precisely the essential parameters of such reactors: number of reactors, beam current, size of the core, sub-criticality... The approach also clearly pinpoints the strategic decisions, for which the scientist or engineer is not competent. This global scheme is applied to three distinct nuclear cycles: incineration of solid fuel without recycling, incineration of liquid fuel without recycling and incineration of liquid fuel with on-line recycling; and for two spectra, either thermal or fast. We show that the radiotoxicity reduction with a solid fuel is significant only with a fast spectrum, but the incineration times range from 20 to 30 years. The liquid fuel is appropriate only with on-line recycling, at equilibrium. The gain on the radiotoxicity can be considerable and we describe a number of such systems. The potential of ADS for the transmutation of nuclear wastes is confirmed, but we should continue the description of specific systems obtained through this approach. (author)

  20. Wastes behavior and environmental impacts, researches and methods; Comportement des dechets et impacts environnementaux, recherches et methodes

    Energy Technology Data Exchange (ETDEWEB)

    Labeyrie, J; Chateau, L [Agence de l' Environnement et de la Maitrise de l' Energie, (ADEME), 49 - Angers (France); Gin, St [CEA/VALRHO - site de Marcoule, Dept. de Recherche en Retraitement et en Vitrification DRRV, 30 - Marcoule (France); and others

    2001-07-01

    The wastes management policy takes into account more and more often the environmental impacts mastership. This evolution is particularly appreciable when the wastes directly interact with the environment: storage, utilization for roads construction and so on. In this context the ADEME organized the 8 june 2000 a colloquium to present the new evaluation methods and tools, to describe the regulations and to identify the research programs needed for this environmental policy. Eleven papers are presented. (A.L.B.)

  1. Long lived nuclear waste transmutation: context and trends; L`incineration des dechets nucleaires a vie longue, contexte et perspectives

    Energy Technology Data Exchange (ETDEWEB)

    Prunier, C; Pacton, L

    1994-12-31

    After a recall of the actual strategy, in France, for the radioactive wastes, we give an overview of the programs CAPRA and SPIN (Separation-Incineration) for separate the minors actinides (Am,Np,..) and then to reduce the radiological risk create by these products by incineration in a LMFBR. 13 figs, 1 annexe.

  2. 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.)

  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. The health physics of installations for decladding irradiated fuels or for handling radio-elements at Marcoule; La radioprotection des installations de degainage des combustibles irradies et des radio-elements a Marcoule

    Energy Technology Data Exchange (ETDEWEB)

    Chassany, J; Guillermin, P; Mallet, P [Commissariat a l' Energie Atomique, Centre de Production de Plutonium de Marcoule, 30 - Chusclan (France)

    1966-07-01

    Radiation protection practices for handling reactor fuel elements are described. Elements of considerable specific radioactivity are handled under water. A study was made of water filtration and of ventilation in the building. The installations are divided up into zones depending on the radioactive risks, and the radiation level atmospheric contamination are the object of a systematic control at various points. A description is given of all aspects of health physics which have been encountered during six years: storage, transfer of radioactive material; decladding, rolling, waste disposal, specialized operations, installations in operation and at rest, and transport. In spite of the gradual increase in the activity of these installations, the total doses received by the personnel have hardly altered and the number of cases of physical contamination has diminished. (authors) [French] Dans ces installations, se manipulent sous l'eau des elements a radioactivite specifique considerable. La filtration de l'eau, la ventilation ont ete particulierement etudiees. L'ensemble a ete divise en lieux classes en fonction des risques radioactifs et des appareils controlent en permanence l'irradiation et la contamination atmospherique en certains points. Tous les aspects de la radioprotection resultant de six annees d'experience relatifs: au stockage, au deconteneurage, au degainage, au laminage, a l'evacuation des residus, aux travaux particuliers, installations en marche et a l'arret, et aux transports sont successivement decrits. Malgre l'accroissement progressif de l'activite de cet ensemble, les doses integrees par le personnel n'ont pratiquement pas augmente et le nombre des cas de contamination corporelle a diminue. (auteurs)

  5. Decontamination of surfaces (1961); La decontamination des surfaces (1961)

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-07-01

    The continued expansion of atomic Energy has led the S.C.R.G.R. to extend simultaneously the recovery of materials contaminated by use in radio-active media. The importance of this aspect of atomic Energy was not immediately obvious to those concerned but is now fully recognized due to the cost of the materials and installations, and also to the time required for the construction of special equipment for the C.E.A. Another very important reason is the dangers associated with the handling of contaminated material. The S.C.R.G.R. attacked this problem from the point of view of these dangers. It later became apparent to the users, once the decontamination methods had proved their worth, that the process presented advantages from the material and cost-saving point of view. (author) [French] Le developpement toujours croissant de l'Energie atomique a conduit le S.C.R.G.R. a developper parallelement la recuperation des materiels contamines par leur emploi en milieu radioactif. Cet aspect de l'Energie atomique n'est pas apparu des le debut aux utilisateurs mais s'est tres vite impose etant donne, d'une part, le cout des installations et du materiel, d'autre part le temps necessaire a la fabrication d'un materiel special aux travaux du C.E.A., enfin et surtout, les risques associes a la manipulation d'un materiel contamine. Les risques seuls ont ete pris comme point de depart a l'examen de ce probleme par le S.C.R.G.R. puis avec le temps, les methodes de decontamination ayant fait leur preuve, les utilisateurs ont alors apercu les aspects materiels et la rentabilite de la decontamination. (auteur)

  6. Lytic process studies on anaerobic digestion of organic wastes. Etude des activites lytiques intervenant au cours de la digestion anaerobie des dechets organiques; Rapport final

    Energy Technology Data Exchange (ETDEWEB)

    Durecu, S.; Thauront, J. (PEC Engineering, 95 - Cergy Pontoise (France). Service de Recherche et Developpement); Festino, C.; Aubart, C.; Reisinger, O. (Nancy-1 Univ., 54 - Vandoeuvre-les-Nancy (France). Lab. d' Ecologie Microbienne)

    1990-01-01

    To improve anaerobic digestion of pig manure, solubilization of the solid fraction was studied as the rate limiting step in the biomethanation process in an experimental completely mixed digester. The performance of conventional digesters should anaerobic microflora were inefficient in degrading complex biopolymers such as plant fibers. For pectin or cellulose, the use of digestible co-substrates accelerated methanation by increasing the yield of methane and a doubling of the apparent first order solubilization rate constant (Kp = 0.090/d). Lignin should methanation by decreasing methane yield and reducing the rate constant (Kp = 0.035/d). This inhibition was unrelated to volatile fatty acid accumulation. Nine strains of pectinolytic and/or cellulolytic bacteria were isolated. Chitin, a structural constituent of many final species, was effectively solubilized dining anaerobic digestion of pig manure. Seven strains of chitinolytic bacteria were isolated by high chitnese activity. The mycolytic power of fermenting manure processes acting through lytic microflora has been shown to be an effective antagonist of soil borne phytopathogenic fungi, as well as a fertilizer. In greenhouse trails, this compiled fraction demonstrated its ability to control flux unit. Keratin enhanced methane production, and increased H{sub 2}S nearly six-fold. Bacterial strains able to solubilize keratin were also used in autoclawed feather meal to extract the amino acids. (KJD)

  7. The future of the nuclear wastes and the spent fuels at the United States; Le devenir des dechets nucleaires et des combustibles uses aux Etats-Unis

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    The USA regulation distinguishes three classes of nuclear wastes: the low activity wastes under the federal states control, the wastes contaminated by long life radionuclides (transuranic elements) and the high activity wastes. The two last classes are controlled by the DOE (Department of energy). The different classes management are discussed as the DOE obligations towards the operators, the storage project of Yucca Mountain and Private fuel storage of Skull Valley. (A.L.B.)

  8. Improvement of the greenhouse effect accounting of the waste storage installations; Ameliorer le bilan effet de serre des installations de stockage des dechets

    Energy Technology Data Exchange (ETDEWEB)

    Couturier, Ch.

    2003-07-01

    The wastes storage installations are responsible of 3 to 4 % of the greenhouse gases emissions in France and Europe. In spite of the decrease since ten years of the emissions hopeful the gas collect on the main sites, it is still possible to improve the greenhouse gases emission in the wastes disposals. The possible measures are presented: the bio-reactor, the improvement of the gas extraction systems, the choice of exploitation modes to limit the fill in times, the biogas valorization. (A.L.B.)

  9. Vade mecum for managers of collective waste methanation projects; Vade-Mecum du porteur de projet de methanisation des dechets des collectivites

    Energy Technology Data Exchange (ETDEWEB)

    Deffontaine, P. [Vice-President Charge des Dechets Menagers, Lille Metropole Communaute Urbaine, 59 (France); Guillet, R. [Commission Dechets et Proprete de l' Astee, Conseil General des Mines (France)

    2006-07-01

    This document is the result of a collective work carried out by the 'biological treatment' working group of the 'wastes and cleanliness' commission of the French scientific and technical association for the water and the environment (ASTEE). It presents the different forms of implementation of the methanation or anaerobic digestion of organic fermentescible wastes. Each process has its advantages and drawbacks which are presented in this guidebook. It deals with the following points: when implementing methanation? (context of methanation and solid wastes, status of wastes methanation, biological mechanisms), upstream and inputs management (authorized wastes, typology, parameters to be considered, organization of wastes pre-collection and collection), processes implemented (parameters of the methanation process, operation of a methanation unit, technical status of some methanation facilities in operation, mass transfer status), valorization of methanation products (biogas, compost, liquid effluents), construction and operation (projects complexity and schedules, parameters to be considered, cost-benefit analysis), regulatory context (typology of sub-contexts, wastes management, legal aspects of facilities classified for environment protection, management of fertilizing matters, renewable energies), conclusion, glossary. (J.S.)

  10. The Economic representation of environmental consumer behavior. The case of household waste; Representation economique du comportement ecologique des consommateurs. Le cas des dechets menagers

    Energy Technology Data Exchange (ETDEWEB)

    Jolivet, P.

    2001-12-01

    This PhD dissertation deals with the economic representation of consumer behavior with regards to their environmental conscience. The particular focus point is the production of household wastes, which is analyzed from a dual point of view: on the one hand as a consequence of consumption activities, and as a specific economic choice activity on the other. The central problem of this dissertation is thus the following: can the phenomenon 'waste' be economically represented as an individual consumption act? The first part of this thesis deals with the environmental sensitivity of consumers in general, and their sensitivity for waste in particular. It is supposed that individuals can integrate the environment in their consumption choices, when buying products on the market: this is defined as continuous environmental rationality. The second part develops the behavior of an individual that decides to separate its waste. On the basis of a qualitative survey among households, their discourse and actions are analyzed in order to define the behavior of a waste consumer-producer. One of the results of our survey is the assumption that when economic agents have an environmental conscience, this latter is not necessarily translated into consumption choices. The conscience for household wastes, which occur only after the consumption moment, defines a discontinuous environmental rationality. On this basis, we suggest to widen the traditional analytical framework of household consumption. (author)

  11. 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)

  12. Study of the aqueous chemical treatment of uranium zirconium fuels; Etude du traitement chimique des combustibles uraniumzirconium par voie seche

    Energy Technology Data Exchange (ETDEWEB)

    Bourgeois, M; Nollet, P [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1964-07-01

    A dry process has been studied for separating the uranium from the zirconium-either for recovering the enriched uranium from fuel element production waste, or with a view to treating this waste after irradiation. In this process the alloy is treated with hydrochloric acid at 400 deg. C in a fluidized corundum bed which causes the zirconium to volatilize as tetrachloride and the uranium to form the trichloride. This latter is then converted to the hexafluoride by attack with fluorure. After the laboratory tests, a first pilot plant with a capacity of 1 kg of alloy was tried out at the Fontenay-aux-Roses Nuclear Research Centre; this made it possible to fix the operational conditions for the process. An industrial scale plant was then built with the collaboration of the from Kuhlmann, and operated until a satisfactory process had been developed for treating the waste. This installation treats 3 kg/h of alloy with a yield for the hydrochloric acid of about 50 per cent and with a uranium loss in the zirconium tetrachloride of about 0.1 per cent. An active pilot plant capable of treating of treating a few kilos of irradiated alloy is now being studied. (authors) [French] On a etudie un procede de voie seche pour effectuer la separation de l'uranium et du zirconium - soit en vue de la recuperation de l'uranium enrichi contenu dans les dechets de fabrication des elements combustibles - soit en vue du traitement de ceux-ci apres irradiation. Ce procede consiste a attaquer l'alliage par l'acide chlorhydrique a 400 deg. C dans un lit fluidise de corindon, ce qui a pour effet de volatiliser le zirconium sous forme de tetrachlorure et de transformer l'uranium en trichlorure. Ce dernier est ensuite converti en hexafluorure par action du fluor. Apres des essais de laboratoire, un premier pilote a l'echelle de 1 kg d'alliage a ete experimente au Centre d'Etudes Nucleaires de Fontenay-aux-Roses et a permis de determiner les conditions operatoires du procede. En collaboration avec

  13. ANALYSE DES PERCEPTIONS LOCALES ET DES FACTEURS ...

    African Journals Online (AJOL)

    AISA

    1Faculté des Sciences Agronomiques (FSA), Université d'Abomey-Calavi (UAC), 01 BP 526 Cotonou Bénin. Email : cgbemavo@yahoo.fr. 2Institut National des Recherches Agricoles du Bénin, Centre de Recherches Agricoles d'Agonkanmey (CRA-A),. Laboratoire des Sciences du Sol, Eau et Environnement (LSSEE).

  14. 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...

  15. 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

  16. 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

  17. Handling and transport problems (1960); Problemes de manipulation et de transport (1960)

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

    I. The handling and transport of radioactive wastes involves the danger of irradiation and contamination. It is indispensable: - to lay down a special set of rules governing the removal and transport of wastes within centres or from one centre to another; - to give charge of this transportation to a group containing teams of specialists. The organisation, equipment and output of these teams is being examined. II. Certain materials are particularly dangerous to transport, and for these special vehicles and fixed installations are necessary. This is the case especially for the evacuation of very active liquids. A transport vehicle is described, consisting of a trailer tractor and a recipient holding 500 litres of liquid of which the activity can reach 1000 C/l; the decanting operation, the route to be followed by the vehicle, and the precautions taken are also described. (author) [French] I. La manipulation et le transport des dechets radioactifs presentent des dangers d'irradiation et de contamination. Il est necessaire: - d'edicter des consignes speciales applicables a l'enlevement et au transport des dechets dans les centres ou de centre a centre; - de confier les transports a un groupe dont relevent des equipes specialisees; - on examine l'organisation, les moyens, le rendement de ces equipes. II. Certains transports sont particulierement dangereux et necessitent des engins speciaux et des installations fixes. C'est le cas, notamment de l'evacuation des liquides tres actifs. On decrit: - un engin de transport compose d'un ensemble a tracteur semi-remorque et d'un recipient qui contient 500 litres de liquide dont l'activite peut atteindre 1000 C/l; - les operations de transvasement, l'acheminement de l'engin, les precautions prises. (auteur)

  18. Modelisation des effets physico-techniques pour la conception des ...

    African Journals Online (AJOL)

    automatisation dans les installations industrielles a besoin d'une régulation automatique des commandes des processus technologiques pour lesquelles certaines contraintes sont à relever compte tenu des exigences des innovations scientifiques de ...

  19. Radioisotopes in sedimentology; Emploi des radioelements en sedimentologie

    Energy Technology Data Exchange (ETDEWEB)

    Courtois, G [CEA, Centre d' etudes Nucleaires de Saclay (France)

    1967-05-15

    infirmation de theses de transport, recherches des phenomenes fondamentaux de transport associees a des experiences en canaux. Apres avoir evoque les possibilites des traceurs naturels, ou dus a des retombees radioactives ou a des rejets d'effluents radioactifs, l'auteur aborde les aspects techniques de l'utilisation des traceurs artificiels: le choix du radioisotope, le marquage superficiel et massique avec mention particuliere du probleme des vases, les appareils d'immersion et de detection, les problemes de navigation et de reperage topographique . Dans la partie concernant l'exploitation des resultats, le probleme de l'obtention de resultats quantitatifs est traite et les methodes proposees decrites; l'auteur fait egalement etat des tentatives actuelles tres louables en vue de relier les tres nombreuses theories de transport de sediments aux parametres mesures sur le terrain au moyen de traceurs radioactifs. Il developpe egalement quelques aspects lies aux problemes de securite. Les methodes decrites peuvent etre egalement appliquees a des problemes voisins et fort interessants: les problemes d'erosion des sols, de stabilisation des terrains, de deplacement des dunes. Quelques indications succinctes sont donnees sur ce sujet. En conclusion, l'auteur indique aussi clairement que possible le potentiel actuel de la methode, ses limitations et les travaux souhaitables pour I'ameliorer. -Mesures en continu de la turbidite. Le transport solide en suspension etant en general beaucoup plus important que le charriage de fond, il importe de pouvoir le mesurer de facon continue; l'auteur donne quelques exemples de l'utilite d'un tel renseignement. Une telle mesure peut etre faite par des jauges decrites dans les ouvrages publies et dont on donne les principes et performances en fonction de la bibliographie connue. L'auteur donne egalement les resultats susceptibles d'etre obtenus en mesurant la turbidite par la radioactivite naturelle d'un sediment en suspension et compare les deux

  20. 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

  1. 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

  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. 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)

  4. 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

  5. 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)

  6. 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

  7. 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

  8. 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)

  9. Wastes and health: representation of sanitary risks linked to wastes and to their processing modes; Dechets et sante: representations des risques sanitaires lies aux dechets et a leurs modes de traitement

    Energy Technology Data Exchange (ETDEWEB)

    Lhuilier, D.; Cochin, Y.

    1999-10-01

    This research has for objective the analysis of perception of sanitary risks in relation with wastes and the waste processing facilities. This work in at the intersection of the sociological study and the psychologic one. (N.C.)

  10. variabilite des productions et des revenus des exploitations

    African Journals Online (AJOL)

    3Centre de coopération internationale en recherche agronomique pour le développement (CIRAD), UMR Innovation,. Montpellier, France. Doubangolo COULIBALY, Email kone_b@yahoo.fr. RESUME. La durabilité des systèmes de production à base de coton dans un contexte de variabilité des prix aux producteurs et de ...

  11. The pretreatment of uranium ores by physical processing; Les problemes de la preconcentration des minerais d'uranium par voie physique

    Energy Technology Data Exchange (ETDEWEB)

    Vuchot, L; Ginocchio, A; Hubert, G; Roques, E; Sandier, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    After giving an outline of the classical means of physical processing - granulometry, gravimetry, flotation, magnetism, electrostatics, the authors study the methods peculiar to radioactive ores: pretreatment in batches (counting cylinders) or stone by stone (electronic sorting belt). The three factors to be considered in any treatment operation are studied (cost of the operation, metal recovery, ratio of concentration), as well as their bearing on the cost and the productivity of the following operations. Making use of radioactivity in order to find out instantaneously the approximate grade of the obtained product makes it possible to reduce costs and improve results by setting up total automation. (author) [French] Apres un apercu des procedes classiques de concentration physique des minerais - granulometrie, gravimetrie, flottation, magnetisme et electrostatique, les auteurs s'attachent aux methodes propres aux minerais radioactifs: preconcentration par lots (cylindre de comptage) ou caillou par caillou (bande de triage electronique). Les trois facteurs a considerer lors de toute operation de traitement sont etudies (prix de revient de l'operation, rendement metal et rendement poids), ainsi que leurs repercussions sur les prix de revient et rendements des traitements ulterieurs. L'utilisation de la radioactivite pour determiner instantanement la teneur approximative des produits obtenus permet d'envisager de reduire les prix de revient et d'ameliorer les resultats par une automatisation totale. (auteur)

  12. The pretreatment of uranium ores by physical processing; Les problemes de la preconcentration des minerais d'uranium par voie physique

    Energy Technology Data Exchange (ETDEWEB)

    Vuchot, L.; Ginocchio, A.; Hubert, G.; Roques, E.; Sandier, J. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    After giving an outline of the classical means of physical processing - granulometry, gravimetry, flotation, magnetism, electrostatics, the authors study the methods peculiar to radioactive ores: pretreatment in batches (counting cylinders) or stone by stone (electronic sorting belt). The three factors to be considered in any treatment operation are studied (cost of the operation, metal recovery, ratio of concentration), as well as their bearing on the cost and the productivity of the following operations. Making use of radioactivity in order to find out instantaneously the approximate grade of the obtained product makes it possible to reduce costs and improve results by setting up total automation. (author) [French] Apres un apercu des procedes classiques de concentration physique des minerais - granulometrie, gravimetrie, flottation, magnetisme et electrostatique, les auteurs s'attachent aux methodes propres aux minerais radioactifs: preconcentration par lots (cylindre de comptage) ou caillou par caillou (bande de triage electronique). Les trois facteurs a considerer lors de toute operation de traitement sont etudies (prix de revient de l'operation, rendement metal et rendement poids), ainsi que leurs repercussions sur les prix de revient et rendements des traitements ulterieurs. L'utilisation de la radioactivite pour determiner instantanement la teneur approximative des produits obtenus permet d'envisager de reduire les prix de revient et d'ameliorer les resultats par une automatisation totale. (auteur)

  13. Contribution to the study of the biological properties of compounds labeled with radio-chromium {sup 51}Cr; Contribution a l'etude des proprietes biologiques des composes marques au radiochrome {sup 51}Cr

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-15

    Among the radioisotopes commonly used in biology and medicine which are controlled Individually in the Radioelement Departement of the Saclay Nuclear Research Centre before being sent to the users, the author has chosen chromium 51 incorporated in inorganic salts or in organic substrates for a study of the biological properties of the compounds. In the first part, he has compared the pathways followed by the radioactive sodium chromate and chromic chloride mixed with blood or given to the whole animal, the object being to determine whether a reduction of hexavalent chromium occurs, both in vitro and in vivo. In the second part, the author has tried to show the validity of using, various substrates labeled with chromium 51, red cells, haemoglobin, plasma proteins and cytochrome c. The results obtained have contributed to underline the interest of using such compounds for biological applications. (author) [French] Parmi les radioisotopes d'utilisation courants en biologie et en medecine qui sont l'objet d'un controle particulier dans le Departement des Radioelements du Centre d'Etudes Nucleaires de Saclay avant leur diffusion aux utilisateurs, l'auteur a choisi le chrome 51 incorpore a des sels mineraux ou a des substrats organiques, afin d'en etudier les proprietes biologiques. Dans la premiere partie, il a compare le sort du chromate de sodium et du chlorure chromique radioactifs melanges a du sang ou administres a l'animal entier en s'efforcant de mettre en evidence une reduction du chrome hexavalent aussi bien in vitro qu'in vivo. Dans la deuxieme partie, il a cherche a etablir la validite de l'emploi de differents substrats marques au chrome 51, l'hematie, l'hemoglobine, les proteines plasmatiques et le cytochrome c. Les resultats obtenus ont permis de souligner le reel interet des applications biologiques des composes marques par le radioisotope. (auteur)

  14. Contribution to the study of the biological properties of compounds labeled with radio-chromium {sup 51}Cr; Contribution a l'etude des proprietes biologiques des composes marques au radiochrome {sup 51}Cr

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-15

    Among the radioisotopes commonly used in biology and medicine which are controlled Individually in the Radioelement Departement of the Saclay Nuclear Research Centre before being sent to the users, the author has chosen chromium 51 incorporated in inorganic salts or in organic substrates for a study of the biological properties of the compounds. In the first part, he has compared the pathways followed by the radioactive sodium chromate and chromic chloride mixed with blood or given to the whole animal, the object being to determine whether a reduction of hexavalent chromium occurs, both in vitro and in vivo. In the second part, the author has tried to show the validity of using, various substrates labeled with chromium 51, red cells, haemoglobin, plasma proteins and cytochrome c. The results obtained have contributed to underline the interest of using such compounds for biological applications. (author) [French] Parmi les radioisotopes d'utilisation courants en biologie et en medecine qui sont l'objet d'un controle particulier dans le Departement des Radioelements du Centre d'Etudes Nucleaires de Saclay avant leur diffusion aux utilisateurs, l'auteur a choisi le chrome 51 incorpore a des sels mineraux ou a des substrats organiques, afin d'en etudier les proprietes biologiques. Dans la premiere partie, il a compare le sort du chromate de sodium et du chlorure chromique radioactifs melanges a du sang ou administres a l'animal entier en s'efforcant de mettre en evidence une reduction du chrome hexavalent aussi bien in vitro qu'in vivo. Dans la deuxieme partie, il a cherche a etablir la validite de l'emploi de differents substrats marques au chrome 51, l'hematie, l'hemoglobine, les proteines plasmatiques et le cytochrome c. Les resultats obtenus ont permis de souligner le reel interet des applications biologiques des composes marques par le radioisotope. (auteur)

  15. Formation and evolution of aerosols in filtered air and in natural air. Effect of radioactivity; Formation et evolution des aerosols dans l'air filtre et dans l'air naturel action de la radioactivite

    Energy Technology Data Exchange (ETDEWEB)

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

    1968-06-01

    Results are presented concerning the formation, the evolution, the coagulation and the electrical charge of aerosols which form in natural filtered air containing only gaseous impurities, under the influence of solar light (photolysis) and of radioactive disintegrations (radiolysis). The modifications brought about in the aerosol by an increase in the sulphur dioxide content and in the natural radioactive gas content are studied. The work is then repeated with non-filtered natural atmospheric air. A comparison is also made of the behaviour of non-radioactive and radioactive particles (active thoron deposit). In conclusion, the possible consequences of these phenomena on the origin and the size distribution of particles occurring in the atmosphere is considered. (author) [French] On expose les resultats obtenus sur la formation, l'evolution, la coagulation et la charge electrique des aerosols qui se forment dans l'air naturel filtre, ne contenant que des impuretes gazeuses, sous l'influence de la lumiere solaire (photolyse) et des desintegrations radioactives (radiolyse). On examine les modifications apportees a l'aerosol forme par l'augmentation de la teneur de l'air en anhydride sulfureux et en gaz radioactif naturel. Cette etude est ensuite reprise mais avec de l'air naturel atmospherique non filtre. On compare egalement le comportement des particules non radioactives et radioactives (depot actif du thoron). En conclusion, on examine les consequences que peuvent avoir ces phenomenes sur l'origine et la granulometrie des particules contenues dans l'atmosphere. (auteur)

  16. Civili, langue des Baloango

    DEFF Research Database (Denmark)

    Mavoungou, Paul Achille; Ndinga-Koumba-Binza, Hugues Steve

    , Congo, Angola, etc.) issus de la décolonisation. Il présente de façon succincte quelques phénomènes historiques, phonologiques, morphosyntaxiques, homonymiques et analogiques de la langue. Des faits sémantiques des emprunts linguistiques y sont également décrits dans le cadre des changements...

  17. 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

  18. Des racines et des ailes

    Directory of Open Access Journals (Sweden)

    Stéphanie Vincent-Geslin

    2012-05-01

    Full Text Available Les mobilités pendulaires semblent être en augmentation en Europe depuis une dizaine d’années. Cette croissance du temps passé à se déplacer amène à remettre en question la conjecture de Zahavi et apparaît relativement inexplicable en regard du paradigme classique de l’acteur rationnel traditionnellement utilisé dans le champ des transports. Si, dans la littérature, les temps de déplacements sont principalement expliqués par le contexte résidentiel, la forme urbaine et le travail, ce cadre explicatif ne dit rien des processus de décision eux-mêmes qui amènent aux pendularités intensives.À partir d’une enquête qualitative menée auprès de pendulaires français, suisses et belges, cette contribution propose d’analyser les arbitrages et les éléments déterminants des processus de la grande pendularité. Les mobilités quotidiennes pendulaires apparaissent comme le résultat de compromis entre activité professionnelle, attachement résidentiel et choix de vie et prennent ainsi la forme de stratégies de conciliation entre vie privée et vie professionnelle. Ces mobilités spatiales permettent alors paradoxalement la préservation des ancrages résidentiels, sociaux et familiaux.Roots and wings. Long-distance commuting patterns, or how to conciliate professional and personal lifeLong-distance commuting patterns appear to be increasing in Europe over the last ten years. These raising mobility patterns lead to reappraise the Zahavi conjecture and appear largely inexplicable by the classical rational actor paradigm traditionally used in transportation research. In literature, commuting is mainly explained by residential contexts, urban forms and job. Nevertheless this theoretical frame says little about the decision-making processes themselves. Based on a qualitative survey conducted in three European countries - France, Belgium and Switzerland – among a population of high commuters, this paper proposes an analysis of

  19. 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

  20. A study of some radioprotection apparatuses used in the case of pool reactors; Etude de quelques dispositifs de radioprotection en service aupres des piles piscines

    Energy Technology Data Exchange (ETDEWEB)

    Robien, E de; Choudens, H de; Delpuech, J [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

    1965-07-01

    necessite de mesurer avec une bonne precision des doses {gamma} a l'aide d'un appareil autonome a conduit a la realisation d'un dosiinetre {gamma} a scintillateur plastique; d) l'obligation de condamner l'ouverture des portes de certains locaux ou il risque d'y avoir une intensite de rayonnement forte a conduit a realiser un asservissement de l'ouverture de ces portes a l'intensite de rayonnement a l'interieur des locaux; e) les degagements d'iode radioactif ont ete mesures a l'aide de cartouches de charbon actif entourant un scintillateur relie a un monocanal; f) enfin, la commande de chute des barres des piles, en cas d'accident radioactif, a ete assuree par une chaine dont le detecteur est une chambre immergee dans la piscine, ce qui offre, dans le cas particulier des reacteurs piscines a couche chaude, le double avantage de pouvoir 'piloter' la couche chaude et de s'affranchir des rayonnements transitoires apparaissant dans le hall du reacteur au moment du defournement des dispositifs experimentaux. (auteurs)

  1. Bitumen coating of the radio-active sludges from the effluent treatment plant at the Marcoule centre. Review of the progress reports 1, 2, 3 and 4 (1963); Enrobage par le bitume des boues radioactives de la station de traitement des effluents du centre de Marcoule. Mise au point des etats d'avancement 1, 2, 3 et 4. (1963)

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-07-01

    dont la structure sera homogene et dont la matiere sera inerte vis-a-vis des milieux de stockage (sol, mer, etc.). Nous avons propose d'enrober ces produits radioactifs avec du bitume. Ce document a pour but de faire le point des etudes poursuivies sur cette methode. Il constitue plutot un etat d'avancement des recherches qu'une mise au point definitive. (auteurs)

  2. Bitumen coating of the radio-active sludges from the effluent treatment plant at the Marcoule centre. Review of the progress reports 1, 2, 3 and 4 (1963); Enrobage par le bitume des boues radioactives de la station de traitement des effluents du centre de Marcoule. Mise au point des etats d'avancement 1, 2, 3 et 4. (1963)

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-07-01

    sera homogene et dont la matiere sera inerte vis-a-vis des milieux de stockage (sol, mer, etc.). Nous avons propose d'enrober ces produits radioactifs avec du bitume. Ce document a pour but de faire le point des etudes poursuivies sur cette methode. Il constitue plutot un etat d'avancement des recherches qu'une mise au point definitive. (auteurs)

  3. Des Connaissances Aux Politiques

    International Development Research Centre (IDRC) Digital Library (Canada)

    Les synergies ont été mises en commun au fur et à mesure des progrès de la recherche. .... Recherche normative (sur le rôle et la performance des institutions .... Système national d'information sur la gestion environnementale connecté à 19 ...... Un fort contrôle centralisé sur l'élaboration des politiques nationales peut ...

  4. 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)

  5. 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

  6. Évaluation des pratiques agricoles des légumes feuilles : le cas des ...

    African Journals Online (AJOL)

    SARAH

    30 sept. 2017 ... ... de Biochimie et Immunologie Appliquée, Centre de Recherche en Sciences Biologiques, Alimentaires et .... l'intoxication des agriculteurs et des consommateurs, ... source d'alimentation en eau et au pouvoir d'achat des.

  7. Adaptation des fiches HT des Septa électrostatiques du SPS pour les Septa du PS en vue d’utiliser le câble EPR

    CERN Document Server

    Prost, A

    2009-01-01

    Suite à de nombreux problèmes de destruction de câbles PB300b d’alimentation des Septa électrostatiques de l’accélérateur PS, il a été choisi de les remplacer par un câble de type EPR. En effet ces câbles haute tension PB300b devenus trop vieux et installés en milieu radioactif ne tiennent plus la tension nominale requise pour les Septa. De plus ceux-ci ne sont plus fabriqués dans l’industrie ce qui empêche tout échange avec un câble similaire. Le câble type EPR est basé sur une technologie plus récente et est aussi plus résistant à la radiation. Il a fait ses preuves dans le passé étant utilisé pour l’alimentation des Septa électrostatiques ZS situés sans le SPS. Étant donné que le câble PB300b 300 kV n’a pas les mêmes dimensions que le câble EPR, il a été nécessaire d’adapter une fiche compatible avec ce nouveau câble et la traversée utilisée sur les Septa électrostatiques du PS. L’ancien câble PB330b est utilisé avec de l’huile comme liquide diélectri...

  8. Modelling of the flow in the interface of a composite liner at the bottom of a municipal waste landfill; Modelisation des ecoulements dans les interfaces des barrieres d'etancheite composites des installations de stockage de dechets

    Energy Technology Data Exchange (ETDEWEB)

    Cartaud, F

    2004-11-15

    Composite liner at the bottom of waste landfill is based, in France, on a geo-membrane overlapping a compacted clay liner. Defects exist in geo-membranes and leachates, provided by water percolation through the waste, then flow in the interface between the two components of the lining system. The present work consisted in analysis, quantification and modelling of the leakage process in the interface. The experimental study has been carried out on a one-meter scale device in laboratory and allowed to assess the role of normal stress on the flow rate in interface. The case where a geo-textile is present beneath the geo-membrane has been also studied. The modelling allows to take into account more accurately the geometry of the interface and ensures a better quantification of leachate flow rates than using existing methods. (author)

  9. Gestion des risques

    CERN Document Server

    Louisot, Jean-Paul

    2009-01-01

    Depuis le début du lie siècle, la gestion des risques connaît une véritable révolution culturelle. Jusqu'alors fonction technique, centrée autour de l'achat de couverture d'assurances, elle est devenue une discipline managériale et transversale : une valise d'instruments que chaque manager doit connaître et appliquer quels que soient son domaine de compétence et ses missions au sein de l'organisation. En effet, la gestion des risques est une culture qui doit être assimilée par chacun des acteurs. C'est précisément l'ambition des 101 questions rassemblées dans cet ouvrage : apporter à chaque manager d'entreprise, de collectivité, d'établissement de santé..., des réponses claires au " pourquoi " et au " comment " : Comment identifier les risques ? Comment analyser les risques ? Quels sont les objectifs de la gestion des risques ? Une carte des risques pour quoi faire ? Pourquoi faut-il financer les risques ? Les entreprises ont-elles des responsabilités pénales ? En quoi consiste la gestion...

  10. La gouvernance des risques naturels et la problematique des ...

    African Journals Online (AJOL)

    Depuis quelques années, la gouvernance des risques naturels dus aux inondations remet en cause les processus de mise en oeuvre des politiques urbaines et la qualité de la structure des aménagements dans les grandes villes du Golfe de Guinée. La perception de la gouvernance et l'application des politiques de ...

  11. 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.)

  12. A contribution to the industrial valorization of tannery waste: the case of cement industry; Contribution a la valorisation industrielle des dechets de tanneries: cas de la cimenterie

    Energy Technology Data Exchange (ETDEWEB)

    Yatribi, A.; Boukhars, L. [Service de l' Environnement, Div. de l' Urbanisme, Province de Kenitra (Morocco); Nejmeddine, A. [Laboratoire d' Ecotoxicologi, Faculte des Sciences Semlalia, Marrakech (Morocco)

    2001-04-01

    The present work addresses the possibility of valorization of tannery waste incineration ashes in the cement industry. To this end, the impact of the addition of ashes at various percentages (0, 5, 10, 15, 20, 25, 30, 35, 40 and 45 % in mass) on some mechanical and physical parameters of cement was examined: normal consistency (%), the beginning of setting (hr), the end of setting (hr), the hot expansion (mm), the resistances to compression and to bending (N/mm{sup 2}) determined on normalized 4 x 4 x 16 cm samples. The impact of the treatment environment (20 deg C and 100 % of relative humidity RH, 30 deg C and 70 % RH, 45 deg C and 45 % RH) was also taken into consideration. The obtained results reveal that the normal consistency, the beginning and the end of setting vary linearly with the quantity of added ashes. Above an addition of ashes of 30 %, the end of setting exceeds the standards demanding a maximum of 10 hours. Additionally, the results indicate that whatever the environment treatment may be, the resistances to compression and to bending increase with the increase of the sample age; they vary inversely to the amount of ash addition. The results allow to conclude that for an ash addition of 15 % and after an ageing of 30 days, the resistance to compression is higher than 40 N/mm{sup 2}, thus allowing the production of CPA 400 cement. These results also allow to conclude that samples kept in a humid environment give the best resistances to compression and to bending, by comparison with those kept in a dry environment. (authors)

  13. Methodology of environmental evaluation of wastes stabilized/solidified by hydraulic binders; Methodologie d'evaluation environnementale des dechets stabilises / solidifies par liants hydrauliques

    Energy Technology Data Exchange (ETDEWEB)

    Imyim, A.

    2000-12-15

    The aim of this work is the formalization of a methodology of evaluation of the leaching behaviour of massive porous materials obtained by stabilization/solidification of wastes. In a first part, a set of simple leaching tests is proposed which allow the physico-chemical characterization of materials. In order to better understand the phenomena involved in the release process, the methodology has been applied to hydraulic binder-based and lead-bearing synthesized materials. In a second step, a mathematical model has been proposed for the description of the leaching behaviour. The development of the model is based on the observations and experimental results obtained with the synthesized materials. Finally, the methodology of evaluation of the leaching behaviour has been applied to two cases of real wastes: the fly ashes of a Danish municipal waste incineration facility, and the galvanic sludges from an industrial waste water processing facility from Netherlands. (J.S.)

  14. The regulatory aspects linked to wastes management. The fundamental safety rules; Les aspects reglementaires lies a la gestion des dechets. Les regles fondamentales de surete

    Energy Technology Data Exchange (ETDEWEB)

    Viala, M. [CEA Fontenay-aux-Roses, 92 (France). Inst. de Protection et de Surete Nucleaire

    2001-07-01

    The radioactive waste management implies a well-established legislative frame. That is that frame that is discussed here, general principles, official authorities, wastes classification, high level radioactive waste management, regulation relative to storage, to uranium ore processing. (N.C.)

  15. Annual report 2000. Department of wastes disposal and storage; Rapport annuel d'activite 2000. Departement d'Entreposage et de Stockage des Dechets

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    This annual report presents the missions, the organization, the researches progress, the events, the publications and the personnel formation of the Department of wastes disposal and storage in the year 2000, one of the CEA fuel cycle Direction. (A.L.B.)

  16. Annual report 1999. Department of wastes disposal and storage; Rapport annuel d'activite 1999. Departement d'Entreposage et de Stockage des Dechets

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-07-01

    This annual report presents the organization, the personnel, the collaborations, the scientific researches and the publications of the Department of wastes disposal and storage of the CEA. A thematic presentation of the research and development programs is provided bringing information on the liquid effluents processing, the materials and solid wastes processing, the wastes conditioning, the characterization, the storage, the radionuclides chemistry and migration, the dismantling and the environment. (A.L.B.)

  17. Direction in charge of the management of wastes. 1998 activity report; Direction chargee de la gestion des dechets. Rapport d'activite 1998

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-07-01

    This document is the 1998 activity report of the direction in charge of the management of radioactive wastes (DGD) of the French atomic energy commission (CEA). The role of the DGD is the elimination of radioactive wastes, the management of spent fuels, the cleansing and dismantling of shut-down and decommissioned installations at the CEA. This report summarizes the highlights of the 1998 year: the cleansing plan of the CEA (current policy, plan scheme, quality assurance, financing, public relation); the radioactive wastes (general considerations, management of liquid and solid effluents, management of sealed sources, modernization of equipments and new projects, relations with the Andra, studies in progress); the spent fuels (general considerations, solutions, long-term storage); the dismantling of shut-down installations (general considerations about decommissioning, dismantling actions at the CEA, main works performed, dismantling actions in progress); the management of wastes at the CEA-direction for military applications (DAM); the cleansing of the CEA-Marcoule site; 1998 status of the management of wastes (appendix). (J.S.)

  18. Reduction at the source of household wastes: why not trying the inciting tariffing?; La reduction a la source des dechets menagers: pourquoi ne pas essayer la tarification incitative?

    Energy Technology Data Exchange (ETDEWEB)

    Glachant, M.

    2002-11-01

    This article discusses how the existing financing tools of the household wastes management implemented in France can be changed to become inciting tools for the reduction of the volume of wastes at the source. It comprises 5 parts: the first part presents the present day way of financing of the public utility of household wastes in France and discusses its (very modest) inciting effect. In the next two parts the possible modalities to make it more inciting are discussed. These parts stresses on two questions: is it better to charge the upstream producers via contributions to chartered companies or to charge the downstream households via volume- or weight-proportional fees? How much should they pay? Then some experiences of inciting tariffing are briefly reviewed: the Duales German system of upstream charging and the US and Dutch downstream charging systems. (J.S.)

  19. The problem of the long-term management of nuclear wastes; Le probleme de la gestion a long terme des dechets nucleaires

    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 proceedings of the synthesis meeting of Dunkerque. It comprises an introduction which recalls the stakes and modalities of the debate, followed by a talk from the president of the national association of local commissions for nuclear activities information (ANCLI), and three synthesis talks from the particular commission of the public debate, the ministry of industry, and the committee of experts and counter-experts. These proceedings end with some questions and answers with the public. A slide presentation by B. Dessus about the progresses made in the debate on nuclear wastes management is attached to the document. (J.S.)

  20. Direction in charge of the management of wastes. 1998 activity report; Direction chargee de la gestion des dechets. Rapport d'activite 1998

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-07-01

    This document is the 1998 activity report of the direction in charge of the management of radioactive wastes (DGD) of the French atomic energy commission (CEA). The role of the DGD is the elimination of radioactive wastes, the management of spent fuels, the cleansing and dismantling of shut-down and decommissioned installations at the CEA. This report summarizes the highlights of the 1998 year: the cleansing plan of the CEA (current policy, plan scheme, quality assurance, financing, public relation); the radioactive wastes (general considerations, management of liquid and solid effluents, management of sealed sources, modernization of equipments and new projects, relations with the Andra, studies in progress); the spent fuels (general considerations, solutions, long-term storage); the dismantling of shut-down installations (general considerations about decommissioning, dismantling actions at the CEA, main works performed, dismantling actions in progress); the management of wastes at the CEA-direction for military applications (DAM); the cleansing of the CEA-Marcoule site; 1998 status of the management of wastes (appendix). (J.S.)

  1. Theoretical study of trivalent element complexes for the nuclear waste reprocessing; Etude theorique de complexes d'elements f trivalents pour le retraitement des dechets nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Petit, L

    2007-10-15

    Current energetic and environmental concerns have made the nuclear waste reprocessing to be a major issue in numerous countries. One avenue to treat nuclear spent fuel requires separating selectively trivalent minor actinides An (Am{sup 3+}, Cm{sup 3+}) from lanthanides Ln. In this regard, nitrogen extractants are under study. Their selectivity toward actinides is still unclear, but could be the result of enhanced covalency effects with trivalent minor actinides with respect to lanthanides (III). In this thesis, we have performed DFT calculations (Density Functional Theory) to study covalency effects within the actinide-ligand bond, following three main axes of research: advanced study of the nature of the chemical bonding, spectroscopic characterization of covalency, and preliminary tests of ab initio molecular dynamics for future calculations in solvent. Methods that are not regularly applied to trivalent actinides complexes have been used: topological methods, TDDFT, LDDFT, ab initio molecular dynamics. We have managed to show that the selectivity of the BTP ligand - the most effective An/Ln extractant to date - comes at least for a part from stronger covalency effects within the An-BTP bond with respect to the Ln-BTP bond, which has never been proved before. (author)

  2. Storage of solid tritiated waste for which there is no management solution; L'entreposage des dechets solides trities sans filiere

    Energy Technology Data Exchange (ETDEWEB)

    Fromonot, C.; Rancher, J. [CEA Bruyeres-le-Chatel, Dir. des applications militaires, 91 (France); Douche, Ch.; Guetat, Ph. [CEA Valduc, Dir. des applications militaires, 21 - Is-sur-Tille (France)

    2011-02-15

    In France, radioactive waste that contains tritium, the radioactive isotope of hydrogen, is produced by the CEA as part of its research and development activities, especially for military applications. There is currently no definitive disposal solution for this waste, so it is processed and packaged and then kept in interim storage at Valduc and Marcoule. Furthermore, industrial companies and medical and pharmaceutical research laboratories use tritium - or have done so in the past - for a number of applications which have led to the production of tritiated waste, a small amount of which is still awaiting a disposal solution. Lastly, beginning in the 2020 years, the ITER power plant will also generate tritiated waste and become the largest source of its production. 6 categories of tritiated waste have been defined. Only the very lowest concentrations of tritiated waste can be dealt with by the processing and disposal solutions currently available. This means CENTRACO, where very low-level tritiated waste can be incinerated or melted, and ANDRA repositories, where the acceptance criteria are very strict, making it very uncommon for them to be used for tritiated waste. This situation is a result of the characteristics of tritium and the history of the Aube repository. The proposed solution is based on a temporary storage (50 years) of tritiated waste near the production zone that will allow a natural diminution of the radioactivity and then the packages will be moved to future storing centers of ANDRA that will be built to receive tritiated wastes

  3. Strategy for nuclear wastes incineration in hybrid reactors; Strategies pour l'incineration de dechets nucleaires dans des reacteurs hybrides

    Energy Technology Data Exchange (ETDEWEB)

    Lelievre, F

    1998-12-11

    The transmutation of nuclear wastes in accelerator-driven nuclear reactorsoffers undeniable advantages. But before going into the detailed study of a particular project, we should (i) examine the possible applications of such systems and (ii) compare the different configurations, in order to guide technological decisions. We propose an approach, answering both concerns, based on the complete description of hybrid reactors. It is possible, with only the transmutation objective and a few technological constraints chosen a posteriori, to determine precisely the essential parameters of such reactors: number of reactors, beam current, size of the core, sub-criticality... The approach also clearly pinpoints the strategic decisions, for which the scientist or engineer is not competent. This global scheme is applied to three distinct nuclear cycles: incineration of solid fuel without recycling, incineration of liquid fuel without recycling and incineration of liquid fuel with on-line recycling; and for two spectra, either thermal or fast. We show that the radiotoxicity reduction with a solid fuel is significant only with a fast spectrum, but the incineration times range from 20 to 30 years. The liquid fuel is appropriate only with on-line recycling, at equilibrium. The gain on the radiotoxicity can be considerable and we describe a number of such systems. The potential of ADS for the transmutation of nuclear wastes is confirmed, but we should continue the description of specific systems obtained through this approach. (author)

  4. The storage center of short life low and intermediate level radioactive wastes; Le centre de stockage des dechets de faible et moyenne activite a vie courte

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    Situated at 50 km of Troyes, the Aube Center was opened in 1992 in order to take over from the Manche Center, for the surface storage of low life low and intermediate level radioactive wastes. It offers an answer to manage safely theses wastes at an industrial scale during 50 years. (A.L.B.)

  5. Municipal wastes prevention and recycling: some approaches in european towns; Prevention et recyclage des dechets municipaux: un eventail d'approches dans 18 villes europeennes

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-07-01

    In 1975, the Community Institutions began to introduce policies and measures to improve waste management. For example, the Member States were required to draft waste management plans and to introduce policies for prevention, recovery and recycling, with incineration and landfills considered less desirable solutions. Cities, where population density and therefore production of waste are higher, play an essential role in the management of municipal waste. For this reason, two networks of European cities, the ACR-AVR (Association of Cities for Recycling) and Energie-Cites along with Agrital Ricerche, an Italian research and study centre, jointly presented a proposal to the European Commission (DG Environment) for a project intended to increase awareness on the part of local authorities and the media in four EU Member States (Spain, Italy, Ireland and the UK) concerning the need to elaborate local waste management strategies. This project is based on the experience of the REMECOM network (European Network of Measures for Classification of Household Waste) as an example of exchanges between cities regarding methods of analysis and measurement of the volume of household waste at local level. As a result of this proposal they have produced Media-com, a method for raising awareness of waste management based on descriptions of good practices in 18 cities in eleven countries of the EU. All these practices are described in an attractive, non-technical style and are supported by statistics and simple technical information, as well as illustrations. This document, which could also be termed a collection of good practices, constitutes a source of information and ideas for local authorities and the media. (A.L.B.)

  6. Thermo-chemistry of nuclear waste glasses: a new approach; Thermochimie des verres de stockage de dechets nucleaires: une nouvelle approche

    Energy Technology Data Exchange (ETDEWEB)

    Linard, Y.; Neuville, D.R.; Richet, P. [Institut de Physique du Globe, Lab. de Physique des Geomateriaux, URA CNRS 734, 75 - Paris (France)

    1997-07-01

    Understanding of the stability and weathering of glasses used for storing fission products is hampered by a general lack of basic thermochemical information. Models have been setup to predict Gibbs free energies of dissolution of glasses, but ascertaining their accuracy is made difficult by the very lack of reliable experimental data with which model results should be compared. As enthalpies of formation can in principle be determined from usual solution calorimetry experiments, the lack of Gibbs-free energy data for glasses mainly stems from the fact that, as disordered substances, glasses do not obey the third principle and have indeed large configurational entropies. These entropies can be determined from thermochemical measurements only when there exist a congruently melting crystalline compound with the same composition. Using available data, we have calculated the Gibbs-free energies of formation of a series of silicate glasses for which such a calorimetric determination is possible. With these results, we assess the predictions of Paul's model (1977) for calculating Gibbs-free energies of dissolution. As the complex compositions of the borosilicate glasses used for nuclear waste storage prevent determining configurational entropies by calorimetric methods, we point out how these can be determined instead from viscosity measurements. We finally discuss the implications of this approach for modeling of water-glass interactions. (authors)

  7. The very-low activity waste storage facility. A new waste management system; Le centre de stockage des dechets de tres faible activite. Une nouvelle filiere de gestion

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    Very-low activity wastes have a radioactivity level close to the natural one. This category of waste is taken into consideration by the French legislation and their storage is one of their point of achievement. This document gives a complete overview of the principles of storage implemented at the storage center for very-low activity wastes (CSTFA) sited in the Aube departement in the vicinity of the storage center for low- and intermediate activity wastes: storage concept, wastes confinement, center organization, environmental monitoring. (J.S.)

  8. Assessment of the feasibility of indefinite containment of canadian nuclear fuel wastes; Evaluation de la faisabilite du confinement illimite des dechets de combustible nucleaire canadiens

    Energy Technology Data Exchange (ETDEWEB)

    Shoesmith, D.W.; King, F.; Ikeda, B.M.

    1995-05-01

    This report presents an analysis of the expected corrosion behavior of nuclear fuel waste containers in a conceptual Canadian disposal vault. The container materials considered are dilute Ti alloys (Grades-2, -12 and -16) and oxygen-free copper.

  9. Annual report 1999. Department of wastes disposal and storage; Rapport annuel d'activite 1999. Departement d'Entreposage et de Stockage des Dechets

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-07-01

    This annual report presents the organization, the personnel, the collaborations, the scientific researches and the publications of the Department of wastes disposal and storage of the CEA. A thematic presentation of the research and development programs is provided bringing information on the liquid effluents processing, the materials and solid wastes processing, the wastes conditioning, the characterization, the storage, the radionuclides chemistry and migration, the dismantling and the environment. (A.L.B.)

  10. Photonique des Morphos

    CERN Document Server

    Berthier, Serge

    2010-01-01

    La photonique est déjà présente dans notre vie quotidienne, et on attend maintenant que la manipulation des photons permette aussi le traitement logique des informations. Cependant, l’élément de base qui permet cette manipulation de la lumière, le cristal photonique, est d’une réalisation complexe et mal contrôlée. Dans la course à la maîtrise de la lumière, les structures photoniques naturelles ont beaucoup à nous apprendre. C’est ce que nous montre Serge Berthier qui étudie dans ce livre la structure des écailles des Morphos. Tenant compte de l’essor récent des approches biomimétiques, il présente de manière détaillée plus de dix-huit techniques expérimentales utilisées pour ses analyses, ainsi que les diverses approches théoriques développées pour la modélisation de structures multi-échelles complexes. Première étude quasi-exhaustive des structures fines d’un genre et des propriétés optiques ainsi que colorimétriques générées, ce livre fournit aux entomologiste...

  11. Droit des organisations internationales

    CERN Document Server

    Sorel, Jean-Marc; Ndior, Valère

    2013-01-01

    Cet ouvrage collectif offre aux enseignants et chercheurs en droit international, aux praticiens et aux étudiants, une analyse actualisée du droit des organisations internationales. Il dresse en cinq parties un tableau, illustré par des exemples variés, des problématiques que soulève le phénomène polymorphe d institutionnalisation de la société internationale. La première partie est consacrée au phénomène des « organisations internationales », sous l angle à la fois de l institutionnalisation progressive des relations internationales et de la difficulté à cerner une catégorie unifiée. La deuxième partie rend compte de la création, de la disparition et des mutations des organisations internationales, ici envisagées comme systèmes institutionnels et ordres juridiques dérivés. La troisième partie analyse l autonomie que l acquisition de la personnalité juridique et de privilèges et immunités, un organe administratif intégré, un personnel ou un budget propres confèrent aux organi...

  12. Adsorption and Biocirculation in Oceanic Waters; Adsorption et Biocirculation dans les Eaux des Oceans

    Energy Technology Data Exchange (ETDEWEB)

    Zenkevich, L. A.

    1960-07-01

    la contamination des oceans par des produits radioactifs. De toute evidence, les hommes de science se preoccupent de plus en plus du role des organismes vivants sur le transport et la diffusion des substances radioactives dans toutes les niasses d'eau. MM. Ketchum et Bowen etudient ce qu'ils appellent le 'transport biologique' et s'efforcent, dans des travaux d'un grand interet, de donner une expression numerique a ce transport et de le comparer au 'transport physique'. Une notion nouvelle est apparue, celle de 'biocirculation'. On ne saurait, de toute evidence, negliger l'importance de ce facteur, tant du point de vue du transport que de celui de 1-adsorption. La masse des substances minerales en suspension dans l'eau (substances ne contenant aucun organisme vivant), qui sont caracterisees par une mobilite relativement faible, ainsi que les bacteries, le phytoplancton et le zooplancton creent une enorme surface d'adsorption (tableaux 1 et 2): Les masses d'eau oceaniques contiennent en effet une grande quantite de ces elements inertes et organismes planctoniques, animaux et vegetaux. La determination quantitative de tous les elements en suspension permet d'apprecier le role qu'ils jouent en tant que surface d'adsorption et moyen de biocirculation (dans le sens vertical et dans le sens horizontal). Les tableaux ci-apres indiquent la surface d'adsorption des differents groupes planctoniques dans les zones de diffusion de densite moyenne et la biocirculation au sein d'une colonne de 1 m{sup 2} dans ces zones.

  13. Santé des adolescents et des jeunes au Burkina Faso : état des ...

    African Journals Online (AJOL)

    Il s'est agi d'une étude évaluative ayant utilisé une revue documentaire associée à une interview des acteurs clés et un atelier de validation et d'identification des interventions pertinentes pour un plan stratégique national. La situation de la santé des adolescents et des jeunes est caractérisée par des grossesses précoces ...

  14. Dental Encounter System (DES)

    Data.gov (United States)

    Department of Veterans Affairs — Dental Encounter System (DES) is an automated health care application designed to capture critical data about the operations of VA Dental Services. Information on...

  15. Diethylstilbestrol (DES) and Cancer

    Science.gov (United States)

    ... DES-exposed grandchildren have? Researchers are also studying possible health effects among women and men who are the children ... for unexposed men. In addition, researchers are studying possible health effects on the grandchildren of mothers who were exposed ...

  16. Table des illustrations

    OpenAIRE

    2016-01-01

    Tableaux Dates d’inauguration des grands hôtels japonais entre 1860 et 1945… 19 Histoire, tourisme et hôtellerie en Corée depuis les années 1870… 59-60 Dates d’inauguration des grands hôtels chinois depuis 1863… 84 Les hôtels de luxe et leurs capacités d’hébergement en Corée en 2000… 103 Les flux de personnes suscités par les hôtels « super luxe » de Séoul en 2000… 105 L’activité des grands hôtels à Séoul en 1999 (en wons)… 106 Propriété et gestion des grands hôtels à Séoul en 1999…. 110 La c...

  17. Direction des Publications

    African Journals Online (AJOL)

    Synthese

    potential and surface properties of their mixtures were investigated, in an ... suppose that the electrostatic repulsive interactions between the two anion ... concentration, et de la conformation des ..... proteins and polysaccharides in solutions,.

  18. New results concerning the behaviour of fission gases in in-pile UO{sub 2} at high temperatures; Resultats nouveaux sur le comportement des gaz de fission a haute temperature dans l'UO{sub 2} en pile

    Energy Technology Data Exchange (ETDEWEB)

    Soulhier, R; Schurenkamper, A [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1964-07-01

    The authors consider in the first part the various phenomena giving rise to the production of fission gases towards the exterior of nuclear fuels. The following aspects are dealt with: diffusion, for which is considered the influence of the predecessors of the radioactive gases, the fission recoil, atom expulsion along the fission paths and the evaporation. In the second part the authors present the results obtained on UO{sub 2} samples subjected to irradiation at temperatures of between 150 and 2000 deg C: - At low temperatures the variation of the amount produced as a function of the half-life of the isotopes studied shows that recoil is hot the only cause of gas production. - Above 1800 deg C, a weight loss by evaporation has been observed and the influence of this phenomenon on gas liberation has been studied; thus the fraction of {sup 135}Xe liberated at 2000 deg C by processes other than evaporation is of the order of 10 per cent. - The influence of the various mechanism on the overall effect as a function of temperature is discussed. (authors) [French] Dans une premiere partie, les auteurs etudient les differents phenomenes pouvant donner lieu au degagement des gaz de fission hors d'un combustible. Sont traites successivement: la diffusion, pour laquelle on discute l'influence des predecesseurs des gaz radioactifs, le recul de fission, l'expulsion des atomes le long des trajets de fission et l'evaporation. Dans une deuxieme partie ils exposent les resultats obtenus sur des echantillons d'UO{sub 2} portes sous irradiation a des temperatures comprises entre 150 deg C et 2000 deg C: - A basse temperature la variation de la quantite degagee suivant la periode des isotopes etudies montre que le recul n'est pas la seule cause du degagement des gaz. - Au-dessus de 1800 deg C on a note une perte de poids par evaporation et on a evalue l'influence de ce phenomene sur la liberation des gaz: ainsi la fraction du {sup 135}Xe liberee a 2000 deg C par d'autres processus

  19. Treatment of effluent at the Saclay Centre d'Etudes Nucleaires (1960); Le traitement des effluents du Centre d'Etudes Nucleaires de Saclay (1960)

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

    The Centre d'Etudes Nucleaires at Saclay possesses several installations from which liquid radioactive effluent is rejected, and it has thus been found necessary to construct a station for the purification of radioactive liquids and to settle various chemical, analytical and technological problems. This report describes, in the following order: - the disposal possibilities at the Centre d'Etudes Nucleaires, Saclay, - the effluents produced at the centre, - the set-up for collecting effluent, - treatment of the effluent, - results of these treatments. (author) [French] La presence, au Centre d'Etudes Nucleaires de Saclay, de plusieurs installations susceptibles de rejeter des effluents liquides radioactifs a necessite la construction d'une station d'epuration d'eaux radioactives et la mise au point de differents problemes chimiques, analytiques et technologiques. Dans ce rapport, nous exposerons successivement: - les possibilites de rejet du Centre d'Etudes Nucleaires de Saclay, - les effluents du centre, - le dispositif de collecte des effluents, - le traitement de ces effluents, - les resultats de ces traitements. (auteur)

  20. 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)

  1. La revolution des savants

    CERN Document Server

    Chavanne, A

    1989-01-01

    Premiere cassette : - 1666 : impact de la creation de l'Academie des Sciences par Colbert, trente ans apres le proces de Galile, et au moment des disparitions de Pascal, Descartes et Fermat. Elle dirigee par le hollandais Huyggens jusqu'a sa fuite de France au moment de la revocation de l'Edit de Nantes. - 1750 : l'Encyclopedie (ou "Dictionnaire raisonne des Sciences, des Arts et des Metiers") de Diderot et d'Alembert, soutenus par Malherbes, Buffon, Condorcet et Rousseau. - 1789 : Revolution francaise. - 8 aout 1793 : l'Assemblee, par une declaration de Marat, dissout l'Academie des Sciences. Celle-ci continue cependant ses travaux pour les poids et mesures jusqu'en 1795. - la Terreur : la condamnation a mort, pas au nom d'une "Revolution qui n'a pas besoin de savants" mais pour d'autres raisons, de trois grands hommes de science : Lavoisier, Bailly et Condorcet. - 1793-1794 : Au printemps 93, le Comite de Salut Publique s'inquiete du demi-million de soldats etrangers de toutes les pays frontaliers qui essai...

  2. Creation, synthesis and characterisation of nitrogenous poly-heterocyclic new molecules for specific complexation of metallic cations; Conception, synthese et caracterisation de molecules polyheterocycliques azotees pour la complexation specifique de cations metalliques

    Energy Technology Data Exchange (ETDEWEB)

    Dupont, C.

    2010-12-10

    In France, the nuclear waste issued from the industrial reprocessing of spent nuclear fuels (by the PUREX process) are currently vitrified at the La Hague plant, waiting for a final disposal in a deep geological repository. The law voted in June 2006 on the management of highly active nuclear waste plans to look for solutions enabling the separation and transmutation of long-lived radionuclides so as to reduce the quantity and noxiousness of the final nuclear waste. To address this issue, the CEA investigates and elaborates advanced separation processes based on specially designed complexing or extracting molecules to selectively extract minor actinides from PUREX raffinates containing fission products like lanthanides, which are neutron scavengers. BTP or bis-triazinyl-pyridines have been extensively studied at the CEA (and in Europe) for actinides(III)/lanthanides(III) separation. They complex actinides(III) selectively. However, they are sensitive to degradation by hydrolysis and radiolysis. Besides, their separation mechanisms are not well understood, especially the influence of their substituting groups on their complexing and extracting properties. The first part of work reports the syntheses of various BTP and BTBP molecules, differently substituted, as well as a new family of poly-aromatic nitrogen-contained ligands: BPBT, presenting a pyridine/triazine sequence that has never been reported in the literature. The second part is devoted to the physico-chemistry studies of the synthesized molecules, such as the determination of their protonation and complexation constants to describe the influence of different substituting groups. Finally, the last part outlines solvent extraction studies by using these ligands either like extractants or like complexants. (author) [French] Resume: La loi du 6 juin 2006 sur la gestion des dechets radioactifs de haute activite et a vie longue prevoit la recherche de solutions permettant la separation et la transmutation des

  3. Contribution des radios communautaires a l'education des ...

    African Journals Online (AJOL)

    Contribution des radios communautaires a l'education des populations rurales pour un developpement durable au Benin: etude de cas. ... Journal de la Recherche Scientifique de l'Université de Lomé. Journal Home · ABOUT THIS JOURNAL ...

  4. La convergence des rôles respectifs des relationnistes et des journalistes influence-t-elle la perception qu'ils ont les uns des autres?

    DEFF Research Database (Denmark)

    Valentini, Chiara

    2017-01-01

    la convergence des rôles respectifs des praticiens des relations publiques et des journalistes a un effet favorable sur la perception qu’ils ont les uns des autres. L’effet est plus marqué chez les praticiens des relations publiques, car leur vision de la profession en journalisme correspond à celle...

  5. Promouvoir l'entrepreneuriat inclusif des jeunes et des femmes ...

    International Development Research Centre (IDRC) Digital Library (Canada)

    Le projet vise à analyser la contribution réelle et potentielle de l'entrepreneuriat inclusif au bien-être des jeunes et des femmes en Côte d'Ivoire, au Burkina Faso et au Kenya. Après un état des lieux de la pratique de l'entrepreneuriat inclusif dans chacun des pays ciblés, l'équipe de recherche étudiera son incidence sur ...

  6. La fabrique des sciences des institutions aux pratiques

    CERN Document Server

    Benninghoff, Martin; Crettaz von Roten, Fabienne; Merz, Martina

    2006-01-01

    Aujourd'hui, les façons de produire, d'organiser, d'évaluer et d'utiliser les savoirs sont en profond débat. De plus en plus, l'Etat, la société civile et l'économie tentent d'influencer les activités des universités et des laboratoires de recherche. Ces développements mettent à l'épreuve tout à la fois les fondements des systèmes d'enseignement supérieur et de recherche, l'autonomie des institutions scientifiques, la définition des frontières des savoirs et l'acceptation des sciences. Dans des contextes suisses et européens, cet ouvrage s'intéresse aux manières dont les sciences et les technologies sont fabriquées, en analysant leurs institutions et les pratiques. A partir d'une approche relationnelle, les sciences et les technologies sont conçues comme des phénomènes profondément sociaux, culturels et politiques. Une telle démarche déstabilise les visions parfois idéalisées et stéréotypées de la construction des savoirs. Des études de cas détaillées décrivent des phénomè...

  7. Effets des extraits vegetaux sur la dynamique de populations des ...

    African Journals Online (AJOL)

    La présente étude se propose de trouver une alternative de l'utilisation des pesticides chimiques en testant l'effet insecticide des extraits aqueux des feuilles de Hyptis suaveolens, graines de Ricinus communis et de Azadirachta indica contre les ravageurs du niébé en conditions de champ en utilisant le cyperméthrine ...

  8. Charte du Conseil des Gouverneurs

    International Development Research Centre (IDRC) Digital Library (Canada)

    Office 2004 Test Drive User

    7. favoriser des communications ouvertes et franches entre le personnel, la direction ..... de dresser le procès-verbal des réunions du Conseil et de ses comités et de veiller à ce ... et des résultats qu'il obtient, et non de sa gestion quotidienne.

  9. Le statut vitaminique des individus et des populations…

    Directory of Open Access Journals (Sweden)

    Icart Jean-Claude

    2000-05-01

    Full Text Available Comme le souligne un récent rapport du Haut comité de santé publique, le statut vitaminique des individus et des populations demeure une question d’actualité. Si les études ne révèlent plus de signes évocateurs de carence, au plus des problèmes de déficiences pour certains groupes à risque, des interrogations, demeurent malgré le contexte d’abondance, concernant la couverture des besoins, laquelle pourrait s’avérer inférieure aux valeurs considérées comme satisfaisantes.

  10. Les lueurs des sables

    CERN Multimedia

    Les lueurs des sables

    2013-01-01

    Two CERN ladies are getting ready for the “Trophée Roses des Sables” rally adventure: Julie and Laetitia are finalizing the last details before setting off on Monday 7th October 2013. Julie from EN-MEF group and Laetitia from DGS-SEE group, met at the CERN Rugby club. This year, they are participating in the 100 % female rally which will take place in Morocco from 10 to 20 October. They will be carrying along 100 kg of humanitarian donation for children such as some clothes, books and medical material. Do not hesitate to show your support at their farewell party to be held on Monday 7 October, from 4 to 6 pm in front of the St Genis-Pouilly Mairie (city Hall). Follow their exciting adventure on the blog leslueursdessables.trophee-roses-des-sables.org and on their association’s Facebook page Les Lueurs des Sables.

  11. Liste des auteurs

    OpenAIRE

    2016-01-01

    Madeleine Akrich      Ecole des Mines – Centre de Sociologie de l’innovation – Paris Noël Barbe      Association comtoise des Arts et Traditions populaires – Besançon Lucien Bernot      Ecole des hautes études en sciences sociales (EHESS) – Paris Anni Borzeix      Centre national de la recherche scientifique (CNRS) –     Groupement d’intérêt public (GIP) « Mutations industrielles » – Paris François Boudarias      Laboratoire d’Anthropologie et de sociologie de Tours (LAST) Dominique Boullier ...

  12. Évaluation des pratiques agricoles des légumes feuilles : le cas des ...

    African Journals Online (AJOL)

    Face à ce constat, le défi de la recherche serait la détermination du niveau actuel de contamination des légumes feuilles et des eaux du barrage et celui de l'État serait l'initiation de programmes de sensibilisation des producteurs par rapport à une gestion plus rigoureuse des pesticides. Mots-clés : pratiques paysannes, ...

  13. Application des TIC à l'atténuation des effets des catastrophes dans ...

    International Development Research Centre (IDRC) Digital Library (Canada)

    L'Amérique centrale est souvent aux prises avec des inondations et des ... (SIG) et de traitement des images, afin de cartographier les dangers et de modéliser les ... de l'Institut d'étude du développement international de l'Université McGill.

  14. REPRISE DES COURS - Yoga

    CERN Multimedia

    Club de Yoga

    2015-01-01

    REPRISE DES COURS – Venez nombreux ! Yoga, Sophrologie, Tai Chi La liste des cours pour le semestre allant du 1er septembre 2015 au 31 janvier 2016 est disponible sur notre site web : http://club-yoga.web.cern.ch Lieu Les cours ont lieu dans la salle des clubs, à l’entresol du restaurant No 2, Bât. 504 (dans la salle no 3 pour la Sophrologie). Prix des cours Le prix pour le semestre (environ 18 leçons) est fixé à 220 CHF plus 10 CHF d’adhésion annuelle au Club. Couple : 200 CHF par personne. 2 cours par semaine : 400 CHF. Inscriptions Les inscriptions aux cours seront prises directement auprès du professeur, lors de la 1ère séance. Avant de s’inscrire pour le semestre, il est possible d’essayer une séance gratuitement. Informations : http://club-yoga.web.cern.ch ----------------------------------------- cern.ch/club-yoga/

  15. Praxis des Klebens

    CERN Document Server

    Theuerkauff, Petra

    1989-01-01

    Bei diesem Buch handelt es sich um einen Leitfaden fur Klebepraktiker. Es werden die verschiedenen Einzelschritte beim kleben beschrieben, als auch die vorbereitenden Massnahmen und anschliessenden Prufverfahren auf Festigkeit behandelt. Das Buch sollte an keinem Arbeitsplatz fehlen, wo man sich mit Problemen der Fugetechnik des Klebens beschaftigt.

  16. Dimensions des stabulations 2018

    OpenAIRE

    Früh, Barbara; Maurer, Veronika; Schneider, Claudia; Schürmann, Stefan; Spengler Neff, Anet; Werne, Steffen

    2018-01-01

    Les «Dimensions des stabulations» contiennent toutes les dimensions pour les stabulations et les parcours pour la production animale en agriculture biologique. Cette liste sert d’instrument de planification pour les éleveurs, d’outil de travail pour la vulgarisation et d’ouvrage de référence pour le contrôle bio.

  17. Direction des Publications

    African Journals Online (AJOL)

    Synthese

    économique des services rendus par les écosystèmes marins. La richesse ... croissance plus rapide que la moyenne de l‟économie ...... services and natural capital. Nature. 387, 253-260. .... d‟interactions où l‟humain est partie prenante. In.

  18. La physique des infinis

    CERN Document Server

    Bernardeau, Francis; Laplace, Sandrine; Spiro, Michel

    2013-01-01

    Écrire l'histoire de l'Univers, tel est l'objectif commun des physiciens des particules et des astrophysiciens. Pour y parvenir, deux approches s'épaulent : la voie de l'infiniment petit, que l'on emprunte via de gigantesques accélérateurs de particules, et celle de l'infiniment grand, dont le laboratoire est l'Univers. Un Univers qui est bien loin d'avoir livré tous ses secrets. On connaît à peine 4,8 % de la matière qui le constitue, le reste étant composé de matière noire (25,8 %) et d'énergie noire (69,4 %), toutes deux de nature inconnue. Et si la récente découverte du boson de Higgs valide le Modèle standard de la physique des particules, celui-ci est toujours incomplet et doit être étendu à ou dépassé. Est-on arrivé au bout du jeu de poupées russes de la matière ? Quelles sont les particules manquantes ? Faut-il revoir les lois fondamentales ? Quels instruments faut-il mettre en œuvre pour accéder à cette « nouvelle physique » ? Comment parler de Super Big Science aux citoye...

  19. 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)

  20. 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)

  1. The Radioisotopic Determination of Diffusion Coefficients and Currents in Natural Waters. Surface Collection of Radioactive Fall-Out on a Large Alpine Lake; Determination par detection nucleaire des coefficients de diffusion et des courants dans les eaux naturelles. Evolution de la surface de collection d'un grand lac alpin pour les retombees radioactives; Opredelenie koehffitsienta diffuzii i skorosti techeniya estestvennykh vod pri pomoshchi yadernogo detektirovaniya. Ehvolyutsiya poverkhnosti sbora radioaktivnykh osadkov na bol'shom al'pijskom ozere; Determinacion por deteccion nuclear de los coeficientes de difusion y de las corrientes en las aguas naturales evolucion de la superficie de captacion de un gran lago alpino para las precipitaciones radiactivas

    Energy Technology Data Exchange (ETDEWEB)

    Chesselet, R.; Nordemann, D. [Service d' Electronique Physique, Centre d' Etudes Nucleaires de Saclay (France); Dussart, B. [Centre de Recherches Hydrobiologiques, CNRS, Gif-sur-Yvette (France)

    1963-08-15

    In an initial stage, the authors brought about the in situ diffusion of a radioactive emitter (sodium-22, in the form of Na{sup +}) with very low activity, i.e. less than 1 mc. The diffusion laws applied in this case made it easy to predict the rate of diffusing of the {sup r}adioactive cloud{sup .} In this way, plotting the activities, as measured by two suitably placed gamma detectors, against time permits the estimation of a diffusion coefficient for the emitter used and, if appropriate, the measurement of current velocity at the point of measurement (in the case described, the Lake of Geneva). Subsequently, and in conjunction with a geophysical study on the general problem of radioactive fall-out, the authors worked on the increases in radioactive fall-out caused by nuclear tests in the atmosphere (October 1961 - January 1962). Measurements of radioactivity were made every day on samples of Lake Geneva water taken at depths of 0 m, 10 m and 20 m and also on a collector of dry and moist atmospheric fall-out. Despite the complex pattern, over a period, of theincreasesinfall-out , the interpretation of the diagrams obtained can help to explain what happens to radioactive products in the diffusion and current conditions encountered. The use of the diffusion of radioactive products in very small quantities and of the various highly sensitive techniques of nuclear detection now available can lead to a better understanding of in situ diffusion and of the movement of natural water masses. (author) [French] Dans un premiere etape, les auteurs ont provoque la diffusion in situ d'un emetteur radioactif, le sodium 22, sous forme de Na{sup +}, avec des activites tres faibles, inferieures au millicurie. Les lois de la diffusion appliquee a ce cas permettent aisement de prevoir l'allure du 'n'uage radioactif'' en cours de diffusion. Ainsi, l'enregistrement en fonction du temps des activites mesurees par deux detecteurs gamma convenablemen t disposes conduit a l'evaluation d

  2. Injectabilite des coulis de ciment dans des milieux fissures

    Science.gov (United States)

    Mnif, Thameur

    Le travail presente ici est un bilan du travaux de recherche effectues sur l'injectabilite des coulis de ciment dans lu milieux fissures. Un certain nombre de coulis a base de ciment Portland et microfin ont ete selectionnes afin de caracteriser leur capacite a penetrer des milieux fissures. Une partie des essais a ete menee en laboratoire. L'etude rheologique des differents melanges a permis de tester l'influence de l'ajout de superplastifiant et/ou de fumee de silice sur la distribution granulometrique des coulis et par consequent sur leur capacite a injecter des colonnes de sable simulant un milieu fissure donne. La classe granulometrique d'un coulis, sa stabilite et sa fluidite sont apparus comme les trois facteurs principaux pour la reussite d'une injection. Un facteur de finesse a ete defini au cours de cette etude: base sur la classe granulometrique du ciment et sa stabilite, il peut entrer dans la formulation theorique du debit d'injection avant application sur chantier. La deuxieme et derniere partie de l'etude presente les resultats de deux projets de recherche sur l'injection realises sur chantier. L'injection de dalles de beton fissurees a permis le suivi de l'evolution des pressions avec la distance au point d'injection. L'injection de murs de maconnerie a caractere historique a montre l'importance de la definition de criteres de performance des coulis a utiliser pour traiter un milieu donne et pour un objectif donne. Plusieurs melanges peuvent ainsi etre predefinis et mis a disposition sur le chantier. La complementarite des ciments traditionnels et des ciments microfins devient alors un atout important. Le choix d'utilisation de ces melanges est fonction du terrain rencontre. En conclusion, cette recherche etablit une methodologie pour la selection des coulis a base de ciment et des pressions d'injection en fonction de l'ouverture des fissures ou joints de construction.

  3. 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.)

  4. 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.)

  5. The Valorga anaerobic digestion process for wastes and its application in an integrated management: the example of waste processing in the Calais region; Le procede Valorga de digestion anaerobie des dechets et son application dans une gestion integree: l'exemple du traitement des dechets du Calaisis

    Energy Technology Data Exchange (ETDEWEB)

    Hyllaire, B. [Valorga International SAS, 34 - Montpellier (France)

    2004-03-01

    The choice for a bio-methanation process for the treatment of the biological wastes of Calais city (Northern France) is the result of a global waste management policy implemented since 1995. The combination of selective waste collection with an original sorting strategy, which consists in directing the waste paper flux towards the fermentescible fraction, has permitted to confirm the relevance of the choice for the methanation way. The stake of this bio-methanation unit is the processing of 27000 t/year of bio-wastes produced in optimal ecological conditions, the production of a quality compost and the efficient valorization of the biogas. This facility will be the very first 'high environmental quality' bio-methanation plant in France. (J.S.)

  6. Regulation imposed to nuclear facility operators for the elaboration of 'waste studies' and 'waste statuses'; Reglementation imposee aux exploitants d'installations nucleaires pour l'elaboration ''des etudes dechets'' et ''des bilans dechets''

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-09-04

    This decision from the French authority of nuclear safety (ASN) aims at validating the new versions of the guidebook for the elaboration of 'waste studies' for nuclear facilities and of the specifications for the elaboration of 'waste statuses' for nuclear facilities. This paper includes two documents. The first one is a guidebook devoted to nuclear facility operators which fixes the rules of production of waste studies according to the articles 20 to 26 of the inter-ministry by-law from December 31, 1999 (waste zoning conditions and ASN's control modalities). The second document concerns the specifications for the establishment of annual waste statuses according to article 27 of the inter-ministry by-law from December 31, 1999 (rational management of nuclear wastes). (J.S.)

  7. 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.

  8. 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)

  9. Screening phytochimique et identification spectroscopique des ...

    African Journals Online (AJOL)

    Origin

    plante, effectuée pour la première fois, a révélé la présence des alcaloïdes, des flavonoïdes, des tanins catéchiques, des terpènes, des coumarines et des composés cyanogénétiques. Quant aux saponines et les quinones libres, ils sont présents chez les fleurs et absents chez les feuilles. La caractérisation des molécules.

  10. Efficacité des néonicotinoïdes et des pyréthrinoïdes utilisés contre le ...

    African Journals Online (AJOL)

    Efficacité des néonicotinoïdes et des pyréthrinoïdes utilisés contre le foreur des tiges du cacaoyer ( Eulophonotus myrmeleon Felder : Lepidoptera, Cossidae). Implications dans la stratégie de protection de la cacaoculture en Côte d'Ivoire.

  11. Determination of the exchange capacity of soils using radio-strontium; Determination de la capacite d'echange des sols au moyen du radio-strontium

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

    In order to improve the technique and in particular to reduce the time required for measuring the exchange capacity of soils, the authors have developed a rapid measurement method based on the use of radio-active tracers. The element chosen for showing the occurrence of exchangeable bases is radio-strontium; it can displace the ions Ca{sup ++}, Mg{sup ++}, Na{sup ++}, K{sup +} from the soil. The use of a de-sorbent, barium chloride, makes it possible to recover the strontium fixed. A comparison of the results obtained using the two methods appears to be very satisfactory. The conventional method requires from 1 1/2 to 2 days - the radio-strontium method requires only 3 hours with the possibility also of carrying out large series of measurements. (authors) [French] Pour ameliorer la technique et surtout reduire le temps de manipulation que necessite la mesure de la capacite d'echange des sols, les auteurs ont mis au point une methode de mesure rapide qui fait appel aux traceurs radioactifs. C'est le radio-strontium qui a ete choisi pour la mise en evidence des bases echangeables. Il permet de deplacer les ions Ca{sup ++}, Mg{sup ++}, Na{sup ++}, K{sup +} du sol. Un desorbant, le chlorure de baryum, permet de recuperer la quantite du strontium fixe. La comparaison des resultats obtenus par les deux methodes semble tres satisfaisante. La methode classique necessite 1 jour et demi a 2 jours - la methode radiostrontium exige seulement 3 heures avec la possibilite de grandes series. (auteurs)

  12. Nuclear wastes; Dechets nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    Here is made a general survey of the situation relative to radioactive wastes. The different kinds of radioactive wastes and the different way to store them are detailed. A comparative evaluation of the situation in France and in the world is made. The case of transport of radioactive wastes is tackled. (N.C.)

  13. Localizing by autoradiography at -195 deg radioactive areas in rats exposed to a high flux of thermal neutrons, importance of phosphorus 32 in consecutive internal irradiation; Localisation par autoradiographie a -195 deg des zones radioactives chez le rat expose a un haut flux de neutrons thermiques, importance du phosphore 32 dans l'irradiation interne consecutive

    Energy Technology Data Exchange (ETDEWEB)

    Chanteur, J; Pellerin, P [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1961-07-01

    Rats weighing 25 g were exposed for 5 mn to a flux of 6.10{sup 12} thermal neutrons/cm{sup 2}/s. Anatomical autoradiography at -195 deg. C has enabled the radioactive organs to be easily localised, to follow in course of time the decrease of radioactivity, and from it to deduce the probable nature of the numerous emitters in question. In particular, the phosphorus 32 has thus appeared to be one of those responsible for internal irradiation, general, on the one hand, by activating cellular phosphorus, local, on the other, by activating bony phosphates. Owing to this, an accidental irradiation by neutrons might have consequences that are both somatic (elective irradiation of the bone marrow) and genetic (activation of nucleic acids). The gamma spectrometry has confirmed the nature of certain other emitters. (author) [French] Des rats de 25 g ont ete exposes pendant 5 mn a un flux de 6.10{sup 12} neutrons thermiques/cm{sup 2}/s. L'autoradiographie anatomique a -195 deg. C a permis de localiser facilement les organes radioactifs, de suivre dans le temps la decroissance de la radioactivite, et d'en deduire la nature probable des nombreux emetteurs en cause. En particulier, le phosphore 32 est ainsi apparu comme l'un des responsables de l'irradiation interne, d'une part generale par activation du phosphore cellulaire, d'autre part locale par activation des phosphates osseux. Une irradiations accidentelle par neutrons aurait, de ce fait, des consequences a la fois somatiques (irradiation elective de la moelle osseuse) et genetiques (activation des acides nucleiques). La spectrometrie gamma a confirme la nature de certains autres emetteurs. (auteur)

  14. 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

  15. 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

  16. La gestion des résultats des entreprises innovantes

    OpenAIRE

    Dumas, Guillaume

    2014-01-01

    Cette thèse s’intéresse à la gestion des résultats dans le cadre des entreprises innovantes. Elle est constituée de trois articles. Dans le premier, il s’agit d’examiner si les résultats des entreprises innovantes sont gérés et si le stade de développement des innovations influence cette gestion des résultats. Il apparaît que les résultats des entreprises innovantes sont gérés à la hausse. Cette gestion ne semble intervenir qu’au cours de l’activité d’innovation (c’est-à-dire lorsque les entr...

  17. Sulphate solubility and sulphate diffusion in oxide glasses: implications for the containment of sulphate-bearing nuclear wastes; Solubilite et cinetiques de diffusion des sulfates dans differents verres d'oxydes: application au conditionnement des dechets nucleaires sulfates

    Energy Technology Data Exchange (ETDEWEB)

    Lenoir, M.

    2009-09-15

    The thesis deals with sulphate solubility and sulphate diffusion in oxide glasses, in order to control sulphate incorporation and sulphate volatilization in nuclear waste glasses. It was conducted on simplified compositions, in the SiO{sub 2}-B{sub 2}O{sub 3}-R{sub 2}O (R = Li, Na, K, Cs), SiO{sub 2}-B{sub 2}O{sub 3}-BaO and V{sub 2}O{sub 5}-B{sub 2}O{sub 3}-BaO systems. These compositions allowed us to study the influence of the nature of network-modifying ions (Li{sup +}, Na{sup +}, K{sup +}, Cs{sup +} or Ba{sup 2+}) and also of former elements (Si, B, V), on structure and properties of glasses. Sulphate volatility is studied in sodium borosilicate melts using an innovative technique of sulphate quantitation with Raman spectroscopy. This technique is useful to obtain kinetic curves of sulphate volatilization. The establishment of a model to fit these curves leads to the determination of diffusion coefficients of sulphate. These diffusion coefficients can thus be compared to diffusion coefficients of other species, determined by other techniques and presented in the literature. They are also linked to diffusion coefficients in relation with the viscosity of the melts. Concerning sulphate solubility in glasses, it depends on glass composition and on the nature of sulphate incorporated. Sulphate incorporation in alkali borosilicate glasses leads to the formation of a sulphate layer floating on top of the melt. Sulphate incorporation in barium borosilicate and boro-vanadate glasses leads to the crystallization of sulphate species inside the vitreous matrix. Moreover, sulphate solubility is higher in these glasses than in alkali borosilicates. Finally, exchanges between cations present in glasses and cations present in the sulphate phase are also studied. (author)

  18. Little and middle enterprises and industries: examples of collaboration in the domains of wastes valorization and treatment; PME-PMI: des exemples de collaboration dans les domaines du traitement et de la valorisation des dechets

    Energy Technology Data Exchange (ETDEWEB)

    Kunegel, A. [Agence de l' Environnement et de la Maitrise de l' Energie, ADEME, 75 - Paris (France); Lacaze, P. [Lacaze, 46 - Leyme (France); Vandenbusshe, F. [Antema (France); Stock, P. [Nucleos (France); Giroudiere, F. [Institut Francais du Petrole (IFP), 92 - Rueil-Malmaison (France)

    2004-07-01

    In the domain of the wastes valorization and treatment, this seminar presents the national context of the wastes treatment, the thermal valorization of oil heterogenous wastes, an innovative process of wastes valorization by microwaves, the leachates treatment and the biogas valorization, wastes valorization by thermolysis. (A.L.B.)

  19. Study of stabilization/solidification processes (of solid porous wastes) based on hydraulic or bituminous binders; Etude des procedes de stabilisation/solidification (des dechets solides poreux) a base de liants hydrauliques ou de liants bitumineux

    Energy Technology Data Exchange (ETDEWEB)

    Sing-Teniere, Ch.

    1998-02-01

    The first part of this thesis presents the regulatory framework and the technical context linked with the study of stabilized/solidified wastes and with the evaluation of stabilization/solidification processes. A presentation of the two type of ultimate wastes under study (a used catalyst and an activated charcoal) and an analysis of the processes is given. The second part is devoted to the experimental characterization of both types of porous wastes. The third part deals with the processing of such wastes using an hydraulic binder. The study stresses on both on the stabilization/solidification efficiency of the process and on the conditions of its implementation. The same work is made for a process that uses a bituminous binder. Some choice criteria for the selection of the better process are deduced from the examination of the overall data collected. The waste characterization methodology is applied six times: two times for the raw wastes, two times for the same wastes processed with an hydraulic binder, and two times for the same wastes processed with a bituminous binder. (J.S.)

  20. Opinions and attitudes on the wastes management, the eco-products consumption and the atmospheric pollution; Opinions et attitudes sur la gestion des dechets, sur la consommation des eco-produits et sur la pollution atmospherique

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-03-01

    This document presents the results of the inquiry on the ''way of life and french aspiration'' concerning the energy. The inquiry was realized at the beginning of 2001 on a sample of 2000 people. The questions dealt with the three following topics: the french attitude facing the atmospheric pollution, consumption and the environment preservation, the opinion on the wastes management. (A.L.B.)

  1. The reprocessing-recycling of spent nuclear fuel. Actinides separation - Application to wastes management; Le traitement-recyclage du combustible nucleaire use. La separation des actinides - Application a la gestion des dechets

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    After its use in the reactor, the spent fuel still contains lot of recoverable material for an energetic use (uranium, plutonium), but also fission products and minor actinides which represent the residues of nuclear reactions. The reprocessing-recycling of the spent fuel, as it is performed in France, implies the chemical separation of these materials. The development and the industrial implementation of this separation process represent a major contribution of the French science and technology. The reprocessing-recycling allows a good management of nuclear wastes and a significant saving of fissile materials. With the recent spectacular rise of uranium prices, this process will become indispensable with the development of the next generation of fast neutron reactors. This book takes stock of the present and future variants of the chemical process used for the reprocessing of spent fuels. It describes the researches in progress and presents the stakes and recent results obtained by the CEA. content: the separation of actinides, a key factor for a sustainable nuclear energy; the actinides, a discovery of the 20. century; the radionuclides in nuclear fuels; the aquo ions of actinides; some redox properties of actinides; some complexing properties of actinide cations; general considerations about treatment processes; some characteristics of nuclear fuels in relation with their reprocessing; technical goals and specific constraints of the PUREX process; front-end operations of the PUREX process; separation and purification operations of the PUREX process; elaboration of finite products in the framework of the PUREX process; management and treatment of liquid effluents; solid wastes of the PUREX process; towards a joint management of uranium and plutonium: the COEX{sup TM} process; technical options of treatment and recycling techniques; the fuels of generation IV reactors; front-end treatment processes of advanced fuels; hydrometallurgical processes for future fuel cycles; the conversion of actinides; fuels re-fabrication; pyrometallurgical processes; strategy of radionuclides management; transmutation principles; general conclusion. (J.S.)

  2. The high-level and long life radioactive wastes management in France: inquiry near the actors; La gestion des dechets nucleaires a haute activite et a vie longue en France: enquete aupres des acteurs

    Energy Technology Data Exchange (ETDEWEB)

    Le Dars, A

    2002-07-01

    This document presents talks carried out near various actors of the radioactive wastes management in France. These talks have been realized in the framework of an inquiry aiming at supporting the developments of an economic sciences thesis, relative to the sustainable management of the nuclear wastes. This inquiry aimed to better determine the actors stakes, the controversies on the technical choices, but also the possible cooperation. (A.L.B.)

  3. The main rules regarding the management of solid waste and liquid effluent contaminated during use at nuclear medicine departments; Les principales regles de gestion des dechets solides et des effluents liquides contamines dans les services de medecine nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Boudouin, E. [Autorite de Surete Nucleaire, Direction des rayonnements ionisants et de la sante, 75 - Paris (France)

    2011-02-15

    This article describes the key requirements applicable to the management of contaminated medical waste and effluent from hospitals and health care centres, and more especially from nuclear medicine departments that use radionuclides for the purposes of diagnosis (in vivo or in vitro) or in patient treatment. It also presents the key management regulations, making a distinction between contaminated solid waste and contaminated liquid waste from such nuclear medicine departments. (author)

  4. Guidance for the management of solid waste contaminated by urine of patients after administration of radiopharmaceuticals; Conseil pour la gestion des dechets solides contamines par des urines de patients apres administration de radiopharmaceutiques

    Energy Technology Data Exchange (ETDEWEB)

    Touzery, C.; Prevot, S.; Perrette, B.; Boichot, C.; Berriolo-Riedinger, A.; Toubeau, M.; Riedinger, J.M.; Brunotte, F. [Centre de Lutte Contre le Cancer Georges-Francois-Leclerc, Service de Medecine Nucleaire, 21 - Dijon (France)

    2003-02-01

    The recent reinforcement of the French regulation on radionuclide contaminated waste brings the Nuclear Medicine Departments in charge of writing guidance intended to the personnel of the health care units. A special attention must be paid to the waste contaminated by urine of the incontinent patients. The present paper provides time duration for the collection and the storage of urine contaminated waste obtained from the simulation with literature models and data for the most frequently used radiopharmaceuticals. The validity of the results is discussed according to the parameter variations of the biokinetic models. (authors)

  5. Proposal of law relative to the follow-up of the sanitary and environmental consequences of nuclear tests. Wastes, pollution and nuisances; Proposition de loi relative au suivi des consequences sanitaires et environnementales des essais nucleaires. Dechets, pollution et nuisances

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-01

    This proposal of law aims at answering the expectations of all people, civil and military, who participated to the nuclear tests carried out by France between February 13, 1960 and January 27, 1996, or who lived in the vicinity of the Sahara and French Polynesia experimentation sites. It proposes the application of the link presumption principle to any illness affecting these people, the creation of an indemnization fund for the victims of these tests and the creation of a national commission for the follow-up of the enforcement of this law. (J.S.)

  6. Domestic wastes heat treatment. Evaluation of the 42 french operations assisted by the ADEME; Traitement thermique des dechets menagers. Bilan des 42 operations francaises aidees par l'ADEME

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-09-01

    Between 1993 and 2000, the ADEME allowed a financial assistance for the construction of 42 domestic wastes incinerators. This document provides the first results of these units operating evaluation with a presentation of the french park transformation, the operating, the economic analysis of the sector, the financial accounting and the future market. (A.L.B.)

  7. Wastes incineration and public health: status of recent knowledge and risk evaluation; L'incineration des dechets et la sante publique: bilan des connaissances recentes et evaluation du risque

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-07-01

    The incineration of municipal and industrial wastes produces combustion products with various pollutants like: dusts, acid gases, heavy metals, nitrogen oxides, dioxines etc.. This report analyzes the toxicity of different pollutants (particulates, polycyclic halogenated compounds, cadmium, mercury, lead), the exposure of the population with respect to incineration pollutants (occupational and general exposure), and the risks linked with this exposure (hazard identification, exposure evaluation, risk characterization, results). (J.S.)

  8. Opinions of the French on the atmospheric pollution, the wastes management and the eco-products; Opinions des francais sur la pollution atmospherique, la gestion des dechets et les eco-produits

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-06-01

    Five main opinions can be presented from the answers analysis to the inquiry realized in 1999 by the ADEME on the French way of life and aspirations. The French think that the atmospheric pollution is dangerous for the health and that they are badly informed about the air quality of their town. 87% of the motorists are ready to leave their vehicles the days of high urban pollution level. In less of two years the green products credibility is worsening. Nevertheless the consumer believes sensitive to the ecological arguments. Finally the French are very favorable to the domestic wastes control. (A.L.B.)

  9. Wastes incineration and public health: status of recent knowledge and risk evaluation; L'incineration des dechets et la sante publique: bilan des connaissances recentes et evaluation du risque

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-07-01

    The incineration of municipal and industrial wastes produces combustion products with various pollutants like: dusts, acid gases, heavy metals, nitrogen oxides, dioxines etc.. This report analyzes the toxicity of different pollutants (particulates, polycyclic halogenated compounds, cadmium, mercury, lead), the exposure of the population with respect to incineration pollutants (occupational and general exposure), and the risks linked with this exposure (hazard identification, exposure evaluation, risk characterization, results). (J.S.)

  10. Des dispositions responsables à prendre pour la protection des ...

    African Journals Online (AJOL)

    En considérant l'effet néfaste des maladies, des parasites, du changement climatique et d'autres facteurs environnementaux (les OGM par exemple) sur la survie des abeilles, la baisse de leurs populations dans certaines parties du monde ne saurait être attribuée aux seules pesticides. En plus, l'impact de ces derniers sur ...

  11. Aspects des Onychomycoses chez des patients camerounais de ...

    African Journals Online (AJOL)

    ... biologiques et évolutifs des onychomycoses chez des patients camerounais. Méthode : Il s'agit d'une étude rétrospective et descriptive menée de mars 2011 à mars 2014 dans l'unité de dermatologie de l'hôpital général de Douala (HGD), incluant des patients chez lesquels le diagnostic d'onychomycose avait été posé.

  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 radioactifs a de grandes distances; il s'ensuit que de nombreux animaux et vegetaux marins vivant loin des foyers de contamination peuvent accumuler ces elements jusqu'a des concentrations dangereuses. (author) [Spanish] En el informe se pone de manifiesto que las corrientes de agua transportan elementos radiactivos a grandes distancias, por lo cual muchos animales y vegetales marinos, que habiten lejos de los focos de contaminacion, pueden acumular estos elementos en concentraciones peligrosas. (author) [Russian] V doklade podcherkivaetsja, chto vodnye massy raznosjat techenijami radioaktivnye jelementy na bol'shie rasstojanija, v rezul'tate chego mnogie morskie zhivotnye i rastenija, obitajushhie daleko ot ochagov zarazhenija, mogut nakaplivat' ztj jelementy do opasnyh koncentracij. (author)

  13. Usages des TIC et socialisation professionnelle des enseignants-chercheurs

    OpenAIRE

    Lavielle-Gutnik, Nathalie; Massou, Luc

    2013-01-01

    En prenant appui sur une nouvelle analyse des données recueillies dans l’enquête Tec-Meus (2008-2011, MSH Lorraine) sur la place accordée par des enseignants-chercheurs en sciences humaines et sociales aux technologies de l’information et de la communication (TIC) dans leur activité d’enseignement, nous souhaitons nous focaliser dans cet article sur la compréhension des processus de socialisation professionnelle en jeu dans leur usage déclaré des TIC. Par socialisation professionnelle, nous e...

  14. Contribution to the detection of radioactivity as applied to regular testing and to protection; Contribution a la detection des rayonnements en vue du controle et de la protection

    Energy Technology Data Exchange (ETDEWEB)

    Fuhrmann,; Joffre,; Savouyaud, [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    1. The equipment which is at the disposal of teams carrying out tests, such as the Radiations Analysis section and the Radtivity Engineers section at the CEA, has been developed from apparatus designed for laboratory research. The result of this is that even when attempts have been made to make this equipment more robust and manageable, no effort has been made to adapt the equipment to exactly what is required for assuring protection against radioactivity. It has therefore been necessary for this section to exactly specify its requirements and to carry out itself a part of the work required for developing the most suitable material. 2. The most important problems concerned the analysis of the radioactivity and the fabrication of electronic equipment, which could be available cheaply on a large scale and be also as far as possible self supporting. 3. In the present paper we briefly describe our contribution to this subject and in particular: - the improvement of methods of {gamma} ray analysis which use photographic films; - the try out of a simple and cheap technique for the analysis and spectrography of {alpha} particles; - the utilisation of new electronic material: ionisation chamber counters, scintillators; - the development of special equipment for measuring the mean flux of particles which are emitted periodically in very short bursts. (author)Fren. [French] 1. Le materiel qui se trouve a la disposition des organismes de controle, tel le Service de Controle des Radiations et de Genie Radioactif au Commissariat a l'Energie Atomique, a ete concu a partir de materiels realises pour des experiences de laboratoire et, meme lorsqu'on a pense a le rendre plus robuste et plus maniable, on a generalement omis de l'adapter exactement aux besoins de la protection contre les radiations. Aussi ce Service a-t-il ete amene a preciser exactement ses besoins et a realiser lui-meme une partie des etudes necessaires a la mise au point d'un materiel mieux adapte. 2. Les

  15. Direction des Publications

    African Journals Online (AJOL)

    Synthese

    Unité de Recherche des Matériaux et des Energies Renouvelables (U.R.M.E.R). Université Abou –Baker Belkaid B.p : 119 Tlemcen 13000 Algerie. 2. Unité de Développement de la Technologie Du Silicium. UDTS, BP 399, Alger, Algérie. Accepté le : 08/06/2011. صخلم. داوﻣﻟا نﻣ ﻲﺗﻟا ﺔﺻﺎﺧو ،ﺔﻋﺎﻧﺻ يأ رﯾوطﺗ ﻲﻓ ﺎﯾﺳﯾﺋر ﻼﻣﺎﻋ ةرﯾﺧﻷا تاوﻧﺳﻟا ...

  16. Mykotische Infektionen des Penis

    Directory of Open Access Journals (Sweden)

    Mayser P

    1999-01-01

    Full Text Available Die häufigste mykotische Infektion des Penis stellt die Balanitis/Balonoposthitis durch Candida albicans dar. Sie weist eine steigende Inzidenz auf und scheint vornehmlich durch Genitalverkehr übertragen zu werden. Penile Infektionen durch Dermatophyten sind sehr selten, obwohl die Tinea inguinalis zu den häufigeren Erkrankungen zählt. Eine Mitbeteiligung des Penis im Rahmen von Systemmykosen kennzeichnet zumeist ein schwer verlaufende Erkrankung. Ursächlich kann beim immunoinkompetenten Patienten nahezu jeder Erreger in Frage kommen. Biopsie sowie Gewebekultur aus den meist ulzerativen Veränderungen können die Diagnose sichern. Die meisten superfiziellen Infektionen sprechen zufriedenstellend auf eine topische antimykotische Behandlung an, insbesondere wenn Provokationsfaktoren und die Möglichkeit der sexuellen Transmission berücksichtigt werden. Ausgedehnte Infektionen durch Dermatophyten, Hefen und natürlich systemische Infektionen erfordern eine systemische antimykotische Therapie.

  17. Chimie des processus biologiques

    OpenAIRE

    Fontecave, Marc

    2014-01-01

    Cours : Chimie biologique radicalaire : de l’origine de l’ADN au métabolisme d’aujourd’hui Il est généralement admis que les radicaux libres, espèces chimiques très réactives, sont des poisons pour les systèmes vivants qui ont élaboré des mécanismes efficaces pour s’en protéger et s’en débarrasser lorsqu’ils viennent à se former, par accident. Par exemple ce qu’on appelle communément le stress oxydant est une situation caractérisée par une accumulation de radicaux issus de l’oxygène moléculai...

  18. La cogestion des Ressources naturelles

    International Development Research Centre (IDRC) Digital Library (Canada)

    L'eau, le sol, les nutriments, la lumière du soleil — ce sont des choses de la vie. .... habitent encore ces régions, soit de 9 % à 14 % de la population mondiale. ...... La guerre civile a fait vivre au Cambodge des années de chaos, d'anarchie et ...... et les allégeances politiques sont des facteurs qu'il est impossible d'ignorer.

  19. Des Ogle's old stump

    International Nuclear Information System (INIS)

    Jones, M.; Sutton, D.; Wallace, R.

    1998-01-01

    On 17 October 1997 Sylvia Bryan of RD4 Kaitaia wrote to 'Dear Somebody-Everybody' at the Anthropology Department, University of Auckland, urging further examination of an adzed stump found by Des Ogle during planting out of the Te Aupouri forest. The authors have since sought out relevant information and present it here for the interests of our readers. (author). 7 refs., 1 fig

  20. Grundlagen des Tissue Engineering

    Science.gov (United States)

    Mayer, Jörg; Blum, Janaki; Wintermantel, Erich

    Die Organtransplantation stellt eine verbreitete Therapie dar, um bei krankheitsoder unfallbedingter Schädigung eines Organs die Gesamtheit seiner Funktionen wieder herzustellen, indem es durch ein Spenderorgan ersetzt wird. Organtransplantationen werden für die Leber, die Niere, die Lunge, das Herz oder bei schweren grossflächigen Verbrennungen der Haut vorgenommen. Der grosse apparative, personelle und logistische Aufwand und die Risiken der Transplantationschirurgie (Abstossungsreaktionen) sowie die mangelnde Verfügbarkeit von immunologisch kompatiblen Spenderorganen führen jedoch dazu, dass der Bedarf an Organtransplantaten nur zu einem sehr geringen Teil gedeckt werden kann. Sind Spenderorgane nicht verfügbar, können in einzelnen Fällen lebenswichtige Teilfunktionen, wie beispielsweise die Filtrationsfunktion der Niere durch die Blutreinigung mittels Dialyse ersetzt oder, bei mangelnder Funktion der Bauchspeicheldrüse (Diabetes), durch die Verabreichung von Insulin ein normaler Zustand des Gesamtorganismus auch über Jahre hinweg erhalten werden. Bei der notwendigen lebenslangen Anwendung apparativer oder medikamentöser Therapie können für den Patienten jedoch häufig schwerwiegende, möglicherweise lebensverkürzende Nebenwirkungen entstehen. Daher werden in der Forschung Alternativen gesucht, um die Funktionen des ausgefallenen Organs durch die Implantation von Zellen oder in vitro gezüchteten Geweben möglichst umfassend wieder herzustellen. Dies erfordert biologisch aktive Implantate, welche die für den Stoffwechsel des Organs wichtigen Zellen enthalten und einen organtypischen Stoffwechsel entfalten.

  1. Dictionnaire des risques psychosociaux

    CERN Document Server

    Zawieja, Philippe

    2014-01-01

    Stress, suicide, harcèlement, épuisement professionnel, workaholism... Au-delà de la souffrance qu'elles désignent, ces notions souvent récentes constituent une approche inédite, et demandent à mieux être comprises, dans leur ensemble et isolément. C'est tout l'enjeu de ce dictionnaire, pionnier en son genre. Le lecteur y trouvera représentés, avec les 314 entrées (rédigées par 251 contributeurs) qui le composent, tous les champs disciplinaires s'intéressant à la souffrance au travail : psychologie du travail et des organisations, psychologie sociale et psychosociologie, psychanalyse, psychopathologie et psychiatrie, ergonomie, sociologie du travail et des organisations, médecine du travail, droit du travail et de la sécurité sociale, sciences de gestion, philosophie... Y sont détaillés les principaux concepts, notions, approches, méthodes, théories, outils, études, etc., ayant cours dans l'étude des risques psychosociaux, mais aussi certaines professions emblématiques (infirmières,...

  2. Le vernis des apparences

    Directory of Open Access Journals (Sweden)

    Grazia Nicosia

    2010-04-01

    Full Text Available Le but de cet article est de comprendre l’incidence sémiotique du nettoyage d’un tableau ainsi que la résultante cognitive induite sur l’observateur. Cette étude confronte l’analyse des phénomènes visuels engendrés par le jaunissement du vernis et son retrait, à des entretiens réalisés à dessein. Le retrait d’un vernis jauni change considérablement l’image. L’heure, le climat, la saison et l’activité même des personnages s’en trouvent ainsi modifié. La patine peut être perçue, soit comme un obstacle à l’exploration, soit pour ceux qui l’apprécient, comme le medium d’une relation plus intime entre l’œuvre et l’observateur.The purpose of this article is to understand the semiotic impact of the cleaning of a painting and the cognitive effects induced on the observer. This study analyses conjointly the visual phenomenon generated by yellowing varnish and its removal and controlled interviews of observers.The removal of yellowing varnish modifies considerably the perception of the picture. Daytime, climate, season and characters activities are modified. The patina may be perceived either as an obstacle to the painting exploration, or, for those who appreciate it, as a medium for a closer relationship between the painting and the observer.

  3. Ultimate Disposal of High-Level Radioactive Wastes - Fixation in Phosphate Glass with Emphasis on the Continuous Mode of Plant Operation; Elimination Definitive de Dechets de Haute Activite - Fixation dans du Verre au Phosphate en Vue d'une Exploitation de l'Installation en Continu; ОКОНЧАТЕЛЬНОЕ УДАЛЕНИЕ ВЫСОКОАКТИВНЫХ ОТХОДОВ - ФИКСАЦИЯ В ФОСФАТНОМ СТЕКЛЕ НА НЕПРЕРЫВНО РАБОТАПЦЕЙ УСТАНОВКЕ; Evacuacion Definitiva de Desechos de Elevada Radiactividad. Fijacion en Vidrio al Fosfato Atendiendo Particularmente a la Continuidad de la Marcha de la Instalacion

    Energy Technology Data Exchange (ETDEWEB)

    Hatch, L. P.; Weth, G. C.; Tuthill, E. J. [Brookhaven National Laboratory, Upton, Long Island, NY (United States)

    1963-02-15

    In the study of ultimate disposal of high-level radioactive wastes at Brookhaven National Laboratory emphasis is being placed on the formation of phosphate glasses as a means of incorporating the fission products in stable media. Of primary interest here is the development of a process in which the entire conversion from the raw aqueous wastes to the final.glass product would be carried out in an all-liquid system. The phosphate-glass method offers a number of important advantages in this respect and, in particular, lends itself to the development of a continuous process in which the liquid medium would be readily transferable from one process step to another. The paper presents the results of bench-scale studies on the production of phosphate glasses, with the continuous mode of operation, utilizing various types of aqueous wastes. The studies have been in progress for some 20 months and were carried out to determine essential operating parameters with particular attention paid to corrosion resistance and physical integrity of the high-temperature crucible. In addition, the paper discusses flow-sheet development together with the design and results of operation of. an engineering-scale plant having a capacity of 0.5 ft{sup 3} of glass per day with a continuous feed of simulated non-radioactive wastes. (author) [French] Dans l'etude des methodes d'elimination definitive des dechets de haute activite, le Laboratoire national de Brookhaven attache une grande importance aux verres au phosphate pour la fixation des produits de fission dans un milieu stable. On s'efforce essentiellement de mettre au point un processus dans lequel la transformation, depuis le dechet liquide et l'etat brut jusqu'au produit vitreux final, s'opererait entierement en phase liquide. A cet egard, le verre au phosphate presente un grand nombre d'avantages importants; en particulier, il se prete a la mise au point d'un processus continu dans lequel le milieu liquide pourrait facilement passer d

  4. Harmonische Reduktion des linken Ventrikels

    OpenAIRE

    Atila, M. (Mehmet)

    2005-01-01

    In der vorliegenden Arbeit wurde die harmonische Reduktion des linken Ventrikels am Modell des ausgewachsenen Hausschweins, unter Verwendung von Saugkappen variabler Größe untersucht. In 10 Schweinen mit Herzen normaler Größe und Funktion wurde eine Saugkappe, in Größe und Form an das abzufaltende Wandsegment angepasst, auf die epikardiale Oberfläche des schlagenden Herzens gesetzt. Wir führten Messungen der linksventrik. und der pulmonalart. Drücke, des ventrikulären Durchmessers und der Her...

  5. New applications of radio-isotopes in France; Quelques nouvelles applications des radioelements en France

    Energy Technology Data Exchange (ETDEWEB)

    Leveque, P; Hours, R; Martinelli, P; May, S; Sandier, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires; Brillant, J [Societe Soletanche (France)

    1958-07-01

    unite de celui du metal de base. L'ition de ciment dans les forages a pour but la consolidation et l'impermeabilisation des sols dans une certaine zone. L'extention de cette zone est etudiee en marquant le ciment et en envoyant dans les forages voisins non injectes une sonde Geiger-Muller qui decele si le ciment a ou non atteint ces forages. On peut ainsi controler l'extension de la zone injectee. La cinetique des echanges d'ions entre differents outremers et des solutions acqueuses est etudiee en suivant un ion radioactif, soit dans la solution, soit dans l'outremer lui-meme. Differentes valeurs de coefficients de diffusion et d'energies d'activation sont donnees par les echanges etudies. (auteur)

  6. La recherche en action : des solutions locales, des effets durables ...

    International Development Research Centre (IDRC) Digital Library (Canada)

    15 déc. 2010 ... Le Centre de recherches pour le développement international (CRDI) appuie la production et l'application de connaissances qui améliorent de façon notable la situation des habitants des pays en développement.

  7. Analyse des caractéristiques structurelles et des performances ...

    African Journals Online (AJOL)

    SARAH

    28 févr. 2014 ... performances technico-économiques de la riziculture irriguée en Côte d' .... en nous basant sur les prix des intrants et des produits en vigueur au cours ..... la recherche et de la vulgarisation et le transfert de technologies ; (2) ...

  8. Evaluation des pratiques de gestion des adventices en riziculture

    African Journals Online (AJOL)

    Les résultats ont montré que les méthodes de gestion de l'enherbement ont .... Le contrôle des adventices en riziculture irriguée a principalement .... mesurer la hauteur des plantes et la longueur ..... Performance agronomique du Sys- tème de ...

  9. Diversification des moyens de subsistance des petits producteurs de ...

    International Development Research Centre (IDRC) Digital Library (Canada)

    L'économie du Malawi repose essentiellement sur la culture du tabac, qui représente plus de 70 % des revenus d'exportation. Pour 60 % des 100 000 membres de la National Smallholder Farmers' Association of Malawi (NASFAM), le tabac est la seule et unique source de revenus. Les cultivateurs de tabac, au Malawi ...

  10. Culture du bambou : diversification des moyens de subsistance des ...

    International Development Research Centre (IDRC) Digital Library (Canada)

    Culture du bambou : diversification des moyens de subsistance des petits producteurs de tabac du sud de la province de Nyanza, au Kenya - phase II. Au cours de la première phase du projet (projet no 103765), les chercheurs ont effectué une analyse de marché pour le bambou et les produits du bambou, comparé les ...

  11. Roles et taches des accompagnateurs des patients hospitalises ...

    African Journals Online (AJOL)

    Roles et taches des accompagnateurs des patients hospitalises dans le service de pneumo-phtysiologie au Centre Hospitalier Universitaire Yalgado Ouedraogo de ... Logistical support represented by material support, drug supply, cleaning of premises, and littering occupied respectively 100%, 91%, 42% and 73%.

  12. Repercussions agronomiques de l'epandage d'effluents et dechets de moulins a huile d'olive

    OpenAIRE

    Morisot, Alain; Tournier, Jean Paul

    1986-01-01

    Les répercussions agronomiques de l’épandage d’effluents (ou margines) de moulins à huile d’olive sont étudiées au moyen de cultures de ray-grass en pots sous serre et de tests d’incubation sur l’azote minéral. L’épandage de 40 mm (40 l/m2) de margines sur une plantation de ray-grass diminue le rendement moyen de 45 p. 100 par rapport à celui de la culture de référence. La production de matière sèche des ray-grass semés immédiatement après l’épandage (doses de 40 et 80 mm) est égale au t...

  13. COMPORTEMENT D’UN COMPOSITE FINE MINERALE - CIMENT - BOIS ELABORE A L’AIDE DE DECHETS INDUSTRIELS SOLIDES

    Directory of Open Access Journals (Sweden)

    M.L BENMALEK

    2000-06-01

    Full Text Available Cinq fines minérales de différentes natures minéralogiques et de limites granulaires comparables, provenant de résidus de carrières, ont été traitées pour former le squelette de bétons légers d'isolation. L'allégement et le pouvoir isolant de ces bétons sont obtenus par incorporation de granulats de bois dans la matrice constituée de la fine minérale et de ciment CPA. Dans une première partie, sont présentés les principales caractéristiques de ces fines: minéralogie par diffraction des rayons X, granulométrie laser, conductivité thermique à la sonde TPS, densité sèche par  pycnomètrie à eau et morphologie au MEB. La seconde partie est consacrée à l'étude de l'effet des caractéristiques de ces fines sur le comportement hygrothermique et mécanique de ces bétons élaborés avec une même formulation et un même état de consistance au moulage. Les résultats de ces investigations sont comparés entre eux et  à ceux de matériaux usuels classés par la RILEM.

  14. Post graduate course of radiation protection. V. 1-2; Cours post-universitaire de radioprotection. V. 1-2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-12-01

    In September 1991, the General Conference of IAEA, in the resolution GC/XXXV/RES/552 demanded the Director General to formulate the propositions in the field of education and teaching of radiation protection. After its meeting in 1993, the General Conference (document GC/XXXVII/1067) a program of education in radiation protection and nuclear safety. The IAEA has chosen L'Instut national des science et techniques nucleaires (INSTN) de Saclay, France, to perform the french training for its long-term education in nuclear field. During the nine weeks in May and June 1994, 24 participants from 22 countries attended 80 courses presented by 70 teachers. The organizers have attained a successful cooperation of competent French organizations in the field of radiation protection and nuclear safety as: Institut de protection et de surete nucleaire (IPSN), Commissariat a l'energie atomique (CEA), Compagnie generales des matieres nucleaires (COGEMA), Agence nationale pour la gestion de dechets radioactif (ANDRA), Office de protection contre les raynnements ionisants (OPRI), Electicite de France (EDF), as well as outstanding specialists in the medical field. The series of these lectures are presented in these two volumes. Admitting that the education and training in the field of radiation protection and nuclear safety are responsibilities of national authorities the IAEA hopes that this published material would be widely used by the Member States as a basis for their training programs in the mentioned field.

  15. Post graduate course of radiation protection. V. 1-2

    International Nuclear Information System (INIS)

    1995-01-01

    In September 1991, the General Conference of IAEA, in the resolution GC/XXXV/RES/552 demanded the Director General to formulate the propositions in the field of education and teaching of radiation protection. After its meeting in 1993, the General Conference (document GC/XXXVII/1067) a program of education in radiation protection and nuclear safety. The IAEA has chosen L'Instut national des science et techniques nucleaires (INSTN) de Saclay, France, to perform the french training for its long-term education in nuclear field. During the nine weeks in May and June 1994, 24 participants from 22 countries attended 80 courses presented by 70 teachers. The organizers have attained a successful cooperation of competent French organizations in the field of radiation protection and nuclear safety as: Institut de protection et de surete nucleaire (IPSN), Commissariat a l'energie atomique (CEA), Compagnie generales des matieres nucleaires (COGEMA), Agence nationale pour la gestion de dechets radioactif (ANDRA), Office de protection contre les raynnements ionisants (OPRI), Electicite de France (EDF), as well as outstanding specialists in the medical field. The series of these lectures are presented in these two volumes. Admitting that the education and training in the field of radiation protection and nuclear safety are responsibilities of national authorities the IAEA hopes that this published material would be widely used by the Member States as a basis for their training programs in the mentioned field

  16. Decontamination of latex gloves; Decontamination de gants en latex

    Energy Technology Data Exchange (ETDEWEB)

    Boutot, P; Schipfer, P; Blachere, A [Commissariat a l' Energie Atomique, Chusclan (France). Centre de Production de Plutonium de Marcoule

    1969-07-01

    Initially the latex gloves used in controlled zones were processed after use as radioactive waste. In view of the continually increasing number used, however, the persons in charge of the SPRAR have considered the possibility of decontaminating the gloves and using them again after control. The recovery installations which have been developed were initially designed rather crudely and operated irregularly; they have been progressively improved as a result of the experience acquired; today they are more really an industrial concern, equipped with automatic machinery. In 1967 it has been possible with this set-up to recover 247000 pairs of gloves, representing nearly 70 per cent of the number treated. (author) [French] Initialement, les gants de latex utilises dans les zones controlees etaient conditionnes apres emploi comme dechets radioactifs. Mais, devant l'augmentation sans cesse croissante des quantites employees, les responsables du SPRAR ont envisage leur decontamination et leur recyclage apres controles. Les installations de recuperation mises au point, de conception artisanale et fonctionnant de maniere episodique au depart, se sont progressivement ameliorees au fur et a mesure de l'experience acquise; elles revetent aujourd'hui le caractere d'une exploitation industrielle equipee de machines automatiques. En 1967, ces nouvelles installations ont permis de recuperer 247000 paires de gants, ce qui represente pres de 70 pour cent des quantites traitees. (auteur)

  17. Utilisation sans risque des eaux usées, des excréta et des eaux ...

    International Development Research Centre (IDRC) Digital Library (Canada)

    Les responsables de ce projet piloteront l'application et l'adaptation des principes directeurs relatifs à l'utilisation sans risque des eaux usées, des excreta et des eaux grises en agriculture et en aquaculture (Guidelines for the Safe Use of Wastewater, Excreta and Greywater in Agriculture and Aquaculture), que ...

  18. Direction des Publications

    African Journals Online (AJOL)

    Synthese

    mélange pulvérulent de coke et de calcaire. La réduction est assurée par le gaz CO à 1250°C [2]. Le procédé Kawazaki iron powder utilise la calamine comme matière première et aussi CO comme gaz réducteur pour élaborer des poudres de fer. [3]. Un autre procédé plus connu qui fabrique les poudres de fer à partir de la.

  19. Glossaire des sigles

    OpenAIRE

    2015-01-01

    ABM Anti-ballistic missile = Missile antimissile balistique AGM Air-to-ground missile = Missile air-sol AIEA Agence Internationale de l’Energie Atomique ALCM Air-launched cruise missile = Missile de croisière air-sol ANSEA Association des Nations du Sud-Est asiatique ANT* Arme nucléaire tactique ASAT Anti-satellite = Arme antisatellite ASW Anti-submarine warfare = Guerre anti-sous-marine AWACS Airborne warning and control system = Système aérien de contrôle et d’alerte BMD Ballistic missile d...

  20. 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)

  1. Instruments used to measure or check {alpha}, {beta}, {gamma} activity and neutron emission in the course of processing ore or irradiated fuel; Appareils de mesure ou de controle {alpha}, {beta}, {gamma}, n, des circuits des usines de traitement du minerai ou du combustible irradie

    Energy Technology Data Exchange (ETDEWEB)

    Blanc, A; Brunet, M; Kermagoret, M; Labeyrie, J; Roux, G; Vasseur, J; Weil, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1959-07-01

    One of the methods checking ores in the course of treatment is the rapid quantitative determination of thorium. This measurement is carried out by means of a scintillation instrument which shows the {beta} and {alpha} coincidences of ThC and ThC'. The treatment of irradiated fuel is accompanied by a large number of radioactive checks relative to the performance of the fixation and elution operations of uranium in the ion exchangers, to the concentration of radioactivity of effluent sent from the plant into watercourses. The operations of fixation and elution of the uranium are checked automatically by an instrument which takes a sample of 5 cm{sup 3} of solution, evaporates it and measures its activity every 10 or 20 minutes. Plutonium concentrations are measured: - in the presence of strong {beta} {gamma} activities, by means of rotating cylinder detectors; - in the presence of weak {beta} {gamma} activities, by means of {alpha} detectors scanning a constant level liquid surface; - by means of fission chambers relatively insensitive to {gamma}. Fission product concentrations are measured by chambers, counters or scintillators, according to the amount of {gamma} activity present. Finally, the activity of effluent to be emptied into watercourses is checked by means of a scintillation instrument, which measures the {alpha} activity on the one hand, and on the other hand the {beta} {gamma} activity of residue from a 100 cm{sup 3} sample taken and evaporated in 20 minutes. (author) [French] Parmi les controles relatifs au minerai en cours de traitement, figure le dosage rapide de thorium. Cette mesure est realisee au moyen d'un appareillage a scintillation qui met en evidence la coincidence des emissions {beta} et {alpha} du ThC et du ThC'. Le traitement des combustibles irradies s'accompagne d'un grand nombre de controles radioactifs portant sur le fonctionnement des operations de fixation et d'elution de l'uranium dans les echangeurs d'ions, sur la concentration du

  2. The use of radioactive sources for the study of wear in refractory linings; L'emploi de sources radioactives pour l'etude de l'usure des revetements refractaires

    Energy Technology Data Exchange (ETDEWEB)

    Courtois, G; Hours, R [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1960-07-01

    Following a discussion on the radioactive method for studying wear in refractory linings (description of the method, advantages and disadvantages, choice of radioactive indicator and detection), the article deals in some detail with the problems of safety involved in this technique. The two most important points discussed are: 1- the need to fix an upper limit of activity in the cast iron: the authors propose a figure of 1 mc of cobalt 60 in 500 tons; 2- the precautions necessary to remedy the diffusion of cobalt 60 in the brickwork (development of special pyro-ceramic sources). After a discussion on the international view point regarding the use of the method, a brief outline of some French projects is given, with particular reference to the case of a blast furnace. A note from the Commission interministerielle des Radioelements is given as an appendix; this deals with special conditions laid down for the use of radioelements in the determination of wear in refractory walls. (author) [French] Apres avoir discute de la methode radioactive pour l'etude de l'usure des revetements refractaires (description de la methode, avantages et inconvenients, choix de l'indicateur radioactif et detection), l'article traite plus particulierement des problemes de securite intervenant dans cette application. Les deux points les plus importants discutes dans ce rapport sont: 1- la necessite de fixer l'activite limite de la fonte et les auteurs proposent ici le chiffre de 1 mc de cobalt 60 dans 500 tonnes de fonte; 2- les remedes a apporter a la diffusion du cobalt 60 dans la maconnerie (realisation de sources speciales en pyrocerame). Apres avoir examine le point de vue international sur l'utilisation de la methode, l'article decrit brievement quelques realisations francaises en etudiant plus particulierement le cas d'un haut-fourneau. En annexe, se trouve une note de la Commission interministerielle des Radio-elements traitant des conditions particulieres d'emploi des radio

  3. Isolement et identification des levures.

    Directory of Open Access Journals (Sweden)

    S. DOMERCQ

    1967-06-01

    Full Text Available La fermentation du moût de raisin est assurée par les levures qui se trouvent sur la pellicule du raisin, sur les rafles, et aussi, par celles qui envahissent le matériel de vendange et de vinification dès que la récolte est commencée. L'apparition deLa fermentation du moût de raisin est assurée par les levures qui se trouvent sur la pellicule du raisin, sur les rafles, et aussi, par celles qui envahissent le matériel de vendange et de vinification dès que la récolte est commencée. L'apparition des signes de la fermentation est spontanée. La fermentation est rapide dans la majorité des cas, si elle devient trop violente et que la température s'élève dangeureusement, il faut la « canaliser », la calmer. Des accidents peuvent se produire; des arrêts de fermentation laissant des sucres non fermentés pouvant être attaqués par d'autres microorganismes, des développements de levures formant des substances nuisibles à la qualité; par la suite, il s'agit d'obtenir la stabilité du vin, en particulier, éviter les refermentations des vins doux. L'étude de ces problèmes nécessite une étude préliminaire, celle des levures responsables de la fermentation alcoolique du jus de raisin, qui ne peut être faite que sur des cultures pures, isolées au préalable à l'aide de prélèvements soigneusement réalisés.s signes de la fermentation est spontanée. La fermentation est rapide dans la majorité des cas, si elle devient trop violente et que la température s'élève dangeureusement, il faut la « canaliser », la calmer. Des accidents peuvent se produire; des arrêts de fermentation laissant des sucres non fermentés pouvant être attaqués par d'autres microorganismes, des développements de levures formant des substances nuisibles à la qualité; par la suite, il s'agit d'obtenir la stabilité du vin, en particulier, éviter les refermentations des vins doux. L'étude de ces problèmes nécessite une étude pr

  4. Le Débat des semences

    International Development Research Centre (IDRC) Digital Library (Canada)

    Solutions pour les lois nationales régissant le contrôle des ressources génétiques et des ...... des pouvoirs) qui reconnaissent, dans une certaine mesure, les droits de gestion collectifs des ...... documentés, les performances physiques, etc.

  5. Mécanique des sols et des roches

    CERN Document Server

    Vullier, Laurent; Zhao, Jian

    2016-01-01

    La mécanique des sols et la mécanique des roches sont des disciplines généralement traitées séparément dans la littérature. Pour la première fois, un traité réunit ces deux spécialités, en intégrant également les connaissances en lien avec les écoulements souterrains et les transferts thermiques. A la fois théorique et pratique, cet ouvrage propose tout d'abord une description détaillée de la nature et de la composition des sols et des roches, puis s'attache à la modélisation de problèmes aux conditions limites et présente les essais permettant de caractériser les sols et les roches, tant d'un point de vue mécanique qu'hydraulique et thermique. La problématique des sols non saturés et des écoulements multiphasiques est également abordée. Une attention particulière est portée aux lois de comportement mécanique et à la détermination de leurs paramètres par des essais in situ et en laboratoire, et l'ouvrage offre également une présentation détaillée des systèmes de classi...

  6. Chirurgie des grassmanniennes

    CERN Document Server

    Lafforgue, Laurent

    2003-01-01

    Les compactifications diverses de variétés de modules sont un thème important et récurrent des mathématiques modernes, et elles connaissent un grand nombre d'applications. Ce livre traite le cas de cellules de Schubert minces, qui sont de sous-variétés naturelles de grassmanniennes. L'auteur a été amené à traiter ces questions par un cas particulier lié à ses travaux sur le programme de Langlands. Dans cette monographie, il en développe une théorie plus systématique, présentant le fortes similarités avec celle des modules du courbes stables. The various compactifications of moduli spaces are an important recurrent theme of modern mathematics, and they have a large number of applications. This book treats the case of thin Schubert varieties, which are natural subvarieties of Grassmannians. The author was led to these questions by a particular case linked to his work on the Langlands program. In this monograph, he develops the theory in a more systematic way, which exhibits strong similarities...

  7. Comportement des polluants des eaux pluviales urbaines en ...

    African Journals Online (AJOL)

    développement et la croissance des organismes vivant dans l'eau et particulièrement les micro- organismes. Le suivi des températures enregistrées oscille entre 9 et 16°C dans les trois sites d'observation durant la période ... de la lumière du soleil. Le site C est bien aéré et .... Effets de différents modes de gestion des eaux ...

  8. The fate of chylomicron cholesterol in the rat. 1. research into the storing of chylomicrons (1961); Destinee du cholesterol des chylomicrons chez le rat. 1. recherches sur le stockage des chylomicrons (1961)

    Energy Technology Data Exchange (ETDEWEB)

    Chevallier, F; Maurice, J P [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1961-07-01

    Rats conditioned to take their dally meal between midnight and 2 a.