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Sample records for une surface radioactive

  1. Decontamination process and device of a radioactive surface with a coherent light beam. Procede et installation de decontamination d'une surface radioactive au moyen d'un faisceau de lumiere coherente

    Energy Technology Data Exchange (ETDEWEB)

    Gauchon, J.P.; Bournot, P.; Caminat, P.; Dupont, A.

    1994-07-29

    To decontaminate a radioactive surface, this one is swept with a focused laser beam and a liquid such as water or preferably a nitric acid solution on the whole surface. The liquid may be a film running on the surface and is recycled advantageously. The resulting decontamination is very efficient. 6 refs., 2 figs., 5 tabs.

  2. Radioactive surface contamination monitors

    International Nuclear Information System (INIS)

    Aoyama, Kei; Minagoshi, Atsushi; Hasegawa, Toru

    1994-01-01

    To reduce radiation exposure and prevent contamination from spreading, each nuclear power plant has established a radiation controlled area. People and articles out of the controlled area are checked for the surface contamination of radioactive materials with surface contamination monitors. Fuji Electric has repeatedly improved these monitors on the basis of user's needs. This paper outlines typical of a surface contamination monitor, a personal surface contamination monitor, an article surface contamination monitor and a laundry monitor, and the whole-body counter of an internal contamination monitor. (author)

  3. Role of surfactants and/or polymers on the properties of new gels for decontaminating a radioactive surface; Role des molecules tensioactives et/ou des polymeres sur les proprietes de nouveaux gels pour decontaminer une surface radioactive

    Energy Technology Data Exchange (ETDEWEB)

    Bousquet, C. [Cogema 30 - Marcoule (France)]|[Montpellier-2 Univ., 34 (France)]|[CEA Valrho, Lab. des Procedes Avances de Decontamination (LPAD), 30 - Marcoule (France)

    2006-07-01

    In the framework of the dismantling and drainage of nuclear facilities, the LPAD (Marcoule) develops new decontamination processes such as 'suckable' gels. The principle of the 'suckable' gels process consists in pulverizing a gel on a vertical, horizontal or elbow surface. During its contact time with the wall, the gel corrodes the surface on its first microns. The gel dries, fractures and forms dried solid residues. These residues have fixed the contamination and will be easily removed of the surface by brushing and/or sucking-up. This new process uses few matter and do not require rinsing (no liquid effluent). With this process, it is then possible to reduce the volume of wastes produced during the decontamination step. (O.M.)

  4. 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

  5. Decontamination of radioactively contaminated surfaces

    International Nuclear Information System (INIS)

    1986-10-01

    By this standard objective conditions to evaluate and test the ease of decontamination of surfaces under laboratory conditions are to be laid down. Ease of decontamination in this context denotes the summed-up effect of two material properties: a) the capacity of the material for retaining radioactive substances at its surface; b) the ease with which these substances are given off again in the course of cleaning processes. (orig./HP) [de

  6. Radioactive Probes on Ferromagnetic Surfaces

    CERN Multimedia

    2002-01-01

    On the (broad) basis of our studies of nonmagnetic radioactive probe atoms on magnetic surfaces and at interfaces, we propose to investigate the magnetic interaction of magnetic probe atoms with their immediate environment, in particular of rare earth (RE) elements positioned on and in ferromagnetic surfaces. The preparation and analysis of the structural properties of such samples will be performed in the UHV chamber HYDRA at the HMI/Berlin. For the investigations of the magnetic properties of RE atoms on surfaces Perturbed Angular Correlation (PAC) measurements and Mössbauer Spectroscopy (MS) in the UHV chamber ASPIC (Apparatus for Surface Physics and Interfaces at CERN) are proposed.

  7. Radioactive Ions for Surface Characterization

    CERN Multimedia

    2002-01-01

    The collaboration has completed a set of pilot experiments with the aim to develop techniques for using radioactive nuclei in surface physics. The first result was a method for thermal deposition of isolated atoms (Cd, In, Rb) on clean metallic surfaces. \\\\ \\\\ Then the diffusion history of deposited Cd and In atoms on two model surfaces, Mo(110) and Pd(111), was followed through the electric field gradients (efg) acting at the probe nuclei as measured with the Perturbed Angular Correlation technique. For Mo(110) a rather simple history of the adatoms was inferred from the experiments: Atoms initially landing at terrace sites diffuse from there to ledges and then to kinks, defects always present at real surfaces. The next stage is desorption from the surface. For Pd a scenario that goes still further was found. Following the kink stage the adatoms get incorporated into ledges and finally into the top surface layer. For all these five sites the efg's could be measured.\\\\ \\\\ In preparation for a further series o...

  8. The control of the radioactive pollution of milk (1962); Comment concevoir une surveillance des pollutions radioactives du lait (1962)

    Energy Technology Data Exchange (ETDEWEB)

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

    1962-07-01

    Milk, an essential foodstuff, is the object of a supervision and vigilant controls governed by numerous laws which protect its commercial and sanitary qualities. The development of the use of nuclear energy poses and will pose new problems of hygiene and the milk should benefit from controls concerning its possible contamination. Grass-eating animals are particularly subjected to radioactive contaminations and the milk which they produce does not escape contamination because of of its saline composition and of the particular metabolism of the mammary gland. As a result, milk is a contamination integrator and its analysis makes it possible to detect radioelements which can only be detected with great difficulty in an average size plant sample. (author) [French] Le lait, aliment essentiel, fait l'objet d'une surveillance et de controles vigilants regis par de nombreux textes legislatifs qui protegent ses qualites marchandes et sanitaires. Le developpement de l'utilisation de l'energie nucleaire pose et posera de nouveaux problemes d'hygiene et le lait doit beneficier de controles portant sur sa pollution radioactive eventuelle. Les, animaux herbivores sont particulierement exposes aux contaminations radioactives et les laits qu'ils produisent, du fait de leurs compositions salines et du metabolisme particulier de la glande mammaire, n'echappent point aux pollutions. De ce fait, le lait est un integrateur de contamination et son analyse permet de retrouver des radioelements que l'on ne decele qu'avec beaucoup de difficultes sur un echantillon vegetal de taille moyenne. (auteur)

  9. Surface deposition from radioactive plumes

    International Nuclear Information System (INIS)

    Garland, J.A.

    1980-01-01

    Accidents involving nuclear plants may release radioactive particles and gases to the atmosphere. Dry deposition of particles has been investigated mainly in the laboratory and a general understanding of the transfer mechanisms has been established. However there is apparently a substantial discrepancy between the few field observations of dry deposition of particles and laboratory measurements, particularly for 0.1 - 1 μm particles for which laboratory work shows very small deposition rates. In addition there are few estimates of deposition rates for forest and some other kinds of terrain. The most important gas in the context of a nuclear accident is I-131 and the behaviour of this gas at grass surfaces has received much attention. However smaller quantities of other gases and vapours may be released and the surface absorption of these species may require further investigation. In addition there is little knowledge of the behaviour of gases over many types of surface. The rate of deposition of particles and gases is influenced by many parameters including wind speed and the temperature stratification of the lower atmosphere. Conditions which give poor atmospheric dispersion usually give lower deposition velocities. Transfer to man depends on the availability of deposited materials on crops and grass. A wide range of isotopes including iodine and several metallic fission products are lost with a half life for residence on grass ranging from a few days to a few tens days, depending on climatic conditions

  10. The control of the radioactive pollution of milk (1962); Comment concevoir une surveillance des pollutions radioactives du lait (1962)

    Energy Technology Data Exchange (ETDEWEB)

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

    1962-07-01

    Milk, an essential foodstuff, is the object of a supervision and vigilant controls governed by numerous laws which protect its commercial and sanitary qualities. The development of the use of nuclear energy poses and will pose new problems of hygiene and the milk should benefit from controls concerning its possible contamination. Grass-eating animals are particularly subjected to radioactive contaminations and the milk which they produce does not escape contamination because of of its saline composition and of the particular metabolism of the mammary gland. As a result, milk is a contamination integrator and its analysis makes it possible to detect radioelements which can only be detected with great difficulty in an average size plant sample. (author) [French] Le lait, aliment essentiel, fait l'objet d'une surveillance et de controles vigilants regis par de nombreux textes legislatifs qui protegent ses qualites marchandes et sanitaires. Le developpement de l'utilisation de l'energie nucleaire pose et posera de nouveaux problemes d'hygiene et le lait doit beneficier de controles portant sur sa pollution radioactive eventuelle. Les, animaux herbivores sont particulierement exposes aux contaminations radioactives et les laits qu'ils produisent, du fait de leurs compositions salines et du metabolisme particulier de la glande mammaire, n'echappent point aux pollutions. De ce fait, le lait est un integrateur de contamination et son analyse permet de retrouver des radioelements que l'on ne decele qu'avec beaucoup de difficultes sur un echantillon vegetal de taille moyenne. (auteur)

  11. Process for cleaning radioactively contaminated metal surfaces

    International Nuclear Information System (INIS)

    Mihram, R.G.; Snyder, G.A.

    1975-01-01

    A process is described for removing radioactive scale from a ferrous metal surface, including the steps of initially preconditioning the surface by contacting it with an oxidizing solution (such as an aqueous solution of an alkali metal permanganate or hydrogen peroxide), then, after removal or decomposition of the oxidizing solution, the metallic surface is contacted with a cleaning solution which is a mixture of a mineral acid and a complexing agent (such as sulfuric acid and oxalic acid), and which preferably contains a corrosion inhibitor. A final step in the process is the treatment of the spent cleaning solution containing radioactive waste materials in solution by adding a reagent selected from the group consisting of calcium hydroxide or potassium permanganate and an alkali metal hydroxide to thereby form easily recovered metallic compounds containing substantially all of the dissolved metals and radioactivity. (auth)

  12. 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)

  13. 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)

  14. Development of radioactive surface contamination monitor

    International Nuclear Information System (INIS)

    Hashimoto, Tadao; Hasegawa, Toru; Fukumoto, Keisuke; Ooki, Yasushi

    2008-01-01

    In the radiation facilities such as nuclear power plants, surface contamination of the people accessing or articles conveyed in and out of the radiation controlled areas is detected and monitored by installing contamination monitors at the boundary of controlled areas and uncontrolled areas against the expansion of the radioactive materials to out of the facilities. It is required for the surface contamination of articles to be tightened of control criteria as 'Guidelines for discrimination ways of nonradioactive waste (not classified as radioactive waste) generated from nuclear power plants' (hereinafter referred to as 'the Guideline') was established by the Nuclear and Industrial Safety Agency of the Ministry of Economy, Trade and Industry in August, 2005. It predicts that the control criteria of monitors other than article monitors are also tightened in the future. Fuji electric has been fabricating and delivering surface contamination detecting monitors. Now we are developing the new contamination monitor corresponding to the tightening of the control criteria. 'Large article transfer monitor', 'Clothing monitor' and 'Body surface contamination monitor' are introduced in this article. (author)

  15. Radioactivity in surface waters and its effects

    International Nuclear Information System (INIS)

    Stoeber, I.

    1987-01-01

    In consequence of the reactor accident in Chernobyl, the State Office for Water and Waste Disposal of North-Rhine Westphalia implemented immediate programmes for monitoring radioactivity in surface waters, including their sediments and organisms. Of the initially-measured radionuclides, only cesium-137, with its long half-life of 30 years, is of interest. Only trace amounts of the almost equally long-lived strontium 90 (half-life 28 years) were present in rainfall. Cs-137 is a non-natural-radionuclide, occurring solely as a by-product of nuclear installations and atomic bomb tests. Following the ban on surface testing of nuclear weapons, the Cs-137 content of surface waters had fallen significantly up to April 1986. The load due to the reactor disaster is of the same order of magnitude as that produced by atomic testing at the end of the nineteen-sixties. The paper surveys radioactive pollution of surface waters in North-Rhine Westphalia and its effects on water use, especially in regard to potable water supplies and the fish population. (orig./HSCH) [de

  16. Condensation En Film Liquidesur Une Surface Verticale Bordant Un ...

    African Journals Online (AJOL)

    This study aims to obtain the necessary information for the characterization and the precision of the dynamics of the condensation phenomenon in order to ... show the effect of the permeability porous medium and inclination of the principal axes on the liquid film thickness, liquid mass flow rate and surface heat transfer rate.

  17. Development of an application simulating radioactive sources; Conception d'une application de simulation de sources radioactives

    Energy Technology Data Exchange (ETDEWEB)

    Riffault, V.; Locoge, N. [Ecole des Mines de Douai, Dept. Chimie et Environnement, 59 - Douai (France); Leblanc, E.; Vermeulen, M. [Ecole des Mines de Douai, 59 (France)

    2011-05-15

    This paper presents an application simulating radioactive gamma sources developed in the 'Ecole des Mines' of Douai (France). It generates raw counting data as an XML file which can then be statistically exploited to illustrate the various concepts of radioactivity (exponential decay law, isotropy of the radiation, attenuation of radiation in matter). The application, with a spread sheet for data analysis and lab procedures, has been released under free license. (authors)

  18. Surface and Interface Studies with Radioactive Ions

    CERN Multimedia

    Weber, A

    2002-01-01

    Investigations on the atomic scale of magnetic surfaces and magnetic multilayers were performed by Perturbed Angular Correlation (PAC) spectroscopy. The unique combination of the Booster ISOLDE facility equipped with a UHV beamline and the UHV chamber ASPIC (Apparatus for Surface Physics and Interfaces at CERN) is ideally suited for such microscopic studies. Main advantages are the choice of problem-oriented radioactive probes and the purity of mass-separated beams. The following results were obtained: $\\,$i) Magnetic hyperfine fields (B$_{hf}$) of Se on Fe, Co, Ni surfaces were determined. The results prompted a theoretical study on the B$_{hf}$ values of the 4sp-elements in adatom position on Ni and Fe, confirming our results and predicting unexpected behaviour for the other elements. $\\,$ii) Exemplarily we have determined B$_{hf}$ values of $^{111}$Cd at many different adsorption sites on Ni surfaces. We found a strong dependence on the coordination number of the probes. With decreasing coordination nu...

  19. Surface temperature measurement with radioactive kryptonates

    International Nuclear Information System (INIS)

    Pruzinec, J.; Piatrik, M.

    1976-01-01

    The preparation and use of radioactive kryptonates is described for measuring surface temperatures within the region of 45 to 70 degC. Two samples each were prepared of kryptonated beechwood and hydroquinone on a paper carrier. One sample served as the standard which during the experiment was placed in a thermostat at a constant temperature of 45 degC. The second sample was placed in another thermostat where the temperature changed from 45 to 70 degC. Both samples were in the thermostat for 30 mins. The temperature was raised in steps of 2.5 degC and the time of measurement was constant in both samples. The dependences are given of the drop in activity on temperature for both types of samples. The difference was determined of the drop in activity between the standard and the second sample and the relation for measuring the temperature of the sample was determined therefrom. (J.B.)

  20. Radioactivity Measurements on Glazed Ceramic Surfaces

    OpenAIRE

    Hobbs, Thomas G.

    2000-01-01

    A variety of commonly available household and industrial ceramic items and some specialty glass materials were assayed by alpha pulse counting and ion chamber voltage measurements for radioactivity concentrations. Identification of radionuclides in some of the items was performed by gamma spectroscopy. The samples included tableware, construction tiles and decorative tiles, figurines, and other products with a clay based composition. The concentrations of radioactivity ranged from near backgr...

  1. Hydrogeological aspects of radioactive waste disposal into surface formations

    International Nuclear Information System (INIS)

    Dlouhy, Z.

    1980-01-01

    Safe disposal is discussed of radioactive wastes in geological surface formations and basic criteria are shown of the radiological protection of population from possible effects of radioactive materials diffused in the environment. Main principles are listed governing the selection of suitable localities with respect to possible interactions of the locality and the storage site with the environment. (author)

  2. Radioactivity Measurements on Glazed Ceramic Surfaces.

    Science.gov (United States)

    Hobbs, T G

    2000-01-01

    A variety of commonly available household and industrial ceramic items and some specialty glass materials were assayed by alpha pulse counting and ion chamber voltage measurements for radioactivity concentrations. Identification of radionuclides in some of the items was performed by gamma spectroscopy. The samples included tableware, construction tiles and decorative tiles, figurines, and other products with a clay based composition. The concentrations of radioactivity ranged from near background to about four orders of magnitude higher. Almost every nuclide identification test demonstrated some radioactivity content from one or more of the naturally occurring radionuclide series of thorium or uranium. The glazes seemed to contribute most of the activity, although a sample of unglazed pottery greenware showed some activity. Samples of glazing paints and samples of deliberately doped glass from the World War II era were included in the test, as was a section of foam filled poster board. A glass disc with known (232)Th radioactivity concentration was cast for use as a calibration source. The results from the two assay methods are compared, and a projection of sensitivity from larger electret ion chamber devices is presented.

  3. 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.

  4. Radioactivity levels in surface water of lakes around Izmir / Turkey

    International Nuclear Information System (INIS)

    Doyurum, S.; Turkozu, D. A.; Aslani, M. A. A.; Aytas, S.; Eral, M.; Kaygun, A. K.

    2006-01-01

    Radioactivity presents in surface continental waters is mainly due to the presence of radioactive elements in the earth's crust, other artificial radionuclides have appeared due to such human activities as nuclear power plants, nuclear weapons testing and manufacture and use of radioactive sources It is well known that natural radionuclides can be effective as tracers for the different processes controlling the distribution of elements among dissolved and particulate phases in aquatic systems. The detection of high radionuclide concentrations was proposed as a public health problem in several areas and consequently studies into the risks of radionuclides were started in the 2000s. Especially, these radioactive substances in groundwater are an unwanted and involuntary risk factor from natural sources, not artificial sources. These radioactive substances include uranium, radon found in uranium series, and other radioactive substances such as radium and gross alpha. Uranium present in rock, soil, and natural materials, and is found in small quantities in air, water, and food that people always contact. In this project, lake water samples were collected from three lakes around Izmir-Turkey. In surface lake water samples, pH, mV and conductivity values were measured and alkaline content was determined titrimetrically. The uranium concentrations in the lake water samples were measured using uranium analyzer. The radioactivity concentrations related to gross radium isotopes, gross-? and gross-? activities in the surface lake water were determined. The correlation among some parameters for water samples and concentrations of uranium, activity concentration of gross radium isotopes, gross alpha and gross beta radioactivity are also discussed

  5. Bonding of radioactive contamination. IV. Effect of surface finish

    International Nuclear Information System (INIS)

    Rankin, W.N.

    1983-01-01

    The mechanisms by which radioactive contamination would be bonded to a DWPF canister are being investigated. Previous investigations in this series have examined the effects of temperature, oxidation before contamination, and atmosphere composition control on the bonding of contamination. This memorandum describes the results of tests to determine the effect of special surface finishes on the bonding of contamination to waste glass canisters. Surface pretreatments which produce smoother canister surfaces actually cause radioactive contamination to be more tightly bonded to the metal surface than on an untreated surface. Based on the results of these tests it is recommended that the canister surface finish be specified as having a bright cold rolled mill finish equivalent to ASTM No. 2B. 7 references, 3 figures, 3 tables

  6. Laser techniques for radioactive decontamination gives metallic surfaces

    International Nuclear Information System (INIS)

    Escobar Alracon, L.; Molina, G.; Vizuet Gonzalez, J.

    1998-01-01

    In this work it presented the prototype for system decontamination at diverse component with removable superficial contamination, using the technique gives laser ablation, for the evaporation at the pollutant. It discusses the principle in the fact that system, as well as the different elements that compose it. The are presented the obtained results when irradiating with a laser a surface without radioactive contamination to verify the system operation

  7. 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

  8. A project for storing the radioactive sludges from Marcoule in the soil (1960); Une solution de stockage dans le sol des boues radioactives de Marcoule (1960)

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

    A study of the feasibility of storing radioactive sludges in the soil. Special attention is paid to the case of the Marcoule plant, producing three kinds of sludges. The movement of the different fission products is given. (author) [French] Etude de la possibilite de stocker dans le sol des boues radioactives. Le cas de la station de traitement des effluents de Marcoule, produisant trois types de boues, est etudie plus specialement. Le mouvement des divers produits de fission est precise. (auteur)

  9. Decontamination of radioactive metal surfaces by plasma arc gouging

    International Nuclear Information System (INIS)

    Osamu, K.; Makoto, K.; Takao, K.

    1983-01-01

    Experiments have been carried out to develop a new decontamination method that applies plasma arc gouging for removal of a thin surface layer from radioactively contaminated metallic wastes. Plasma arc gouging has been carried out on stainless steel and carbon steel pipes. The torch nozzle and gouging angle have been optimized to increase the decontamination rate. A water film is formed on the pipe surface to reduce both dust concentration in the off-gas and prevent slag particles, which are splashed up by the plasma gas, from adhering to the gouged surface. Using chromium-electroplated carbon steel pipes as samples, a decontamination factor of >10 3 is obtained after gouging to a depth of about0.5 mm in combination with ultrasonic cleaning

  10. 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.)

  11. Road surface washing system for decontaminating radioactive substances. Experiment of radioactive decontamination

    International Nuclear Information System (INIS)

    Endo, Mitsuru; Endo, Mai; Kakizaki, Takao

    2015-01-01

    The Great East Japan Earthquake that occurred on March 11, 2011 resulted in the explosion of the TEPCO Fukushima 1st Nuclear Power Plant and the global dispersion of a large quantity of radioactive substances. A high radiation dose was particularly recorded in Fukushima prefecture several weeks after the accident, although the level is presently sufficiently low. However, considering that the adverse effects of low but extended exposure to radiation are yet to be negated, there is the urgent need for further decontamination. In our study, we focused on the efficient decontamination of radioactive substances in residential areas, for which we propose a high-pressure water jet system for washing road surfaces. The system differs from conventional systems of its type that were initially designed for use in the immediate environment of the nuclear reactors of the TEPCO Fukushima 1st Nuclear Power Plant. The proposed system consists of multiple washing, transporter, and server robots. The washing robots decontaminate the road surface using high-pressure water jets and are transported between washed and unwashed areas by the transporter robots. The server robots supply the water used for washing and absorb the polluted water together with ground dust. In this paper, we describe the concept of the system and present the results of decontamination experiments. Particular attention is given to the washing robot and its mechanism and control method. The results of the integration of the washing robot in an experimental system confirmed the feasibility of the proposed system. (author)

  12. Regionalized study of the impact of an accidental radioactive pollution on a permanent meadow; Etude regionalisee de l'impact d'une pollution radioactive accidentelle sur une prairie permanente

    Energy Technology Data Exchange (ETDEWEB)

    Durand, V.; Mercat-Rommens, C

    2006-07-01

    The objective of this study consists in evaluating the sensitivity of the first part of the die grass-milk with respect to an accidental radioactive discharge. We want to know if a single uniform deposit would involve a contamination of the grazing grass identical on the scale of the own territory. The study was based on the A.S.T.R.A.L. model, a computer code developed by the I.R.S.N. which makes it possible to evaluate the transfer of the radionuclides in the terrestrial food chain following an accidental atmospheric emission. The way of transfer of A.S.T.R.A.L. on which the study focused is the transfer of the deposit to milk, via the grazing grass ingestion. The sensitivity of this way of transfer relies on several parameters: captation, yield, cows food rates and dates of setting to grass. Methodology thus consisted in regionalizing these parameters. The software S.T.I.C.S. developed by the I.N.R.A. of Avignon was then used. This model proposes a daily follow-up of the leaf area index which has been correlated with captation and with the production of fresh biomass (yield). (authors)

  13. Sensitivity and rapidity of the evaporation method for the measurement of the radioactivity of residual water; Sensibilite et rapidite de la methode d'evaporation pour la mesure de la radioactivite d'une eau residuaire

    Energy Technology Data Exchange (ETDEWEB)

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

    1958-07-01

    The authors have used the evaporation method for counting the radioactivity of water polluted to the tolerance limit by Sr{sup 90}. Total duration of the manipulation is 2 hours. (author) [French] Les auteurs ont utilise la methode d'evaporation pour le comptage de la radioactivite d'une eau polluee, a la limite de tolerance, par du {sup 90}Sr. La duree de la manipulation totale est de 2 h. (auteur)

  14. Analysis on the influence of forest soil characteristics on radioactive Cs infiltration and evaluation of residual radioactive Cs on surfaces.

    Science.gov (United States)

    Mori, Yoshitomo; Yoneda, Minoru; Shimada, Yoko; Fukutani, Satoshi; Ikegami, Maiko; Shimomura, Ryohei

    2018-03-29

    We investigated the depth profiles of radioactive Cs, ignition loss, and cation exchange capacity (CEC) in five types of forest soils sampled using scraper plates. We then simulated the monitored depth profiles in a compartment model, taking ignition loss as a parameter based on experimental results showing a positive correlation between ignition loss and the CEC. The calculated values were comparable with the monitored values, though some discrepancy was observed in the middle of the soil layer. Based on decontamination data on the surface dose rate and surface contamination concentration, we newly defined a surface residual index (SRI) to evaluate the residual radioactive Cs on surfaces. The SRI value tended to gradually decrease in forests and unpaved roads and was much smaller in forests and on unpaved roads than on paved roads. The radioactive Cs was assumed to have already infiltrated underground 18 months after the nuclear power plant accident, and the sinking was assumed to be ongoing. The SRI values measured on paved roads suggested that radioactive Cs remained on the surfaces, though a gradual infiltration was observed towards the end of the monitoring term. The SRI value is thought to be effective in grasping the rough condition of residual radioactive Cs quickly at sites of decontamination activity in the field. The SRI value may be serviceable for actual contamination works after further research is done to elucidate points such as the relation between the SRI and the infiltration of radioactive Cs in various types of objects.

  15. Influence of radioactivity on surface charging and aggregation kinetics of particles in the atmosphere.

    Science.gov (United States)

    Kim, Yong-Ha; Yiacoumi, Sotira; Lee, Ida; McFarlane, Joanna; Tsouris, Costas

    2014-01-01

    Radioactivity can influence surface interactions, but its effects on particle aggregation kinetics have not been included in transport modeling of radioactive particles. In this research, experimental and theoretical studies have been performed to investigate the influence of radioactivity on surface charging and aggregation kinetics of radioactive particles in the atmosphere. Radioactivity-induced charging mechanisms have been investigated at the microscopic level, and heterogeneous surface potential caused by radioactivity is reported. The radioactivity-induced surface charging is highly influenced by several parameters, such as rate and type of radioactive decay. A population balance model, including interparticle forces, has been employed to study the effects of radioactivity on particle aggregation kinetics in air. It has been found that radioactivity can hinder aggregation of particles because of similar surface charging caused by the decay process. Experimental and theoretical studies provide useful insights into the understanding of transport characteristics of radioactive particles emitted from severe nuclear events, such as the recent accident of Fukushima or deliberate explosions of radiological devices.

  16. Natural radioactivity assessment of surface sediments in the Yangtze Estuary

    International Nuclear Information System (INIS)

    Wang, Jinlong; Du, Jinzhou; Bi, Qianqian

    2017-01-01

    The activities of the natural radionuclides ( 238 U, 232 Th, 226 Ra and 40 K) of the surface sediments in the Yangtze Estuary were determined and used to evaluate radiation hazards in the study area. The of activities of 238 U, 232 Th, 226 Ra and 40 K ranges from 14.1 to 62.3, 26.1 to 71.9, 13.7 to 52.3, and 392 to 898 Bq kg −1 , respectively, which were comparable to values of other regions in China. The activities of 232 Th, 40 K and 226 Ra were clearly different from the global recommended values. The radium equivalent activity was less than the recommended limit of 370 Bq kg −1 ; therefore, the sediment in this area can be safely used for reclamation. The external hazard index values were less than one. The average absorbed gamma dose rate and annual effective dose equivalent values were slightly greater than the world average value. 226 Ra/ 238 U and 232 Th/ 238 U ratios could potentially be applied for tracing sediment source. - Highlights: • The natural radioactivity of surface sediments in the Yangtze Estuary was observed. • The radiological hazards of the sediments are insignificant in this study area. • The ratios of natural radionuclides can potentially be applied for sediment source.

  17. Enlargement of the Baldone near-surface radioactive waste repository

    International Nuclear Information System (INIS)

    Dreimanis, A.

    2007-01-01

    A unified analysis of the enlargement of the Baldone near-surface radioactive waste (RW) repository RADONS considers the interplay of the existing engineering, safety and infrastructure premises, with the foreseen newly socio-technical features. This enlargement consists in construction of two additional RW disposal vaults and in building a long-term storage facility for spent sealed sources at the RADONS territory. Our approach is based on consecutive analysis of following basic elements: - the origin of enlargement - the RADONS safety analysis and a set of optimal socio-technical solutions of Salaspils research reactor decommissioning waste management; - the enlargement - a keystone of the national RW management concept, including the long-term approach; - the enlargement concept - the result of international co-operation and obligations; - arrangement optimization of new disposal and storage space; - environmental impact assessment for the repository enlargement - the update of socio-technical studies. The study of the public opinion revealed: negative attitude to repository enlargement is caused mainly due to missing information on radiation level and on the RADONS previous operations. These results indicate: basic measures to improve the public attitude to repository enlargement: the safety upgrade, public education and compensation mechanisms. A detailed stakeholders engagement and public education plan is elaborated. (author)

  18. Worker exposures from recycling surface contaminated radioactive scrap metal

    International Nuclear Information System (INIS)

    Kluk, A.; Phillips, J.W.; Culp, J.

    1996-01-01

    Current DOE policy permits release from DOE control of real property with residual levels of surficial radioactive contamination if the contamination is below approved guidelines. If the material contains contamination that is evenly distributed throughout its volume (referred to as volumetric contamination), then Departmental approval for release must be obtained in advance. Several DOE sites presently recycle surface contaminated metal, although the quantities are small relative to the quantities of metal processed by typical mini-mills, hence the potential radiation exposures to mill workers from processing DOE metals and the public from the processed metal are at present also a very small fraction of their potential value. The exposures calculated in this analysis are based on 100% of the scrap metal being processed at the maximum contamination levels and are therefore assumed to be maximum values and not likely to occur in actual practice. This paper examines the relationship between the surface contamination limits established under DOE Order 5400.5, open-quotes Radiation Protection of the Public and the Environment,close quotes and radiation exposures to workers involved in the scrap metal recycling process. The analysis is limited to surficial contamination at or below the guideline levels established in DOE Order 5400.5 at the time of release. Workers involved in the melting and subsequent fabrication of products are not considered radiation workers (no requirements for monitoring) and must be considered members of the public. The majority of the exposures calculated in this analysis range from tenths of a millirem per year (mrem/yr) to less than 5 mrem/yr. The incremental risk of cancer associated with these exposures ranges from 10 -8 cancers per year to 10 -6 cancers per year

  19. Research on near-surface disposal of very low level radioactive waste

    International Nuclear Information System (INIS)

    Wang Shaowei; Yue Huiguo; Hou Jie; Chen Haiying; Zuo Rui; Wang Jinsheng

    2012-01-01

    Radioactive waste disposal is one of the most sensitive environmental problems to control and solve. As the arriving of decommissioning of early period nuclear facilities in China, large amounts of very low level radioactive waste will be produced inevitably. The domestic and abroad definitions about very low level radioactive waste and its disposal were introduced, and then siting principles of near-surface disposal of very low level radioactive waste were discussed. The near- surface disposal siting methods of very low level radioactive waste were analyzed from natural and geographical conditions assessment, geological conditions analysis, hydrogeological conditions analysis, geological hazard assessment and radioactive background investigation; the near-surface disposal sites'natural barriers of very low level radioactive waste were analyzed from the crustal structure and physico-chemical characteristics, the dynamics characteristics of groundwater, the radionuclide adsorption characteristics of natural barriers and so on; the near-surface disposal sites' engineered barriers of very low level radioactive waste were analyzed from the repository design, the repository barrier materials selection and so on. Finally, the improving direction of very low level radioactive waste disposal was proposed. (authors)

  20. Decontamination and radioactivity measurement on building surfaces related to dismantling of Japan power demonstration reactor (JPDR)

    International Nuclear Information System (INIS)

    Hatakeyama, Mutsuo; Tachibana, Mitsuo; Yanagihara, Satoshi

    1997-12-01

    In the final stage of dismantling activities for decommissioning a nuclear power plant, building structures have to be demolished to release the site for unrestricted use. Since building structures are generally made from massive reinforced concrete materials, it is not a rational way to treat all concrete materials arising from its demolition as radioactive waste. Segregation of radioactive parts from building structures is therefore indispensable. The rational procedures were studied for demolition of building structures by treating arising waste as non-radioactive materials, based on the concept established by Nuclear Safety Commission, then these were implemented in the following way by the JPDR dismantling demonstration project. Areas of the JPDR facilities are categorized into two groups : possibly contaminated areas, and possibly non-contaminated areas, based on the document of the reactor operation. Radioactivity on the building surfaces was then measured to confirm that the qualitative categorization is reasonable. After that, building surfaces were decontaminated in such a way that the contaminated layers were removed with enough margin to separate radioactive parts from non-radioactive building structures. Thought it might be possible to demolish the building structures by treating arising waste as non-radioactive materials, confirmation survey for radioactivity was conducted to show that there is no artificial radioactive nuclides produced by operation in the facility. This report describes the procedures studied on measurement of radioactivity and decontamination, and the results of its implementation in the JPDR dismantling demonstration project. (author)

  1. Levels of surface contamination with radioactive materials at workplaces of nuclear research centre at Rez

    International Nuclear Information System (INIS)

    Hoelgye, Z.; Nemcova, I.; Kasikova, M.; Popper, J.; Chysky, J.

    1983-01-01

    A hygiene supervision unit at workplaces of the nuclear Research Institute in Rez monitored on a long-term basis surface contamination with radioactive substances. Surface contamination was found at workplaces with open sources. Of the 4343 monitored places action levels were only exceeded in 13 cases. The obtained data were used for typifying workplaces with the highest level of surface contamination, to determine in certain instances the mechanism of the escape of radioactive substances from insulating facilities and to determine the rate of the spread of the radioactive substance into adjacent non-active workplaces. (author)

  2. Radioactivity

    International Nuclear Information System (INIS)

    Chelet, Y.

    2006-01-01

    The beginning of this book explains the why and how of the radioactivity, with a presentation of the different modes of disintegration. Are tackled the reports between radioactivity and time before explaining how the mass-energy equivalence appears during disintegrations. Two chapters treat natural radioisotopes and artificial ones. This book makes an important part to the use of radioisotopes in medicine (scintigraphy, radiotherapy), in archaeology and earth sciences (dating) before giving an inventory of radioactive products that form in the nuclear power plants. (N.C.)

  3. Radioactivity

    International Nuclear Information System (INIS)

    2002-01-01

    This pedagogical document presents the origin, effects and uses of radioactivity: where does radioactivity comes from, effects on the body, measurement, protection against radiations, uses in the medical field, in the electric power industry, in the food (ionization, radio-mutagenesis, irradiations) and other industries (radiography, gauges, detectors, irradiations, tracers), and in research activities (dating, preservation of cultural objects). The document ends with some examples of irradiation levels (examples of natural radioactivity, distribution of the various sources of exposure in France). (J.S.)

  4. Seasonal optimisation of panel surfaces in a photovoltaic plant; Optimisation saisonniere de la surface des panneaux dans une installation photovoltaique

    Energy Technology Data Exchange (ETDEWEB)

    Affolter, P.; Keller, L. [Bureau d`Etudes Keller-Burnier, Lavigny (CH)

    1991-02-01

    By carefully calculating the panel surface in a photovoltaic plant connected to the network, energy can be obtained at a minimum cost price. This has been discussed in a survey entitled `Optimisating the surface of photo= voltaic panels according to the static inverter`. This survey does not however describe how the price of energy varies during the year. This gap is filled by the present work which is helping show how to make optimum calculations in winter. Most of the simulations made during the course of the first study have been repeated. This has allowed new elements to be brought in. One example is the importance of the crystalline cell output-temperature characteristic. It is noted that the winter potential of a photovoltaic plant is greater than that of a solar power plant. This study has also facilitated better definition of the behaviour of the plant`s production-surface characteristic. This shows the importance of having a static inverter capable, in the event of intense periods of sunshine, of limiting the energy injected at rated power. Many parametric studies are helping to show the important parameters of this type of plant for the period from October to March. figs., 3 refs.

  5. Radioactive air and surface contamination in Czechia and Slovakia

    International Nuclear Information System (INIS)

    Rumyantsev, V.V.

    1992-01-01

    Data are presented on the radioactive substance effluents into the environment in conditions of NPP normal operation and on the air contamination by 85 Kr due to operation of the European and Soviet plants for reprocessing spent nuclear fuel. Data are given on the dosage of the Czechoslovakia population due to the Chernobyl NPP accident

  6. Radioactivity of some alpha, beta and gamma emitting radionuclides in surface marine sediments of different bays in Algeria

    International Nuclear Information System (INIS)

    Noureddine, A.; Baggoura, B.

    1999-01-01

    Samples of surface (0-15) cm marine sediments of different grain sizes, namely sand, muddy and fine sand, were collected in the western, central and east coast of Algeria, to measure concentrations of natural and artificial radioactivity. The aim of this study is to detect any radioactive contamination, its origin and also to determine the uptake of radioactivity by marine surface sediments

  7. KS 20322007 Near-Surface Disposal Radioactive Waste - Code Of Practice

    International Nuclear Information System (INIS)

    Omondi, C.

    2017-01-01

    To provide a basis for the near-surface disposal of solid radioactive waste to ensures that there is no unacceptable risk to humans, other biota or the environment. Near-Surface Disposal is the disposal of radioactive waste in below or above the natural ground surface, within app. 30 m. The code deals with management aspects associated with radioactive waste disposal only, and is not intended to cover issues related to the production and use of radionuclides. The objective of waste disposal is to isolate radioactive waste in order to ensure that there is no unacceptable health risk to humans and no long-term unacceptable effect to the environment. Radiation protection annual effective dose for exposure of members of the public should not exceed 1 mSv/year and occupational exposure of 20 mSv/year

  8. Lactoperoxidase catalyzed radioiodination of cell surface immunoglobulin: incorporated radioactivity may not reflect relative cell surface Ig density

    International Nuclear Information System (INIS)

    Wilder, R.L.; Yuen, C.C.; Mage, R.G.

    1979-01-01

    Rabbit and mouse splenic lymphocytes were radioiodinated by the lactoperoxidase technique, extracted with non-ionic detergent, immunoprecipitated with high titered rabbit anti-kappa antisera, and compared by SDS-PAGE. Mouse sIg peaks were reproducibly larger in size than rabbit sIg peaks (often greater than 10 times). Neither differences in incorporation of label into the rabbit cell surface, nor differences in average sIg density explain this result. Total TCA-precipitable radioactivity was similar in each species. Estimation of the relative amounts of sIg in the mouse and rabbit showed similar average sIg densities. Differences in detergent solubility, proteolytic lability, or antisera used also do not adequately account for this difference. Thus, these data indicate that radioactivity incorporated after lactoperoxidase catalyzed cell surface radioiodination may not reflect cell surface Ig density. Conclusions about cell surface density based upon relative incorporation of radioactivity should be confirmed by other approaches

  9. Valuating report on radioactivity concentrations in surface waters in 1988

    International Nuclear Information System (INIS)

    Henrich, E.; Weisz, J.; Zapletal, M.; Friedrich, M.; Haider, W.

    1989-02-01

    Sample preparation- and measuring methods and results on river and lake water samples for 1988 are presented. This is part of the Austrian Environment Radioactivity Monitoring Network. 22 sampling sites and 9 nuclides - natural, atomic weapons tests and Chernobyl fallout - were assessed. Emphasis was on the Chernobyl fallout; iodine 131, chromium 51 and cobalt 60. Hypotheses on the origin of the radionuclides are presented. The radiation burden to the population is marginal. 15 refs., 19 figs., 15 tabs. (qui)

  10. Reconstruction de la surface de Fermi dans l'etat normal d'un supraconducteur a haute Tc: Une etude du transport electrique en champ magnetique intense

    Science.gov (United States)

    Le Boeuf, David

    Des mesures de resistance longitudinale et de resistance de Hall en champ magnetique intense transverse (perpendiculaire aux plans CuO2) ont ete effectuees au sein de monocristaux de YBa2Cu3Oy (YBCO) demacles, ordonnes et de grande purete, afin d'etudier l'etat fondamental des supraconducteurs a haute Tc dans le regime sous-dope. Cette etude a ete realisee en fonction du dopage et de l'orientation du courant d'excitation J par rapport a l'axe orthorhombique b de la structure cristalline. Les mesures en champ magnetique intense revelent par suppression de la supraconductivite des oscillations magnetiques des resistances longitudinale et de Hall dans YBa2Cu 3O6.51 et YBa2Cu4O8. La conformite du comportement de ces oscillations quantiques au formalisme de Lifshitz-Kosevich, apporte la preuve de l'existence d'une surface de Fermi fermee a caractere quasi-2D, abritant des quasiparticules coherentes respectant la statistique de Fermi-Dirac, dans la phase pseudogap d'YBCO. La faible frequence des oscillations quantiques, combinee avec l'etude de la partie monotone de la resistance de Hall en fonction de la temperature indique que la surface de Fermi d'YBCO sous-dope comprend une petite poche de Fermi occupee par des porteurs de charge negative. Cette particularite de la surface de Fermi dans le regime sous-dope incompatible avec les calculs de structure de bande est en fort contraste avec la structure electronique presente dans le regime surdope. Cette observation implique ainsi l'existence d'un point critique quantique dans le diagramme de phase d'YBCO, au voisinage duquel la surface de Fermi doit subir une reconstruction induite par l'etablissement d'une brisure de la symetrie de translation du reseau cristallin sous-jacent. Enfin, l'etude en fonction du dopage de la resistance de Hall et de la resistance longitudinale en champ magnetique intense suggere qu'un ordre du type onde de densite (DW) est responsable de la reconstruction de la surface de Fermi. L'analogie de

  11. Radioactivity in the Rhine - the LWA controls North-Rhine-Westphalian surface waters

    International Nuclear Information System (INIS)

    Kloes, H.

    1985-01-01

    The State Authority for Water and Waste Management has been testing the Rhine and the most important surface waters of North-Rhine Westphalia for radioactivity ever since it was founded in 1969. Radiation exposure of human beings who use Rhine water is far below the permitted maximum values of the 'radiation protection ordinance'. Pollution of the Rhine and its tributaries in North-Rhine Westphalia with artificial radioactive substances has even slightly decreased over the past ten years; pollution of the River Emscher with natural radioactive material remained high, the Lippe River now contains less radium than before. (orig./PW) [de

  12. Production of zero energy radioactive beams through extraction across superfluid helium surface

    NARCIS (Netherlands)

    Takahashi, N; Huang, WX; Gloos, K; Dendooven, P; Pekola, JP; Aysto, J

    A radioactive Ra-223 source was immersed in superfluid helium at 1.2-1.7 K. Electric fields transported recoiled Rn-219 ions in the form of snowballs to the surface and further extracted them across the surface. The ions were focussed onto an aluminium foil and alpha particle spectra were taken with

  13. Sodium exchange process in lower vertebrates studies by means of {sup 24}Na. Their interpretation as a 'purification' of radioactive water; Les echanges de sodium des vertebres inferieurs etudies a l'aide du {sup 24}Na. Leur interpretation comme une 'epuration' d'eau radioactive

    Energy Technology Data Exchange (ETDEWEB)

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

    1958-07-01

    Fresh-water fish and amphibians live in an aquatic medium which is very hypotonic with respect to their internal medium. By osmosis the water passes through their permeable teguments (gills, mucous membranes, skin). It is known from the work of Krogh (1937-1939) that this water is eliminated by the kidney, which emits a copious diluted urine. Yet however great the dilution, the urinary excretion results in a loss of salts for the organism. This loss is compensated, even in the absence of any nourishment, by active absorption of ions. Some recent workers have attempted, by using radioactive isotopes, to establish the balance between the input and output flows of ions through the permeable membranes in vivo, whereas chemical analytical methods only allow the net result of these exchanges to be obtained. We have attempted to present here a new method for the simultaneous measurement of the sodium flow takes over the whole animal. This method has been applied to the fresh-water fish Carassius auratus and to the frog Rana esculenta. In the course of this investigation we have considered interpreting it as a 'purification of radioactive water'. (author) [French] Les poissons d'eau douce et les amphibiens vivent dans un milieu aquatique tres hypotonique par rapport a leur milieu interieur. Par osmose, l'eau penetre a travers leurs teguments permeables (branchies, muqueuses, peau). On sait depuis les travaux de Krogh (1937-1939) que cette eau est eliminee par le rein qui emet une urine abondante et diluee. Mais si diluee soit-elle, l'excretion uranaire entraine une perte de sels pour l'organisme. Cette perte est compensee, meme en l'absence de toute alimentation, par une absorption active d'ions. Quelques travaux recents ont tente, grace a l'utilisation des isotopes radioactifs, de dresser le bilan des flux d'entree et de sortie des ions a travers les membranes permeables in vivo, alors que les methodes d'analyse chimique permettent seulement de dresser le bilan net de ces

  14. 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.)

  15. An attemp to use a pulsed CO2 laser for decontamination of radioactive metal surfaces

    OpenAIRE

    MILAN S. TRTICA; SCEPAN S. MILJANIC; NATASA N. STJEPANOVIC

    2000-01-01

    There is a growing interest in laser radioactive decontamination of metal surfaces. It offers advantages over conventional methods: improved safety, reduction of secondary waste, reduced waste volume, acceptable cost. The main mechanism of cleaning by lasers is ablation. A pulsed TEA CO2 laser was used in this work for surface cleaning in order to show that ablation of metal surfaces is possible even at relatively low pulse energies, and to suggest that it could be competitive with other lase...

  16. Radioactivity distribution measurement of various natural material surfaces with imaging plate

    International Nuclear Information System (INIS)

    Mori, C.; Suzuki, T.; Koido, S.; Uritani, A.; Yanagida, K.; Wu, Y.; Nishizawa, K.

    1996-01-01

    Distribution images of natural radioactivity in natural materials such as vegetables were obtained by using Imaging Platc. In ssuch cases, it is necessary to reduce background radiation intensity by one order or more. Graded shielding is very important. Espacially, the innermost surface of a shielding box sshould be covered with acrylic rein plate. We obtained natural radioactivity distribution images of vegetable, sea food, mea etc. Most β-rays emitted from 40 K print the radioactivity distribution image. Comparison between γ-ray intensity of KCL solution measured with HPGe detector and that of natural material specimen gave the radioactivity around 0.06- 0.04Bq/g depending on the kind and the part of specimens. (author). 6 refs., 5 figs., 1 tab

  17. Uptake of radioactivity by marine surface sediments collected in Ghazaouet, west coast of Algeria

    International Nuclear Information System (INIS)

    Noureddine, A.; Baggoura, B.; Hocini, N.; Boulahdid, M.

    1998-01-01

    Samples of surface marine sediments of different grain sizes collected in Ghazaouet, a small bay on the western coast of Algeria, have been examined to measure concentrations of natural and artificial gamma-emitting radionuclides. The aim of this study is to determine the level of radioactivity and its repartition in the sedimentary area. The samples analyzed by direct counting gamma spectrometry, showed relatively high activities for natural radioactivity and revealed measurable quantities of 137 Cs, ranging from 0.66-8.47 Bq kg -1 dry weight. In addition, some of the samples of different nature were sieved in different grain-sizes, to study the uptake of radioactivity. It is found that the sediments of less than 100 μm grain-size have the highest level of uptake of radioactivity

  18. Uptake of radioactivity by marine surface sediments collected in Ghazaouet, west coast of Algeria

    Energy Technology Data Exchange (ETDEWEB)

    Noureddine, A.; Baggoura, B. [Laboratoire d' Environnement, Centre de Radioprotection et de Surete (C.R.S.), Algiers (Algeria); Hocini, N. [Laboratoire de Sedimentologie, Centre de Developpement des Techniques Nucleaires (C.D.T.N.), Algiers (Algeria); Boulahdid, M. [Departement de la Pollution Chimique, Institut des Sciences de la Mer et de l' Amenagement du Littoral, Tipaza (Algeria)

    1998-12-01

    Samples of surface marine sediments of different grain sizes collected in Ghazaouet, a small bay on the western coast of Algeria, have been examined to measure concentrations of natural and artificial gamma-emitting radionuclides. The aim of this study is to determine the level of radioactivity and its repartition in the sedimentary area. The samples analyzed by direct counting gamma spectrometry, showed relatively high activities for natural radioactivity and revealed measurable quantities of {sup 137}Cs, ranging from 0.66-8.47 Bq kg{sup -1} dry weight. In addition, some of the samples of different nature were sieved in different grain-sizes, to study the uptake of radioactivity. It is found that the sediments of less than 100 {mu}m grain-size have the highest level of uptake of radioactivity.

  19. Near-surface facilities for disposal radioactive waste from non-nuclear application

    International Nuclear Information System (INIS)

    Barinov, A.

    2000-01-01

    The design features of the near-surface facilities of 'Radon', an estimation of the possible emergency situations, and the scenarios of their progress are given. The possible safety enhancing during operation of near-surface facilities, so called 'Historical facilities', and newly developed ones are described. The Moscow SIA 'Radon' experience in use of mobile module plants for liquid radioactive waste purification and principal technological scheme of the plant are presented. Upgrading of the technological scheme for treatment and conditioning of radioactive waste for new-developed facilities is shown. The main activities related to management of spent ionizing sources are mentioned

  20. Isopleths of surface air concentration and surface air kerma rate due to a radioactive cloud released from a stack (3)

    International Nuclear Information System (INIS)

    Tachibana, Haruo; Kikuchi, Masamitsu; Sekita, Tsutomu; Yamaguchi, Takenori

    2004-06-01

    This report is a revised edition of 'Isopleths of Surface Air Concentration and Surface Air Absorbed Dose Rate due to a Radioactive Cloud Released from a Stack(II) '(JAERI-M 90-206) and based on the revised Nuclear Safety Guidelines reflected the ICRP1990 Recommendation. Characteristics of this report are the use of Air Karma Rate (Gy/h) instead of Air Absorbed Dose Rate (Gy/h), and the record of isopleths of surface air concentration and surface air karma rate on CD-ROM. These recorded data on CD-ROM can be printed out on paper and/or pasted on digital map by personal computer. (author)

  1. Sources and fate of environmental radioactivity at the earth's surface

    International Nuclear Information System (INIS)

    El-Daoushy, F.

    2010-01-01

    Sources and fate of environmental radioactivity at the earth surface This is to link environmental radioactivity to RP in Africa? To describe the benefits of Africa from this field in terms of RP, safety and security policies. To create a mission and a vision to fulfil the needs of ONE PEOPLE, ONE GOAL, ONE FAITH. Sources, processes and fate of environmental radioactivity Previous experience helps setting up an African agenda.(1) Factors influencing cosmogenic radionuclides(2) Factors influencing artificial radionuclides: (a) nuclear weapon-tests (b) nuclear accidents (c) Energy, mining and industrial waste (3) Factors influencing the global Rn-222 and its daughters. (4) Dynamics of cycles of natural radioactivity, e.g. Pb-210. (5) Environmental radiotracers act as DIAGNOSTIC TOOLS to assess air and water quality and impacts of the atmospheric and hydrospheric compartments on ecosystems.6) Definition of base-lines for rehabilitation and protection. Climate influences sources/behaviour/fate of environmental radioactivity. Impacts on life forms in Africa would be severe. Assessing environmental radioactivity resolves these issue

  2. Removal and treatment of radioactive, organochlorine, and heavy metal contaminants from solid surfaces

    International Nuclear Information System (INIS)

    Grieco, S.A.; Neubauer, E.D.

    1996-01-01

    The U.S. Department of Energy (DOE) is defining decontamination and decommissioning (D ampersand D) obligations at its sites. Current D ampersand D activities are generally labor intensive, use chemical reagents that are difficult to treat, and may expose workers to radioactive and hazardous chemicals. Therefore, new technologies are desired that minimize waste, allow much of the decommissioned materials to be reused rather than disposed of as waste, and produce wastes that will meet disposal criteria. The O'Brien ampersand Gere companies tested a scouring decontamination system on concrete and steel surfaces contaminated with radioactive and hazardous wastes under the sponsorship of Martin Marietta Energy Systems, Inc. (MMES) at DOE's K-25 former gaseous diffusion plant in Oak Ridge, Tennessee. The scouring system removes fixed radioactive and hazardous contamination yet leaves the surface intact. Blasting residuals are treated using physical/chemical processes. Bench- and pilot-scale testing of the system was conducted on surfaces contaminated with uranium, technetium, heavy metals, and PCBs. Areas of concrete and metal surfaces were blasted. Residuals were dissolved in tap water and treated for radioactive, hazardous, and organochlorine constituents. The treatment system comprised pH adjustment, aeration, solids settling, filtration, carbon adsorption, and ion exchange. This system produced treated water and residual solid waste. Testing demonstrated that the system is capable of removing greater than 95% of radioactive and PCB surface contamination to below DOE's unrestricted use release limits; aqueous radionuclides, heavy metals, and PCBs were below DOE and USEPA treatment objectives after treatment. Waste residuals volume was decreased by 71 %. Preliminary analyses suggest that this system provides significant waste volume reduction and is more economical than alternative surface decontamination techniques that are commercially available or under development

  3. A methodology for evaluating alternative sites for a near-surface radioactive waste repository

    International Nuclear Information System (INIS)

    Watson, S.R.; Brownlow, S.A.

    1986-02-01

    This report addresses the issue of constructing an evaluation procedure for a near-surface radioactive waste repository. It builds on earlier work of the authors, and describes a basis for a practicable methodology for assessing the relative merits of different sites. (author)

  4. Device for measuring the two-dimensional distribution of a radioactive substance on a surface

    International Nuclear Information System (INIS)

    Anon.

    1986-01-01

    A device is described by which, using a one-dimensional measuring proportional counter tube depending on position, one can measure the two-dimensionally distributed radioactivity of a surface and can plot this to scale two-dimensionally, after computer processing, or can show it two-dimensionally on a monitor. (orig.) [de

  5. Investigation into the radioactivity of surface waters in the Netherlands

    International Nuclear Information System (INIS)

    Mattern, F.C.M.; Drost, R.M.S.; Glastra, P.; Ockhuizen, A.; Koolwijk, A.C.

    1990-11-01

    This report over 1989 summarizes the results of the determination of radioactivity in the rivers Meuse, Rhine, Roer, Westerscheldt and the channel of Sas van Gent to Terneuzen at locations near the border, as well as the Westerscheldt at Hansweert and Vlissingen and the North Sea at some locations along the Dutch coast. Concentrations of 90 Sr in the Meuse, Rhine and Roer (3.0 up to 4.1Bq/m 3 ) and in the Westerscheldt (9 Bq/m 3 ) were equal to, and in the North Sea ( up to 17 Bq/m 3 ) generally higher then the levels during 1988. The latter are caused by discharges of installations processing used nuclear fuel. The concentrations in the Westerscheldt are partly explained by mixing with water from the North Sea. Concentrations of 89 Sr in the Meuse, Rhine and Roer were below the limit of detection. In 1989 concentrations of 226 Ra in the rivers Rhine (4.2 Bq/m 3 ), Roer (15 Bq/m 3 ) and Westerscheldt (38Bq/m 3 ) were a bit higher than in 1988. Those of the Meuse (3.3 Bq/m 3 ) were unchanged. The relatively high concentration in the Roer can be explained by liquid discharges of coalmines in the FRG while the one in the Westerscheldt originates from discharges by plants processing phosphate rock. The amount of 226 Ra transported in 1988 by the river Westerscheldt was approximately 200 GBq. In the Westerscheldt the concentrations of 210 Pb (16 Bq/m 3 ) and of 210 Po (19 Bq/m 3 ) clearly exceeds those in the rivers Meuse, Rhine and Roer (2 to 5 Bq/m 3 ), due to discharges of phosphogypsum. Also the 210 Pb level in the channel of Sas van Gent to Terneuzen (6.8 Bq/m 3 ) was a bit higher. Concentrations of 3 H in the North Sea varied between 2200Bq/m 3 for the location Walcheren (20 km out of the coast) down to 1300 Bq/m 3 for the location Terschelling (100 km out of the coast). A level of 22 Bq/m 3 137 Cs in the North Sea has been measured at Terschelling. At the other locations the levels ranged from 7 to 9 Bq/m 3 . 134 Cs levels were below the limit of detection

  6. Radioactivity in the Dutch surface waters after Chernobylsk

    International Nuclear Information System (INIS)

    Kroesbergen, J.; Ballegooijen, L. van; Uunk, E.J.B.

    1988-12-01

    A survey is given of the impact of the nuclear accident in Chernobylsk upon the Dutch surface waters. With this the measurements, which have been performed in the various compartments (water, suspended matter, bottom, biota) are presented. Since the investigation is still going, the period from May 1986 - December 1987 has been chosen. This period is long enough in order to obtain an impression of the long-term effects. In chapter 2 a description is given of the measuring program performed and the analyzing methods employed. In chapter 3 the activation measurements in the surface waters, the suspended matter and the bottom are considered. Also the contamination of biologic matter and the purification mud is discussed. Chapter 4 gives a survey of the amount of radionuclides, which have been accumulated in the Dutch surface waters as a result of the Chernobylsk accident. The investigation of the processes are discussed in chapter 5. Since the study of the effects of radionuclides in the aquatic environment is still going, only some aspects are treated. Chapter 6 gives a general discussion of the results. Also an estimation is presented towards the future development of the contamination of the aquatic environment. Finally in chapter 7 the most important conclusions are summarized. Also some recommendations are made with regard to future measurements to be taken. (author). 72 refs.; 36 figs.; 26 tabs

  7. Development of an automatic smear sampler and a polymer film for surface radioactive contamination assay

    International Nuclear Information System (INIS)

    Seo, B.-K.; Lee, K.-W.; Woo, Z.-H.; Jeong, K.-S.; Oh, W.-Z.; Han, M.-J.

    2004-01-01

    Measurement of the surface contamination by an indirect method is subject to the various kinds of error according to the sampling person and needs much time and effort in the sampling and assay. In this research, an automatic smear sampler is developed. It improved efficiency for assay work of surface contamination level achieved periodically in a radiation controlled area. Using an automatic smear sampler developed, it is confirmed that radioactive contaminated materials are uniformly transferred to smear paper more than any sampling method by an operator. Also, Solid scintillation proximity membranes were prepared for measuring the amount of radioactive contamination in laboratories contaminated by the low energy beta-ray emitter, such as 3 H and 14 C. Polysulfone scintillation proximity membranes were prepared by impregnating Cerium Activated Yttrium Silicate (CAYS), an inorganic fluor, in a membrane structure. The inorganic fluor-impregnated membranes were applied to detect the radioactive surface contamination. The preparation of membranes was divided into two processes. A supporting polymer film was made of casting solutions consisting of polysulfone and solvent, their cast film being solidified by vacuum evaporation. CAYS-dispersed polymer solutions were cast over the first, solidified polymer films and coagulated either by evaporating solvent in the solution with non-solvent in a coagulation bath. The prepared membranes had two distinguished, but tightly attached, double layers : one is the supporting layer of dense polymer film and the other results revealed that the prepared membranes were efficient to monitor radioactive contamination with reliable counting ability. For enhancement of pick-up and measurement efficiency, the membrane was prepared with the condition of different membrane solidification. The scintillation produced by interaction with radiation and CAYS was measured with photomultiplier tube. The test results showed that the prepared

  8. Natural background radioactivity of the earth's surface -- essential information for environmental impact studies

    International Nuclear Information System (INIS)

    Tauchid, M.; Grasty, R.L.

    2002-01-01

    An environmental impact study is basically a study of change. This change is compared to the preexisting conditions that are usually perceived to be the original one or the 'pristine' stage. Unfortunately reliable information on the 'so called' pristine stage is far from adequate. One of the essential parts of this information is a good knowledge of the earth's chemical make up, or its geochemistry. Presently available data on the geochemistry of the earth's surface, including those related to radioactive elements, are incomplete and inconsistent. The main reason why a number of regulations are judged to be too strict and disproportional to the risks that might be caused by some human activities, is the lack of reliable information on the natural global geochemical background on which environmental regulations should be based. The main objective of this paper is to present a view on the need for complete baseline information on the earth's surface environment and in particular its geochemical character. It is only through the availability of complete information, including reliable baseline information on the natural radioactivity, that an appropriate study on the potential effect of the various naturally occurring elements on human health be carried out. Presented here are a number of examples where the natural radioactivity of an entire country has been mapped, or is in progress. Also described are the ways these undertakings were accomplished. There is a general misconception that elevated radioactivity can be found only around uranium mines, nuclear power reactors and similar nuclear installations. As can be seen from some of these maps, the natural background radioactivity of the earth's surface closely reflects the underlying geological formations and their alteration products. In reality, properly regulated and managed facilities, the levels of radioactivity associated with many of these facilities are generally quite low relative to those associated with

  9. Weathering and decontamination of radioactivity deposited on asphalt surfaces

    International Nuclear Information System (INIS)

    Warming, L.

    1982-12-01

    Longlived fission products might be deposited in the environment after a serious reactor accident. At Risoe we have studied how danish weather conditions and fire hosing influence the decontamination of Rubidium 86 (representing Cesium 134 and 137) Barium-Lanthanum 140 and Ruthenium 103 deposited on asphalt surfaces. Measurements have been done at different types of roads and during all seasons including winter with snow and ice cover of the roads. The results from the first five experiments were used for calculating doses to the population in the land contamination (RISO-R-462). (author)

  10. Contribution of the characterization of radioactive surfaces after sodium corrosion

    International Nuclear Information System (INIS)

    Menken, G.; Holl, M.

    1978-01-01

    Since 1972 INTERATOM is performing sodium mass and activity transfer investigations in an SNR-corrosion mockup loop which allows to study the transport of activated corrosion products in the primary heat transfer system of a sodium cooled reactor. The loop simulates the temperature and flow conditions and the materials combination of the SNR 300. The mass transfer examinations were aimed at the determination of the following: the linear corrosion and deposition rates; the selective corrosion of the alloying elements; the transfer of activated corrosion products. The results of a number of corrosion runs will be used in the following contribution to characterize the contaminated and corroded surface layers of reactor components. The loop reached a total operation time of 12300 h while the cold trap temperature was changed between 105 deg. C and 165 deg. C in successive runs

  11. Contents and Sample Arguments of a Safety Case for Near Surface Disposal of Radioactive Waste

    International Nuclear Information System (INIS)

    2017-06-01

    This publication arises from the results of two projects to assist Member States in understanding and developing safety cases for near-surface radioactive waste disposal facilities. The objective of the publication is to give detailed information on the contents of safety cases for radioactive waste disposal and the types of arguments that may be included. It is written for technical experts preparing a safety case, and decision makers in the regulatory body and government. The publication outlines the key uses and aspects of the safety case, its evolution in parallel with that of the disposal facility, the key decision steps in the development of the waste disposal facility, the components of the safety case, their place in the Matrix of Arguments for a Safety Case (the MASC matrix), and a detailed description of the development of sample arguments that might be included in a safety case for each of two hypothetical radioactive waste disposal facilities.

  12. Considerations in the development of near surface repositories for radioactive waste

    International Nuclear Information System (INIS)

    2003-01-01

    The report presents an integrated, stepwise approach for the development (includes pre-operational, operational and post-closure phases) of near surface disposal facilities for low and intermediate level radioactive waste. It has been developed in light of the considerable experience that has accumulated on the development of such disposal systems and is consistent with the current international requirements, principles, standards and guidance for the disposal of radioactive waste. It is considered that the systematic application of the various steps of the approach can contribute to the successful development of a repository programme. The approach is designed to be generic, integrating the various technical and nontechnical factors, and flexible enough to be suitable for use in the various Member States, ranging from countries that have nuclear power plants to countries that have small inventories of radioactive waste from nuclear applications. It is anticipated that this report will be particularly useful and of direct relevance to Member States that are currently developing, or have plans to develop, disposal facilities for low and intermediate level radioactive waste in the near future. The report is intended to respond to the disposal needs of the various Member States, ranging from countries with nuclear power plants to countries having small inventories of radioactive waste from nuclear applications. It was developed with the help of consultants and through an Advisory Group Meeting held in November 2001

  13. Derivation of activity limits for the disposal of radioactive waste in near surface disposal facilities

    International Nuclear Information System (INIS)

    2003-12-01

    Radioactive waste must be managed safely, consistent with internationally agreed safety standards. The disposal method chosen for the waste should be commensurate with the hazard and longevity of the waste. Near surface disposal is an option used by many countries for the disposal of radioactive waste containing mainly short lived radionuclides and low concentrations of long lived radionuclides. The term 'near surface disposal' encompasses a wide range of design options, including disposal in engineered structures at or just below ground level, disposal in simple earthen trenches a few metres deep, disposal in engineered concrete vaults, and disposal in rock caverns several tens of metres below the surface. The use of a near surface disposal option requires design and operational measures to provide for the protection of human health and the environment, both during operation of the disposal facility and following its closure. To ensure the safety of both workers and the public (both in the short term and the long term), the operator is required to design a comprehensive waste management system for the safe operation and closure of a near surface disposal facility. Part of such a system is to establish criteria for accepting waste for disposal at the facility. The purpose of the criteria is to limit the consequences of events which could lead to radiation exposures and in addition, to prevent or limit hazards, which could arise from non-radiological causes. Waste acceptance criteria include limits on radionuclide content concentration in waste materials, and radionuclide amounts in packages and in the repository as a whole. They also include limits on quantity of free liquids, requirements for exclusion of chelating agents and pyrophoric materials, and specifications of the characteristics of the waste containers. Largely as a result of problems encountered at some disposal facilities operated in the past, in 1985 the IAEA published guidance on generic acceptance

  14. Application of a modified electrochemical system for surface decontamination of radioactive metal waste

    International Nuclear Information System (INIS)

    Lee, J.H.; Lim, Y.K.; Yang, H.Y.; Shin, S.W.; Song, M.J.

    2003-01-01

    Conventional and modified electrolytic decontamination experiments were performed in a solution of sodium sulfate for the decontamination of carbon steel as the simulated metal wastes which are generated in large amounts from nuclear power plants. The effect of reaction time, current density and concentration of electrolytes in the modified electrolytic decontamination system were examined to remove the surface contamination of the simulated radioactive metal wastes. As for the results of this research, the modified electrochemical decontamination process can decontaminate more effectively than the conventional decontamination process by applying different anode material which causes higher induced electro-motive forces. When 0.5 M sodium sulfate, 0.4 A/cm 2 current density and 30 minutes reaction time were applied in the modified process, a 16 μm thickness change that is expected to remove most surface contamination in radioactive metal wastes was achieved on carbon steel which is the main material of radioactive metal waste in nuclear power plants. The decontamination efficiency of metal waste showed similar results with the small and large lab-scale modified electrochemical system. The application of this modified electrolytic decontamination system is expected to play a considerable role for decontamination of radioactive metal waste in nuclear power plants in the near future. (author)

  15. A Surface Soil Radioactivity Mapping Has Been Carried Out at Muria Peninsula, Central Java

    International Nuclear Information System (INIS)

    Soepradto-Tjokrokardono; Nasrun-Syamsul; Supardjo-AS; Djodi-R-Mappa; Kurnia-Setyawan W

    2004-01-01

    The air of this mapping is to gain exposure dose value of the soil surface of Muria Peninsula. Central Java, in the area of 75 km radius from Ujung Lemah Abang. Lemah Abang is the proposed site of the first indonesian nuclear Power Plant. A radioactivity data obtained in 1995/1996 to 1998/1999 researches has been used for input data. For further analysis, a conversation factor multiplication is applied. This conversation factor is obtained from linear regression equation of the relationship between radioactivity and exposure values gained from re-measured randomly 44 points which are representative for high, medium, and low radiation areas obtained in 1995/1996 to 1998/1999 activities and it taking soil samples. The conversation data result is being constructed of the Surface Exposure Dose Map of Muria Peninsula. Those data show that the exposure dose of northern slope of Muria Volcano is relatively higher than that of southern slope, it means be harmonizing to the soil sample radioactivity values. The maximum radioactivity value of the soil samples is 3,56.10 -2 Bq/gram (α radiation), 8,22.10 -1 Bq/gram (β radiation) and 6,20.10 -1 Bq/gram (γ radiation) and the minimum values are 4,44 10 -3 Bq/gram (α radiation), 1,50. 10 -1 Bq/gram (β radiation) and 4,09. 10 -2 Bq/gram (γ radiation). (author)

  16. Risk assessment based on current release standards for radioactive surface contamination

    International Nuclear Information System (INIS)

    Chen, S.Y.

    1993-09-01

    Standards for uncontrolled releases of radioactive surface contamination have been in existence in the United States for about two decades. Such standards have been issued by various agencies, including the US Department of Energy. This paper reviews the technical basis of published standards, identifies areas in need of revision, provides risk interpretations based on current technical knowledge and the regulatory environment, and offers suggestions for improvements

  17. An overview of technical requirements on durable concrete production for near surface disposal facilities for radioactive wastes

    International Nuclear Information System (INIS)

    Tolentino, Evandro; Tello, Cledola Cassia Oliveira de

    2013-01-01

    Radioactive waste can be generated by a wide range of activities varying from activities in hospitals to nuclear power plants, to mines and mineral processing facilities. General public have devoted nowadays considerable attention to the subject of radioactive waste management due to heightened awareness of environmental protection. The preferred strategy for the management of all radioactive waste is to contain it and to isolate it from the accessible biosphere. The Federal Government of Brazil has announced the construction for the year of 2014 and operation for the year of 2016 of a near surface disposal facility for low and intermediate level radioactive waste. The objective of this paper is to provide an overview of technical requirements related to production of durable concrete to be used in near surface disposal facilities for radioactive waste concrete structures. These requirements have been considered by researchers dealing with ongoing designing effort of the Brazilian near surface disposal facility. (author)

  18. Radioactivity decontamination of materials commonly used as surfaces in general-purpose radioisotope laboratories.

    Science.gov (United States)

    Leonardi, Natalia M; Tesán, Fiorella C; Zubillaga, Marcela B; Salgueiro, María J

    2014-12-01

    In accord with as-low-as-reasonably-achievable and good-manufacturing-practice concepts, the present study evaluated the efficiency of radioactivity decontamination of materials commonly used in laboratory surfaces and whether solvent spills on these materials affect the findings. Four materials were evaluated: stainless steel, a surface comprising one-third acrylic resin and two-thirds natural minerals, an epoxy cover, and vinyl-based multipurpose flooring. Radioactive material was eluted from a (99)Mo/(99m)Tc generator, and samples of the surfaces were control-contaminated with 37 MBq (100 μL) of this eluate. The same procedure was repeated with samples of surfaces previously treated with 4 solvents: methanol, methyl ethyl ketone, acetone, and ethanol. The wet radioactive contamination was allowed to dry and then was removed with cotton swabs soaked in soapy water. The effectiveness of decontamination was defined as the percentage of activity removed per cotton swab, and the efficacy of decontamination was defined as the total percentage of activity removed, which was obtained by summing the percentages of activity in all the swabs required to complete the decontamination. Decontamination using our protocol was most effective and most efficacious for stainless steel and multipurpose flooring. Moreover, treatment with common organic solvents seemed not to affect the decontamination of these surfaces. Decontamination of the other two materials was less efficient and was interfered with by the organic solvents; there was also great variability in the overall results obtained for these other two materials. In expanding our laboratory, it is possible for us to select those surface materials on which our decontamination protocol works best. © 2014 by the Society of Nuclear Medicine and Molecular Imaging, Inc.

  19. Measurement of residual radioactive surface contamination by 2-D laser heated TLD

    International Nuclear Information System (INIS)

    Jones, S.C.

    1997-06-01

    The feasibility of applying and adapting a two-dimensional laser heated thermoluminescence dosimetry system to the problem of surveying for radioactive surface contamination was studied. The system consists of a CO 2 laser-based reader and monolithic arrays of thin dosimeter elements. The arrays consist of 10,201 thermoluminescent phosphor elements of 40 micron thickness, covering a 900 cm 2 area. Array substrates are 125 micron thick polyimide sheets, enabling them to easily conform to regular surface shapes, especially for survey of surfaces that are inaccessible for standard survey instruments. The passive, integrating radiation detectors are sensitive to alpha and beta radiation at contamination levels below release guideline limits. Required contact times with potentially contaminated surfaces are under one hour to achieve detection of transuranic alpha emission at 100 dpm/100 cm 2 . Positional information obtained from array evaluation is useful for locating contamination zones. Unique capabilities of this system for survey of sites, facilities and material include measurement inside pipes and other geometrical configurations that prevent standard surveys, and below-surface measurement of alpha and beta emitters in contaminated soils. These applications imply a reduction of material that must be classified as radioactive waste by virtue of its possibility of contamination, and cost savings in soil sampling at contaminated sites

  20. Study of waterproof capabilities of the engineered barrier containing bentonite in near surface radioactive waste repositories

    International Nuclear Information System (INIS)

    Luu Cao Nguyen; Nguyen Ba Tien; Doan Thi Thu Hien; Nguyen Van Chinh; Vuong Huu Anh

    2017-01-01

    In Vietnam, the study of nuclear fuel cycle is in first steps, such as the exploitation and uranium processing. These processes generated large amounts of radioactive waste over-timing. The naturally occurring radioactive material and technologically enhanced radioactive material (NORM/TENORM) waste, which would be large, needs to be managed and disposed reasonably by effective methods. These wastes were used to be disposal in the near surface. It was therefore very important to study the model of radioactive waste repository, where bentonite waterproofing layer would be applied for the engineered barrier. The aim of this study was to obtain the preliminary parameters for low-level radioactive waste disposal site being suitable with the conditions of Vietnam. The investigation of the ratio between soil and bentonite was taken part. The experiments with some layers of waterproofing material with the ratio of soil and bentonite as 75/25, 50/50 and 25/75 were carried out to test the moving of uranium nuclide through these waterproofing material layers. Analyzing the uranium content in each layer (0.1 cm) of pressed soil - bentonite mixture (as a block) to determine the uranium nuclide adsorption from solution into the materials in the different ratios at the different times: 1, 2 and 3 months was carried out. The results showed that the calculated average rate of uranium nuclide migration into the soil - bentonite layer was 5.4x10 -10 , 5.4x10 -10 and 3.85x10 -10 m/s corresponding to the waterproofing layer thickness (for 300 years) 4.86 m, 4.86 m and 3.63 m respectively, which was due on the ratio of soil and bentonite 75/25, 50/50, 25/75 to keep the safety for the repository. (author)

  1. Isopleths of surface concentration and surface exposure rate due to a radioactive cloud released from a stack

    International Nuclear Information System (INIS)

    Kobayashi, Hideo; Yabuta, Hajimu; Katagiri, Hiroshi; Obata, Kazuichi; Kokubu, Morinobu

    1982-03-01

    Various calculations are made to estimate the distributions of concentration and γ-exposure rate due to a radioactive cloud released from a point source to the atmosphere. In this report, the isopleths of concentration and γ-exposure rate which were calculated are given in graphs to enable rapid prediction of the influence of released radioactive material in the emergency situation. Recently there are facilities which are equipped with a system to display the calculation results on CRT; but such practice is rather rare. By placing the calculated isopleths of reduction scale 1/25000 or 1/50000 on the usual map, any facilities without the CRT system can readily estimate the influence of an accidental release. The graphs of isopleths are given with the release height (11 values of 0 to 200 m at about 20 m intervals) and the atmospheric stability (6 classes) as parameters. Calculations of γ-exposure rates were made using the computer code GAMPUL developed by T. Hayashi and T. Shiraishi. In the calculation of radioactive concentrations and γ-exposure rates, the vertical diffusion depths, σsub(z), exceeding 1000 m are taken to be 1000 m according to the Meteorological Guide for the Safety Analysis of Power Reactor (J.AEC). The comparison between with and without this limitation in σsub(z) is made in the case of downwind axial surface distributions. (author)

  2. A review of construction techniques available for surface and underground radioactive waste repositories

    International Nuclear Information System (INIS)

    Godfrey, D.G.; Davies, I.L.; MacKenzie, R.D.

    1985-01-01

    In terms of engineering requirements the construction of surface or indeed underground radioactive waste repositories is not unduly difficult. The civil engineering techniques likely to be required have generally been carried out previously, albeit not in the context of radioactive waste repositories in this country. The emphasis will have to be very much on the quality of construction. This paper emphasises the need for quality construction and describes the techniques likely to be used in the construction of repositories. Reference is made to the materials likely to be used in the construction of repositories and also to the need for being able to convince the designers, regulating authorities and the general public that the materials used will indeed last for the required time. Brief reference is made at the end of the paper to the civil engineering parameters requiring consideration in the location of repository siting. (author)

  3. 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.)

  4. A Contribution to Turbulent Combustion: Premixed Flames and Material Surfaces Une contribution à la combustion turbulente : flammes prémélangées et surfaces des matériaux

    Directory of Open Access Journals (Sweden)

    Nicolleau F.

    2006-11-01

    from each other. The turbulent diffusion process is very active to create new burning zones. This diffusion process is closely related to both the intensity and the length scale of the turbulent field. That explains the dominant role of turbulence and the adaptation of the burning rate to the rotation speed in combustion engines. Additional information useful for the reader is reported in Appendices I and II. Le comportement des flammes de prémélange a été examiné par de nombreux auteurs. En fait, le problème de la combustion en milieu turbulent repose pour beaucoup sur des comparaisons d'échelles. Dans le présent article, une première étude porte sur l'évolution d'une surface matérielle (qui peut être assimilée sous certaines conditions à une surface de flamme. On utilise successivement une démarche analytique et une démarche numérique. On constate alors la rapidité d'extension de la surface et le rôle prépondérant des petites échelles ce que confirme l'étude analytique. Les risques d'extinction sont prédits en général par comparaison d'échelles. D'une simulation directe conduite sur un cas spécifique, Poinsot confirme l'idée que ce ne sont pas les structures ayant les échelles caractéristiques de la flamme qui sont les plus redoutables, mais des structures de taille quelque peu plus grande. Dans un précédent article, le rôle cumulé des gradients locaux avait été signalé. Nous donnons à ce concept une forme quantitative en utilisant le ß modèle lequel définit un taux d'occupation de l'espace en fonction du rang (et donc de la dimension de structures. Un calcul de gradient cumulé redonne la prédiction de Poinsot. Enfin, le même ß modèle est utilisé pour définir une nouvelle zone dans la région de combustion distribuée. Des balles fluides brûlent isolément tandis qu'un processus de diffusion lié très étroitement au champ turbulent et à son intensité crée d'autres points d'allumage. Le mécanisme explique l

  5. Radioactive contamination of some rubber or plastic surfaces by fission products. Decontamination tests

    International Nuclear Information System (INIS)

    Mestre, E.; Sautiez, N.

    1957-10-01

    With the objective of notably addressing the contamination and decontamination of gloves and floor covering, this report first presents some characteristics of contaminating radioactive materials (nature, physical and chemical condition), of contaminated surfaces (surface condition, surface nature), and of decontamination processes (physical, chemical or mechanical action). It describes the operational modality implemented to test decontamination processes on various glove or flooring materials: sample preparation, counting, decontamination, reproducibility of decontamination tests, results in terms of activity reduction. It more precisely describes the tested samples: short gloves, gloves from glove boxes, floor and wall coverings. Results are presented and discussed in terms of sample susceptibility to contamination, and of decontamination, but also for re-contamination tests after a Nab-based decontamination (susceptibility to contamination, decontamination gain)

  6. A Review of Removable Surface Contamination on Radioactive Materials Transportation Containers

    Energy Technology Data Exchange (ETDEWEB)

    Kennedy, Jr, W. E.; Watson, E. C.; Murphy, D. W.; Harrer, B. J.; Harty, R.; Aldrich, J. M.

    1981-05-01

    This report contains the results of a study sponsored by the U.S. Nuclear Regulatory Commission (NRC) of removable surface contamination on radioactive materials transportation containers. The purpose of the study is to provide information to the NRC during their review of existing regulations. Data was obtained from both industry and literature on three major topics: 1) radiation doses, 2) economic costs, and 3) contamination frequencies. Containers for four categories of radioactive materials are considered including radiopharmaceuticals, industrial sources, nuclear fuel cycle materials, and low-level radioactive waste. Assumptions made in this study use current information to obtain realistic yet conservative estimates of radiation dose and economic costs. Collective and individual radiation doses are presented for each container category on a per container basis. Total doses, to workers and the public, are also presented for spent fuel cask and low-level waste drum decontamination. Estimates of the additional economic costs incurred by lowering current limits by factors of 10 and 100 are presented. Current contamination levels for each category of container are estimated from the data collected. The information contained in this report is designed to be useful to the NRC in preparing their recommendations for new regulations.

  7. Radionuclide transport modelling for a buried near surface low level radioactive waste

    International Nuclear Information System (INIS)

    Terzi, R.

    2004-01-01

    The disposal of radioactive waste, which is the last step of any radioactive waste management policy, has not yet been developed in Turkey. The existing legislation states only the discharge limits for the radioactive wastes to be discharged to the environment. The objective of this modelling study is to assist in safety assessment and selecting disposal site for gradually increasing non-nuclear radioactive wastes. This mathematical model has been developed for the environmental radiological assessment of near surface disposal sites for the low and intermediate level radioactive wastes. The model comprised of three main components: source term, geosphere transport and radiological assessment. Radiation dose for the babies (1 years age) and adults (≥17 years age) have been computed for the radionuclides Cesium 137 (Cs-137) and Strontium 90 (Sr-90), having the activity of 1.10 12 Becquerel(Bq), in radioactive waste through transport of radionuclide in liquid phase with the various pathways. The model consisted of first order ordinary differential equations was coded as a TCODE file in MATLAB program. The radiation dose to man for the realist case and low probability case have been calculated by using Runge-Kutta solution method in MATLAB programme for radionuclide transport from repository to soil layer and then to the ground water(saturated zone) through drinking water directly and consuming agricultural and animal products pathways in one year period. Also, the fatal cancer risk assessment has been made by taking into account the annual dose received by people. Various dose values for both radionuclides have been found which depended on distribution coefficient, retardation factor and dose conversion factors. The most important critical parameters on radiological safety assessment are the distribution coefficient in soil layer, seepage velocity in unsaturated zone and thickness of the unsaturated zone (soil zone). The highest radiation dose and average dose to

  8. A high-efficiency positive (negative) surface ionization source for radioactive ion beam (abstract)a

    International Nuclear Information System (INIS)

    Alton, G.D.; Mills, G.D.

    1996-01-01

    A versatile, new concept, spherical-geometry, positive (negative) surface-ionization source has been designed and fabricated which will have the capability of generating both positive- and negative-ion beams without mechanical changes to the source. The source utilizes a highly permeable, high-work-function Ir ionizer (φ≡5.29 eV) for ionizing highly electropositive atoms/molecules; while for negative-surface ionization, the work function is lowered to φ≡1.43 eV by continually feeding cesium vapor through the ionizer matrix. The use of this technique for negative ion beam generation has the potential of overcoming the chronic poisoning effects experienced with LaB 6 while enhancing considerably the efficiency for negative surface ionization of atoms and molecules with intermediate electron affinities. The flexibility of operation in either mode makes it especially attractive for radioactive ion beam applications and, therefore, the source will be used as a complementary replacement for the high-temperature electron impact ionization sources presently in use at the Holifield radioactive beam facility. The design features and operational principles of the source will be described in this report. copyright 1996 American Institute of Physics

  9. A positive (negative) surface ionization source concept for radioactive ion beam generation

    International Nuclear Information System (INIS)

    Alton, G.D.; Mills, G.D.

    1996-01-01

    A novel, versatile, new concept, spherical-geometry, positive (negative) surface-ionization source has been designed and fabricated which will have the capability of generating both positive- and negative-ion beams without mechanical changes to the source. The source utilizes a highly permeable, high-work-function Ir ionizer (φ ≅ 5.29 eV) for ionizing highly electropositive atoms/molecules; while for negative-surface ionization, the work function is lowered by continually feeding a highly electropositive vapor through the ionizer matrix. The use of this technique to effect low work function surfaces for negative ion beam generation has the potential of overcoming the chronic poisoning effects experienced with LaB 6 while enhancing the probability for negative ion formation of atomic and molecular species with low to intermediate electron affinities. The flexibility of operation in either mode makes it especially attractive for radioactive ion beam (RIB) applications and, therefore, the source will be used as a complementary replacement for the high-temperature electron impact ionization sources presently in the use at the Holifield radioactive ion beam facility (HRIBF). The design features and operational principles of the source are described in this report. (orig.)

  10. Processing method and processing device for liquid waste containing surface active agent and radioactive material

    International Nuclear Information System (INIS)

    Nishi, Takashi; Matsuda, Masami; Baba, Tsutomu; Yoshikawa, Ryozo; Yukita, Atsushi.

    1998-01-01

    Washing liquid wastes containing surface active agents and radioactive materials are sent to a deaerating vessel. Ozone is blown into the deaerating vessel. The washing liquid wastes dissolved with ozone are introduced to a UV ray irradiation vessel. UV rays are irradiated to the washing liquid wastes, and hydroxy radicals generated by photodecomposition of dissolved ozone oxidatively decompose surface active agents contained in the washing liquid wastes. The washing liquid wastes discharged from the UV ray irradiation vessel are sent to an activated carbon mixing vessel and mixed with powdery activated carbon. The surface active agents not decomposed in the UV ray irradiation vessel are adsorbed to the activated carbon. Then, the activated carbon and washing liquid wastes are separated by an activated carbon separating/drying device. Radioactive materials (iron oxide and the like) contained in the washing liquid wastes are mostly granular, and they are separated and removed from the washing liquid wastes in the activated carbon separating/drying device. (I.N.)

  11. Application of autonomous robotics to surveillance of waste storage containers for radioactive surface contamination

    International Nuclear Information System (INIS)

    Sweeney, F.J.; Beckerman, M.; Butler, P.L.; Jones, J.P.; Reister, D.B.

    1991-01-01

    This paper describes a proof-of-principal demonstration performed with the HERMIES-III mobile robot to automate the inspection of waste storage drums for radioactive surface contamination and thereby reduce the human burden of operating a robot and worker exposure to potentially hazardous environments. Software and hardware for the demonstration were developed by a team consisting of Oak Ridge National Laboratory, and the Universities of Florida, Michigan, Tennessee, and Texas. Robot navigation, machine vision, manipulator control, parallel processing and human-machine interface techniques developed by the team were demonstrated utilizing advanced computer architectures. The demonstration consists of over 100,000 lines of computer code executing on nine computers

  12. On release of radionuclides from a near-surface radioactive waste repository to the environment

    Directory of Open Access Journals (Sweden)

    Gudelis Arūnas

    2015-09-01

    Full Text Available A closed near-surface radioactive waste repository is the source of various radionuclides causing the human exposure. Recent investigations confirm an effectiveness of the engineering barriers installed in 2006 to prevent the penetration of radionuclides to the environment. The tritium activity concentration in groundwater decreased from tens of kBq/l to below hundreds of Bq/l. The monitoring and groundwater level data suggest the leaching of tritium from previously contaminated layers of unsaturated zone by rising groundwater while 210Pb may disperse as a decay product of 226Ra daughters.

  13. Procedures and techniques for closure of near surface disposal facilities for radioactive waste

    International Nuclear Information System (INIS)

    2001-12-01

    The overall objective of this report is to provide Member States with guidance on planning and implementation of closure of near surface disposal facilities for low and intermediate level radioactive waste. The specific objectives are to review closure concepts, requirements, and components of closure systems; to discuss issues and approaches to closure, including regulatory, economic, and technical aspects; and to present major examples of closure techniques used and/or considered by Member States. Some examples of closure experience from Member States are presented in the Appendix and were indexed separately

  14. Adsorbed radioactivity and radiographic imaging of surfaces of stainless steel and titanium

    Science.gov (United States)

    Jung, Haijo

    1997-11-01

    Type 304 stainless steel used for typical surface materials of spent fuel shipping casks and titanium were exposed in the spent fuel storage pool of a typical PWR power plant. Adsorption characteristics, effectiveness of decontamination by water cleaning and by electrocleaning, and swipe effectiveness on the metal surfaces were studied. A variety of environmental conditions had been manipulated to stimulate the potential 'weeping' phenomenon that often occurs with spent fuel shipping casks during transit. In a previous study, few heterogeneous effects of adsorbed contamination onto metal surfaces were observed. Radiographic images of cask surfaces were made in this study and showed clearly heterogeneous activity distributions. Acquired radiographic images were digitized and further analyzed with an image analysis computer package and compared to calibrated images by using standard sources. The measurements of activity distribution by using the radiographic image method were consistent with that using a HPGe detector. This radiographic image method was used to study the effects of electrocleaning for total and specified areas. The Modulation Transfer Function (MTF) of a film-screen system in contact with a radioactive metal surface was studied with neutron activated gold foils and showed more broad resolution properties than general diagnostic x-ray film-screen systems. Microstructure between normal areas and hot spots showed significant differences, and one hot spot appearing as a dot on the film image consisted of several small hot spots (about 10 μm in diameter). These hot spots were observed as structural defects of the metal surfaces.

  15. Region study of the impact of an accidental radioactive pollution on the corn of winter; Etude regionalisee de l'impact d'une pollution radioactive accidentelle sur le ble d'hiver

    Energy Technology Data Exchange (ETDEWEB)

    Delboe, A.; Mercat-Rommens, C

    2005-07-01

    The goal of this study is to evaluate the sensitivity of corn of winter with respect to an accidental release of radioactivity. We want to know if a uniform and specific deposit would involve the same contamination on the scale of the whole territory. the study was based on the equations of the A.S.T.R.A.L. model which makes it possible to evaluate the transfer of the radionuclides in the terrestrial food chain following an accidental atmospheric emission. The parameter of A.S.T.R.A.L. on which the study concentrated is the factor of transfer of the radioactivity of the air to the grain. This factor depends on the parameters of captation and translocation, since harvest is contaminated when the radionuclides deposited on the leaves are assimilated and transported towards the grain. Methodology thus consisted in regionalizing these two parameters. for that, software S.T.I.C.S. (multidisciplinary simulator for standard cultures) developed by the I.N.R.A. of Avignon was used. This model proposes a daily follow-up of the foliar index, as well as the dates of occurrence of the agronomic stages of corn. These variables were correlated with captation and translocation. The outputs of the simulations carried out on 12 climates and 2 varieties made it possible to express the parameters of captation and translocation according to the typology of A.S.T.R.A.L., i e according to the time deposit-harvest. Then, these values were compared with bibliographical data and with data issued from I.R.S.N. programs R.E.S.S.A.C. and R.A.D.E.M.I.C.. (authors)

  16. Process for dissolving the radioactive corrosion products from internal surfaces in nuclear reactors

    International Nuclear Information System (INIS)

    Brown, W.W.

    1976-01-01

    This invention concerns a process for dissolving in the coolant flowing in a reactor the radioactive substances from the corrosion of the internal surfaces of the reactor to which they cling. When a reactor is operating, the fission occurring in the fuel generates gases and fission substances, such as iodine 131 and 133, cesium 134 and 137, molybdenum 99, xenon 133 and activates the structural materials of the reactor such as nickel by giving off cobalt 58 and similar substances. Under this invention an oxygen rich solution is injected in the reactor coolant after the temperature and pressure reduction stage, during the preparation prior to refuelling and repairs. The oxygen in the solution speeds up the release of cobalt 58 and other radioactive substances from the internal surfaces of the reactor and their dissolving in the oxygenated cold coolant at the start of the cooling procedures of the installation. This allows them to be removed by an ion exchanger before the reactor is emptied. By utilising this process, about half a day may be gained in refuelling time when this has to be done once a week [fr

  17. Types of safety assessments of near surface repository for radioactive waste

    International Nuclear Information System (INIS)

    Mateeva, M.

    2004-01-01

    The purpose of this article is to presents the classification of different types safety assessments of near surface repository for low and intermediate level radioactive waste substantiated with results of safety assessments generated in Bulgaria. The different approach of safety assessments applied for old existing repository as well as for site selection for construction new repository is outlined. The regulatory requirements in Bulgaria define three main types of assessments: Safety assessment; Technical substation of repository safety; Assessment of repository influence on environment that is in form of report prepared from the Ministry of environment and waters on the base of results obtained in two first types of assessments. Additionally first type is subdivided in three categories - preliminary safety assessment, safety assessment and post closure safety assessment, which are generated using deterministic approach. The technical substation of repository safety is generated using probabilistic approach. Safety assessment results that are presented here are based on evaluation of existing old repository type 'Radon' in Novi Han and real site selection procedure for new near surface repository for low and intermediate level radioactive waste from nuclear power station in Kozloduy. The important role of safety assessment for improvement the repository safety as well as for repository licensing, correct site selection and right choice of engineer barriers and repository design is discussed using generated results. (author)

  18. Portable instrumentation for quantitatively measuring radioactive surface contaminations, including 90Sr

    International Nuclear Information System (INIS)

    Brodzinski, R.L.

    1983-10-01

    In order to measure the effectiveness of decontamination efforts, a quantitative analysis of the radiocontamination is necessary, both before and after decontamination. Since it is desirable to release the decontaminated material for unrestricted use or disposal, the assay equipment must provide adequate sensitivity to measure the radioactivity at or below the release limit. In addition, the instrumentation must be capable of measuring all kinds of radiocontaminants including fission products, activation products, and transuranic materials. Finally, the survey instrumentation must be extremely versatile in order to assay the wide variety of contaminated surfaces in many environments, some of which may be extremely hostile or remote. This communication describes the development and application of portable instrumentation capable of quantitatively measuring most transuranics, activation products, and fission products, including 90 Sr, on almost any contaminated surface in nearly any location

  19. Possibilities of a metal surface radioactive decontamination using a pulsed CO2 laser

    Science.gov (United States)

    Milijanic, Scepan S.; Stjepanovic, Natasa N.; Trtica, Milan S.

    2000-01-01

    There is a growing interest in the laser radioactive decontamination of metal surfaces. It offers advantages over conventional methods: improved safety, reduction of secondary waste, reduced waste volume, acceptable cost. A main mechanism of cleaning in by lasers is ablation. In this work a pulsed TEA CO2 laser was used for surface cleaning, primarily in order to demonstrate that the ablation from metal surfaces with this laser is possible even with relatively low pulse energies, and secondary, that it could be competitive with other lasers because of much higher energy efficiencies. The laser pulse contains two parts, one strong and shot peak at the beginning, followed with a tail. The beam was focused onto a contaminated surface with a KBr lens. The surface was contaminated with 137Cs. Three different metals were used: stainless steel, copper and aluminum. The evaporated material was pumped out in air atmosphere and transferred to a filter. Presence of the activity on the filter was proved by a germanium detector-multichannel analyzer. Activity levels were measured by a GM counter. Calculated decontamination factors as well as collection factors have shown that ablation takes place with relatively high efficiency of decontamination. This investigation suggests that decontamination using the CO2 laser should be seriously considered.

  20. An attemp to use a pulsed CO2 laser for decontamination of radioactive metal surfaces

    Directory of Open Access Journals (Sweden)

    MILAN S. TRTICA

    2000-06-01

    Full Text Available There is a growing interest in laser radioactive decontamination of metal surfaces. It offers advantages over conventional methods: improved safety, reduction of secondary waste, reduced waste volume, acceptable cost. The main mechanism of cleaning by lasers is ablation. A pulsed TEA CO2 laser was used in this work for surface cleaning in order to show that ablation of metal surfaces is possible even at relatively low pulse energies, and to suggest that it could be competitive with other lasers because of much higher energy efficiencies. A brief theoretical analysis was made before the experiments. The laser beam was focused using a KBr-lens onto a surface contaminated with 137Cs (b-, t1/2 = 30.17 y. Three different metals were used: stainless steel, copper and aluminium. The ablated material was pumped out in an air atmosphere and transferred to a filter. The presence of activity on the filter was shown by a germanium detector-multichannel analyzer. The activity levels were measured by a GM counter. The calculated decontamination factors and collection factors showed that ablation occurs with a relatively high efficiency of decontamination. This investigation suggests that decontamination using a CO2 laser should be seriously considered.

  1. Consideration of Criteria for a Conceptual Near Surface Radioactive Waste disposal Facility in Kenya

    Energy Technology Data Exchange (ETDEWEB)

    Nderitu, Stanley Werugia; Kim, Changlak [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2014-05-15

    The purpose of the criteria is to limit the consequences of events which could lead to radiation exposures. This study will present an approach for establishing radiological waste acceptance criteria using a safety assessment methodology and illustrate some of its application in establishing limits on the total activity and the activity concentrations of radioactive waste to be disposed in a conceptual near surface disposal facility in Kenya. The approach will make use of accepted methods and computational schemes currently used in assessing the safety of near surface disposal facilities. The study will mainly focus on post-closure periods. The study will employ some specific inadvertent human intrusion scenarios in the development of example concentration ranges for the disposal of near-surface wastes. The overall goal of the example calculations is to illustrate the application of the scenarios in a performance assessment to assure that people in the future cannot receive a dose greater than an established limit. The specific performance assessments will use modified scenarios and data to establish acceptable disposal concentrations for specific disposal sites and conditions. Safety and environmental impacts assessments is required in the post-closure phase to support particular decisions in development, operation, and closure of a near surface repository.

  2. Man-made radioactivity of surface air and precipitation Munich-Neuherberg 1970-1975

    International Nuclear Information System (INIS)

    Hoetzl, H.; Rosner, G.; Winkler, R.

    1976-07-01

    The activity concentration of a number of artificial radionuclides and of Be 7 in surface air and the deposition of these nuclides to the ground by the precipitation is measured since 1970 resp. 1971 at Neuherberg near Munich. Air dust filters are compressed to give a pellet and precipitation is evaporated to a small volume before γ-spectrometry using a Ge(Li)-detector. After ashing of the samples Pusup(238, 239, 240) and Fe 55 are separated radiochemically and measured by alpha respectively X-ray spectrometry. The results, presented as monthly mean resp. sum values, are discussed and compared with results published by other authors (HASL, UKAEA, PTB, DWD a.o.). The contribution of artificial radioactivity to the radiation exposure from fallout nuclides during the years 1970 to 1975 was very low. Their concentration levels led to values of the annual intake, which are far beyond the admissible values according to the new Radiation Protection Ordinance of the FRG. With regard to the intake by inhalation Pu 239 is the most important of all observed nuclides, whereas in the case of ingestion Sr 90 is the critical nuclide. At this time the level of the activity concentration is mainly represented by the residual radioactivity from nuclear bomb tests. A continuous control is necessary because of the growth of nuclear power production and the increasing use of radionuclides. (orig.) [de

  3. Environmental radioactivity and water supply. Pt. 3. The contamination of surface waters in Germany after the Chernobyl reactor accident

    International Nuclear Information System (INIS)

    Haberer, K.

    1988-03-01

    After the reactor accident, german surface waters have been monitored in numerous positions over a long period of time. The highest concentrations of iodine 131 occurred in the lower german region of the Danube river with more than 200 Bg/l whereas the Rhine river had the lowest concentrations. The sudden rise of the radioactivity of the river water have been followed by a slower decrease but nevertheless much faster than the radioactive decay. Probably this is caused by the interaction with river sediments. For the german lakes and reservoirs it was very important whether the water masses have been stratified or not when the radioactive cloud arrived. Where this was the case, the radioactive contaminants remained predominantly in the upper layer, the epilimnion for a long period of time [fr

  4. Méthodologie de conception de motifs dirigée par la distance de Hamming : application à la reconstruction de surfaces à partir d'une seule image

    OpenAIRE

    Maurice , Xavier; Doignon , Christophe

    2012-01-01

    Session "Articles"; National audience; En vision artificielle par lumière structurée, la projection d'un motif sur un objet permet de capturer la forme de sa surface à un instant donné, en effectuant plusieurs acquisitions. Cette technique peut cependant s'avérer inefficace lorsque l'objet est en mouvement. Il devient alors nécessaire de ne faire appel qu'à une seule prise d'images pour analyser la forme d'une région d'intérêt en mouvement et des motifs intégrant des propriétés intrinsèques d...

  5. Post-closure safety assessment of near surface disposal facilities for disused sealed radioactive sources

    International Nuclear Information System (INIS)

    Lee, Seunghee; Kim, Juyoul

    2017-01-01

    Highlights: • Post-closure safety assessment of near surface disposal facility for DSRS was performed. • Engineered vault and rock-cavern type were considered for normal and well scenario. • 14 C, 226 Ra, 241 Am were primary nuclides contributing large portion of exposure dose. • Near surface disposal of DSRSs containing 14 C, 226 Ra and 241 Am should be restricted. - Abstract: Great attention has been recently paid to the post-closure safety assessment of low- and intermediate-level radioactive waste (LILW) disposal facility for disused sealed radioactive sources (DSRSs) around the world. Although the amount of volume of DSRSs generated from industry, medicine and research and education organization was relatively small compared with radioactive wastes from commercial nuclear power plants, some DSRSs can pose a significant hazard to human health due to their high activities and long half-lives, if not appropriately managed and disposed. In this study, post-closure safety assessment was carried out for DSRSs generated from 1991 to 2014 in Korea in order to ensure long-term safety of near surface disposal facilities. Two kinds of disposal options were considered, i.e., engineered vault type disposal facility and rock-cavern type disposal facility. Rock-cavern type disposal facility has been under operation in Gyeongju city, republic of Korea since August 2015 and engineered vault type disposal facility will be constructed until December 2020 in the vicinity of rock-cavern disposal facility. Assessment endpoint was individual dose to the member of critical group, which was modeled by GoldSim, which has been widely used as probabilistic risk analysis software based on Monte Carlo simulation in the area of safety assessment of radioactive waste facilities. In normal groundwater scenario, the maximum exposure dose was extremely low, approximately 1 × 10 −7 mSv/yr, for both disposal options and satisfied the regulatory limit of 0.1 mSv/yr. However, in the

  6. Formation of filtration fields close to near-surface radioactive waste storages

    International Nuclear Information System (INIS)

    Mart'yanov, V.V.

    2008-01-01

    Data on the formation of filtration fields in the location of near-surface radioactive waste storages for the conditions of uniformly isotropic properties of bearing strata are demonstrated. The possibility for changing parameters of mean-caused ground flow depending on water permeability of the storages and their dimensions in plan is noted. Comparison of different filtration fields permits to determine a state of its isolating properties. Assessment criteria of the storage engineering barriers integrity are given. Conditions for uniformly isotropic properties of bearing strata by three scenarios, when engineering barriers of the storage are waterproof, distracted or lost protective properties in full, have been determined. Changing filtration field, geochemical and radiochemical situations in bearing strata are noted to represent one of basic characteristics of the integrity of the storage [ru

  7. Conceptual model to determine maximum activity of radioactive waste in near-surface disposal facilities

    International Nuclear Information System (INIS)

    Iarmosh, I.; Olkhovyk, Yu.

    2016-01-01

    For development of the management strategy for radioactive waste to be placed in near - surface disposal facilities (NSDF), it is necessary to justify long - term safety of such facilities. Use of mathematical modelling methods for long - term forecasts of radwaste radiation impact and assessment of radiation risks from radionuclides migration can help to resolve this issue. The purpose of the research was to develop the conceptual model for determining the maximum activity of radwaste to be safely disposed in the NSDF and to test it in the case of Lot 3 Vector NSDF (Chornobyl exclusion zone). This paper describes an approach to the development of such a model. The conceptual model of "9"0 Sr migration from Lot 3 through aeration zone and aquifer soils was developed. The results of modelling are shown. The proposals on further steps for the model improvement were developed

  8. Surface-type repository for low and intermediate level radioactive waste in the Republic of Croatia

    International Nuclear Information System (INIS)

    Kucar-Dragicevic, S.; Zarkovic, V.; Subasic, D.

    1995-01-01

    The low-level intermediate-level (LL/IL) radioactive waste repository siting and construction project is one of the activities related to establishing the rad waste management system in the Republic of Croatia. The repository project design is one in an array of project activities which also include the site selection procedure and public attitude issues. The prepared design documentation gives technical, safety and financial background relevant for making a final decision on the waste disposal type, and it includes the technological, mechanical, civil and financial documentation on the preliminary/basic design level. During the last few years, the preliminary design has been prepared and safety assessment conducted for the tunnel-type LL/IL rad waste repository. As the surface-type repository is one of alternatives for final disposal the design documentation for that repository type was prepared during 1994. (author)

  9. Radioactive elements on Mercury's surface from MESSENGER: implications for the planet's formation and evolution.

    Science.gov (United States)

    Peplowski, Patrick N; Evans, Larry G; Hauck, Steven A; McCoy, Timothy J; Boynton, William V; Gillis-Davis, Jeffery J; Ebel, Denton S; Goldsten, John O; Hamara, David K; Lawrence, David J; McNutt, Ralph L; Nittler, Larry R; Solomon, Sean C; Rhodes, Edgar A; Sprague, Ann L; Starr, Richard D; Stockstill-Cahill, Karen R

    2011-09-30

    The MESSENGER Gamma-Ray Spectrometer measured the average surface abundances of the radioactive elements potassium (K, 1150 ± 220 parts per million), thorium (Th, 220 ± 60 parts per billion), and uranium (U, 90 ± 20 parts per billion) in Mercury's northern hemisphere. The abundance of the moderately volatile element K, relative to Th and U, is inconsistent with physical models for the formation of Mercury requiring extreme heating of the planet or its precursor materials, and supports formation from volatile-containing material comparable to chondritic meteorites. Abundances of K, Th, and U indicate that internal heat production has declined substantially since Mercury's formation, consistent with widespread volcanism shortly after the end of late heavy bombardment 3.8 billion years ago and limited, isolated volcanic activity since.

  10. Post-closure safety assessment of near surface disposal facilities for disused sealed radioactive sources

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Seunghee; Kim, Juyoul, E-mail: gracemi@fnctech.com

    2017-03-15

    Highlights: • Post-closure safety assessment of near surface disposal facility for DSRS was performed. • Engineered vault and rock-cavern type were considered for normal and well scenario. • {sup 14}C, {sup 226}Ra, {sup 241}Am were primary nuclides contributing large portion of exposure dose. • Near surface disposal of DSRSs containing {sup 14}C, {sup 226}Ra and {sup 241}Am should be restricted. - Abstract: Great attention has been recently paid to the post-closure safety assessment of low- and intermediate-level radioactive waste (LILW) disposal facility for disused sealed radioactive sources (DSRSs) around the world. Although the amount of volume of DSRSs generated from industry, medicine and research and education organization was relatively small compared with radioactive wastes from commercial nuclear power plants, some DSRSs can pose a significant hazard to human health due to their high activities and long half-lives, if not appropriately managed and disposed. In this study, post-closure safety assessment was carried out for DSRSs generated from 1991 to 2014 in Korea in order to ensure long-term safety of near surface disposal facilities. Two kinds of disposal options were considered, i.e., engineered vault type disposal facility and rock-cavern type disposal facility. Rock-cavern type disposal facility has been under operation in Gyeongju city, republic of Korea since August 2015 and engineered vault type disposal facility will be constructed until December 2020 in the vicinity of rock-cavern disposal facility. Assessment endpoint was individual dose to the member of critical group, which was modeled by GoldSim, which has been widely used as probabilistic risk analysis software based on Monte Carlo simulation in the area of safety assessment of radioactive waste facilities. In normal groundwater scenario, the maximum exposure dose was extremely low, approximately 1 × 10{sup −7} mSv/yr, for both disposal options and satisfied the regulatory limit

  11. Use of artificial barriers in a site for surface storage of radioactive waste

    International Nuclear Information System (INIS)

    Gros, J.C.; Madoz-Escande, C.; Metivier, J.M.; Grimaud, P.

    1990-01-01

    The objective is the on site study of the influence of an injection screen on the flow in a water table of a porous medium, in order to improve the safety of a surface radioactive waste storage site. A hydrodispersive study has provided information for the definition of the role of the screen: the transfer times of the pollutant in the water table are increased by a factor of 2 and, in comparison, the concentration are clearly reduced by a factor of 10. The implantation of an injection screen in the ground should result in an improvement in the restrictive quality of the barrier and the contamination of an aquifer should be slower without interruption to the flow

  12. Methodology for safety assessment of near-surface radioactive waste disposal facilities

    International Nuclear Information System (INIS)

    Mateeva, M.

    1998-01-01

    The objective of the work is to present the conceptual model of the methodology of safety assessment of near-surface radioactive disposal facilities. The widely used mathematical models and approaches are presented. The emphasis is given on the mathematical models and approaches, which are applicable for the conditions in our country. The different transport models for analysis and safety assessment of migration processes are presented. The parallel between the Mixing-Cell Cascade model and model of Finite-Differences is made. In the methodology the basic physical and chemical processes and events, concerning mathematical modelling of the flow and the transport of radionuclides from the Near Field to Far Field and Biosphere are analyzed. Suitable computer codes corresponding to the ideology and appropriate for implementing of the methodology are shown

  13. Trench 'bathtubbing' and surface plutonium contamination at a legacy radioactive waste site.

    Science.gov (United States)

    Payne, Timothy E; Harrison, Jennifer J; Hughes, Catherine E; Johansen, Mathew P; Thiruvoth, Sangeeth; Wilsher, Kerry L; Cendón, Dioni I; Hankin, Stuart I; Rowling, Brett; Zawadzki, Atun

    2013-01-01

    Radioactive waste containing a few grams of plutonium (Pu) was disposed between 1960 and 1968 in trenches at the Little Forest Burial Ground (LFBG), near Sydney, Australia. A water sampling point installed in a former trench has enabled the radionuclide content of trench water and the response of the water level to rainfall to be studied. The trench water contains readily measurable Pu activity (~12 Bq/L of (239+240)Pu in 0.45 μm-filtered water), and there is an associated contamination of Pu in surface soils. The highest (239+240)Pu soil activity was 829 Bq/kg in a shallow sample (0-1 cm depth) near the trench sampling point. Away from the trenches, the elevated concentrations of Pu in surface soils extend for tens of meters down-slope. The broader contamination may be partly attributable to dispersion events in the first decade after disposal, after which a layer of soil was added above the trenched area. Since this time, further Pu contamination has occurred near the trench-sampler within this added layer. The water level in the trench-sampler responds quickly to rainfall and intermittently reaches the surface, hence the Pu dispersion is attributed to saturation and overflow of the trenches during extreme rainfall events, referred to as the 'bathtub' effect.

  14. Trench ‘Bathtubbing’ and Surface Plutonium Contamination at a Legacy Radioactive Waste Site

    Science.gov (United States)

    2013-01-01

    Radioactive waste containing a few grams of plutonium (Pu) was disposed between 1960 and 1968 in trenches at the Little Forest Burial Ground (LFBG), near Sydney, Australia. A water sampling point installed in a former trench has enabled the radionuclide content of trench water and the response of the water level to rainfall to be studied. The trench water contains readily measurable Pu activity (∼12 Bq/L of 239+240Pu in 0.45 μm-filtered water), and there is an associated contamination of Pu in surface soils. The highest 239+240Pu soil activity was 829 Bq/kg in a shallow sample (0–1 cm depth) near the trench sampling point. Away from the trenches, the elevated concentrations of Pu in surface soils extend for tens of meters down-slope. The broader contamination may be partly attributable to dispersion events in the first decade after disposal, after which a layer of soil was added above the trenched area. Since this time, further Pu contamination has occurred near the trench-sampler within this added layer. The water level in the trench-sampler responds quickly to rainfall and intermittently reaches the surface, hence the Pu dispersion is attributed to saturation and overflow of the trenches during extreme rainfall events, referred to as the ‘bathtub’ effect. PMID:24256473

  15. Development of a surface ionization source for the production of radioactive alkali ion beams in SPIRAL

    International Nuclear Information System (INIS)

    Eleon, C.; Jardin, P.; Gaubert, G.; Saint-Laurent, M.-G.; Alcantara-Nunez, J.; Alves Conde, R.; Barue, C.; Boilley, D.; Cornell, J.; Delahaye, P.; Dubois, M.; Jacquot, B.; Leherissier, P.; Leroy, R.; Lhersonneau, G.; Marie-Jeanne, M.; Maunoury, L.; Pacquet, J.Y.; Pellemoine, F.; Pierret, C.

    2008-01-01

    In the framework of the production of radioactive alkali ion beams by the isotope separation on-line (ISOL) method in SPIRAL I, a surface ionization source has been developed at GANIL to produce singly-charged ions of Li, Na and K. This new source has been designed to work in the hostile environment whilst having a long lifetime. This new system of production has two ohmic heating components: the first for the target oven and the second for the ionizer. The latter, being in carbon, offers high reliability and competitive ionization efficiency. This surface ionization source has been tested on-line using a 48 Ca primary beam at 60.3 A MeV with an intensity of 0.14 pA. The ionization efficiencies obtained for Li, Na and K are significantly better than the theoretical values of the ionization probability per contact. The enhanced efficiency, due to the polarization of the ionizer, is shown to be very important also for short-lived isotopes. In the future, this source will be associated with the multicharged electron-cyclotron-resonance (ECR) ion source NANOGAN III for production of multicharged alkali ions in SPIRAL. The preliminary tests of the set up are also presented in this contribution.

  16. Development of a methodology for the safety assessment of near surface disposal facilities for radioactive waste

    International Nuclear Information System (INIS)

    Simon, I.; Cancio, D.; Alonso, L.F.; Agueero, A.; Lopez de la Higuera, J.; Gil, E.; Garcia, E.

    2000-01-01

    The Project on the Environmental Radiological Impact in CIEMAT is developing, for the Spanish regulatory body Consejo de Seguridad Nuclear (CSN), a methodology for the Safety Assessment of near surface disposal facilities. This method has been developed incorporating some elements developed through the participation in the IAEA's ISAM Programme (Improving Long Term Safety Assessment Methodologies for Near Surface Radioactive Waste Disposal Facilities). The first step of the approach is the consideration of the assessment context, including the purpose of the assessment, the end-Points, philosophy, disposal system, source term and temporal scales as well as the hypothesis about the critical group. Once the context has been established, and considering the peculiarities of the system, an specific list of features, events and processes (FEPs) is produced. These will be incorporated into the assessment scenarios. The set of scenarios will be represented in the conceptual and mathematical models. By the use of mathematical codes, calculations are performed to obtain results (i.e. in terms of doses) to be analysed and compared against the criteria. The methodology is being tested by the application to an hypothetical engineered disposal system based on an exercise within the ISAM Programme, and will finally be applied to the Spanish case. (author)

  17. Design and operational considerations of United States commercial nea-surface low-level radioactive waste disposal facilities

    International Nuclear Information System (INIS)

    Birk, Sandra M.

    1997-01-01

    Low-level radioactive waste disposal standards and techniques in the United States have evolved significantly since the early 1960's. Six commercial LLW disposal facilities(Barnwell, Richland, Ward Valley, Sierra Blanca, Wake County and Boyd County) operated and proposed between 1962 and 1997. This report summarizes each site's design and operational considerations for near-surface disposal of low-level radioactive waste. These new standards and mitigating efforts at closed facilities (Sheffield, Maxey Flats, Beatty and West Valley) have helped to ensure that the public has been safely protected from LLW. 15 refs

  18. Estimates of surface deposition of radioactivity and radiation doses resulting from proposed NNTRP activities

    International Nuclear Information System (INIS)

    Gudiksen, P.H.; Peterson, K.R.

    1975-04-01

    The National Nuclear Test Readiness Program (NNTRP) has been developed by the AEC (now ERDA) and DOD to maintain a state of readiness for the prompt resumption of atmospheric nuclear testing if circumstances warrant such resumption. Such proposed tests would be conducted at the Pacific Test Site. The environmental consequences of the program were assessed. Estimations were made of the magnitude and distribution of radioactive debris deposited on the surface waters of the Pacific Ocean as a result of the test and of the total person-rem to the Continental U.S. and Hawaiian Islands populations. Since the proposed test series consists of a wide range of weapon yields to be detonated at various altitudes and the specific number and types of tests change with time according to national defense needs, a set of seven representative tests were selected for performing a parametric yield analysis at various burst locations and heights. The yields were selected to cover the low intermediate, intermediate, and low megaton ranges. The respective yields, detonation heights, and ground zero locations of the seven bursts were considered. The atmospheric transport and diffusion models that were used are described and the meteorological and radiological input data used, and the results of the calculations are included. (U.S.)

  19. Status of siting studies for a near surface repository site for radioactive wastes in the Philippines

    International Nuclear Information System (INIS)

    Valdezco, E.M.; Palattao, M.V.B.; Marcelo, E.A.; Caseria, E.S.; Venida, L.L.; Cruz, J.M. dela

    2002-01-01

    The Philippines, through the Philippine Nuclear Research Institute (PNRI), decided to conduct a study on siting a low level radioactive waste disposal facility. The infrastructure set up for this purpose, the radioactive waste disposal concept, the overall siting process, the methodology applied and preliminary results obtained are described in this paper. (author)

  20. Decontamination of radioactively contaminated surfaces - Testing of decontamination agents for textiles. 1. ed.

    International Nuclear Information System (INIS)

    1992-01-01

    The present International Standard provides an experimental method for determining the efficiency of the agents for removal radionuclides deposited on textile materials. It applies to testing the detergents which might be used in water solution for cleaning textiles contaminated by radioactive elements. It is applicable for testing the efficiency of detergents for eliminating non-radioactive dirt

  1. Natural radioactivity and external dose assessment of surface soils in Vietnam

    International Nuclear Information System (INIS)

    Huy, N. Q.; Hien, P. D.; Luyen, T. V.; Hoang, D. V.; Hiep, H. T.; Quang, N. H.; Long, N. Q.; Nhan, D. D.; Binh, N. T.; Hai, P. S.; Ngo, N. T.

    2012-01-01

    In this study, natural radioactivity in surface soils of Vietnam and external dose assessment to human population, deduced from activities of 226 Ra, 232 Th and 40 K nuclides, were determined. From 528 soil samples collected in 63 provinces of Vietnam, including five centrally governed cities, the average activities were obtained and equal to 42.77 ± 18.15 Bq kg -1 for 226 Ra, 59.84 ± 19.81 Bq kg -1 for 232 Th and 411.93 ± 230.69 Bq kg -1 for 40 K. The outdoor absorbed dose rates (OADRs) in air at 1 m above the ground level for 63 provinces were calculated, and their average value was 71.72 ± 24.72 nGy h -1 , with a range from 17.45 to 149.40 nGy h -1 . The population-weighted OADR of Vietnam was 66.70 nGy h -1 , which lies in the range of 18-93 nGy h -1 found in the World. From the OADRs obtained, it was estimated that the outdoor annual effective dose and indoor annual effective dose to the population were 0.082 and 0.458 mSv, which are higher than the corresponding values 0.07 and 0.41 mSv, respectively, of the World. The radium equivalent activity Ra eq and the external hazard index H ex of surface soils of Vietnam are lower than the corresponding permissible limits of 370 Bq kg -1 and 1, respectively. Therefore, soil from Vietnam is safe for the human population when it is used as a building material. (authors)

  2. Natural Radioactivity and External Dose Assessment of Surface Soils in Vietnam

    International Nuclear Information System (INIS)

    Huy, N.Q.; Hien, P.D.; Hoang, D.V.; Quang, N.H.; Long, N.Q.; Binh, N.T.; Hai, P.S.

    2012-01-01

    In this study, natural radioactivity in surface soils of Vietnam and external dose assessment to human population, deduces from activities of 226 Ra, 232 Th and 40 K nuclides, were determined. From 528 soil samples collected in 63 provinces of Vietnam, including five centrally governed cities, the average activities were obtained and equal to 42.77 ± 18.15 Bq kg -1 for 226 Ra, 59.84 ± 19.81 Bq kg -1 for 232 Th and 411.93 ± 230.69 Bq kg -1 for 40 K. The outdoor absorbed dose rates (OADRs) in air at 1 m above the ground level for 63 provinces were calculated, and their average value was 71.72 ± 24.72 nGy h -1 , with a range from 17.45 to 149.40 nGy h -1 . The population-weighted OADR of Vietnam was 66.70 nGy h -1 , which lies in the range of 18-93 nGy h -1 found in the World. From the OADR obtained, it was estimated that the outdoor annual effective dose and indoor annual effective dose to the population were 0.082 and 0.458 mSv, which are higher than the corresponding values 0.07 and 0.41 mSv, respectively, of the World. The radium equivalent activity Ra eq and the external hazard index H ex of surface soils of Vietnam are lower than the corresponding permissible limits of 370 Bq kg -1 and 1, respectively. Therefore, soil from Vietnam is safe for the human population when it used as a building material. (author)

  3. Preliminary safety evaluation of an aircraft impact on a near-surface radioactive waste repository

    Energy Technology Data Exchange (ETDEWEB)

    Lo Frano, R.; Forasassi, G.; Pugliese, G. [Department of Industrial and Civil Engineering (DICI), University of Pisa, Pisa (Italy)

    2013-07-01

    The aircraft impact accident has become very significant in the design of a nuclear facilities, particularly, after the tragic September 2001 event, that raised the public concern about the potential damaging effects that the impact of a large civilian airplane could bring in safety relevant structures. The aim of this study is therefore to preliminarily evaluate the global response and the structural effects induced by the impact of a military or commercial airplane (actually considered as a 'beyond design basis' event) into a near surface radioactive waste (RWs) disposal facility. The safety evaluation was carried out according to the International safety and design guidelines and in agreement with the stress tests requirements for the security track. To achieve the purpose, a lay out and a scheme of a possible near surface repository, like for example those of the El Cabril one, were taken into account. In order to preliminarily perform a reliable analysis of such a large-scale structure and to determine the structural effects induced by such a types of impulsive loads, a realistic, but still operable, numerical model with suitable materials characteristics was implemented by means of FEM codes. In the carried out structural analyses, the RWs repository was considered a 'robust' target, due to its thicker walls and main constitutive materials (steel and reinforced concrete). In addition to adequately represent the dynamic response of repository under crashing, relevant physical phenomena (i.e. penetration, spalling, etc.) were simulated and analysed. The preliminary assessment of the effects induced by the dynamic/impulsive loads allowed generally to verify the residual strength capability of the repository considered. The obtained preliminary results highlighted a remarkable potential to withstand the impact of military/large commercial aircraft, even in presence of ongoing concrete progressive failure (some penetration and spalling of the

  4. Organization of work for prevention of propagation of radioactive contamination, for decontamination of the premise surfaces and individual protective means in case of radiation accident

    International Nuclear Information System (INIS)

    Klochkov, V.N.; Vas'kin, A.G.; Filatova, V.M.

    1995-01-01

    Radiation accident results in radioactive contamination of the surface, clothes and other property. If proper measures are taken, it will prevent propagation of contamination. Decontamination of surfaces - is a complicated and tedious process. The paper has examined the measures of organization and technical aspects of prevention of propagation of radioactive contamination. Methods of decontamination of internal surfaces of premises are demonstrated, organization of the individual protective means is determined. 9 refs

  5. Estimation of mean time to failure of a near surface radioactive waste repository for PWR power stations

    International Nuclear Information System (INIS)

    Aguiar, Lais A. de; Frutuoso e Melo, P.F.; Alvim, Antonio C.M.

    2007-01-01

    This work aims at estimating the mean time to failure (MTTF) of each barrier of a near surface radioactive waste repository. It is assumed that surface water infiltrates through the barriers, reaching the matrix where radionuclides are contained, releasing them to the environment. Radioactive wastes considered in this work are low and medium level wastes (produced during operation of a PWR nuclear power station) fixed on cement. The repository consists of 6 saturated porous media barriers (top cover, upper layer, packages, basis, repository walls and geosphere). It has been verified that the mean time to failure (MTTF) of each barrier increases for radionuclides having higher retardation factor (Fr) and also that the MTTF for concrete is larger for Nickel , while for the geosphere, Plutonium gives the largest MTTF. (author)

  6. Determination of natural radioactivity of groundwater and surface of Brumadinho and Nova Lima, Brazil

    International Nuclear Information System (INIS)

    Faria, Ligia Santana de

    2013-01-01

    The municipalities of Brumadinho and Nova Lima are located in the metropolitan area of Belo Horizonte city. They are of ecological interest since they belong to an Environmental Protection Area, which is located on a very important deposit of iron ore. In addition of mineral wealth, the region has a geological characteristic that includes quartzitic conglomerates associated with uranium and significant potential underground water with hydrogeological characteristics very particular and complex, as the Quartzite Aquifer, which belongs to a geological formation called the 'Moeda Formation'. In the present work radiometric measurements were performed for 44 water samples. The samples were collected in four geographical points, three of them situated in Brumadinho (surface water) and one point situated in Nova Lima municipality (underground water). The period of sampling extended for a thirteen months period. Some of these locations was used as an alternative sampling point. Uranium and thorium concentrations of the samples were determined using an Inductively Coupled Plasma Mass Spectrometer. The content of gross alpha and gross beta activity, and the concentration of the radionuclides 226 Ra, 228 Ra e 210 Pb were determinate by using Spectrometer Liquid Scintillation. In this case was necessary to calibrate the spectrometer using 241 Am e 90 Sr/ 90 Y standards. The resultants values were compared with those recommended by the World Health Organization, Ministry of Health and the National Council of the Environment. The maximum level of water natural radioactivity found was 0,275 ± 0,052 Bq.L -1 for gross alpha radiation, 0,130 ± 0,046 Bq.L -1 for 226 Ra and 0,096 ± 0,005 Bq.L-1 for 228 Ra. The levels of gross beta activity and 210 Pb were below the detection limit. The maximum concentrations of uranium and thorium found were 0,068 μg.L -1 and 0.027 μg.L -1 respectively. (author)

  7. Radioactivity of surface water and freshwater fish in Finland in 1987

    International Nuclear Information System (INIS)

    Saxen, R.

    1990-05-01

    Changes over time in the activity concentrations of radionuclides in surface water were monitored as in the previous year. Monitoring of the radioactivity transported by the largest rivers to the Baltic Sea was also continued. All samples were analysed gammaspectrometrically and for 90 Sr. Some water samples were analysed for tritium. The dominant gamma-emitting radionuclides were 137 Cs and 134 Cs. The uneven distribution of Chernobyl deposition is still seen in the results. The activity concentrations of 137 Cs have decreased significantly: In the drainage area where the activity concentrations were highest after the Chernobyl accident the concentrations in October 1987 were only about 7% of the values in May 1986. The decrease in the activity concentrations of 90 Sr was much slighter. The study on areal and temporal changes in the activity concentrations of 137 Cs in fish was expanded in 1987. In all about 1550 samples were analysed gammaspectrometrically and a few samples were also analysed radiochemically for 90 Sr. Fifteen different fish species were included in the study. The highest activity concentrations of 137 Cs were detected in small oligotrophic lakes in the area of highest deposition. The level of 137 Cs in non-predatory fish had clearly decreased, while that in predatory fish was almost double what it had been in 1986. The average intake of 137 Cs via freshwater fish countrywide was about 4200 Bq a -1 in 1987. The average intakes in the various drainage basins ranged from about 500 Bq to 6600 Bq in 1987. The mean activity concentrations of 137 Cs in the three fish groups (predatory, non-predatory and intermediate groups) countrywide were 1300, 600 and 1300 Bq kg -1 in 1987, respectively

  8. Radioactivity in surface and coastal waters of the British Isles, 1987

    International Nuclear Information System (INIS)

    Hunt, G.J.

    1988-01-01

    This report presents the results of the environmental monitoring programme carried out during 1987 by staff of the Directorate of Fisheries Research, Lowestoft. The monitoring programme supports the Ministry's functions under the Radioactive Substances Act, 1960 (Great Britain-Parliament, 1960). The programme is set up to verify the satisfactory control of liquid radioactive waste discharges to the aquatic environment, and to ensure that the resulting public radiation exposure is within nationally-accepted limits. The monitoring is independent of similar programmes carried out by nuclear site operators as a condition of their authorisations to discharge radioactive wastes. This report also includes results of monitoring carried out on behalf of departments of the Scottish Office, the Welsh Office, the Department of the Environment for Northern Ireland [DOE (NI)] and the Channel Islands States. Where appropriate, the information presented is supplemented by results from our extensive programme of research into the behaviour of radioactivity in the aquatic environment. (author)

  9. Control of the surface radioactive contamination in the field of biological research

    International Nuclear Information System (INIS)

    Calvo, S.; Encina, A. de la; Gaspar, J.; Macias, M. T.; Sanchez, A.; Usera, F.

    2012-01-01

    The manipulation of unsealed sources in biomedical research involves significant risk of radioactive contamination. the aim of this study has been to analyze the radioactive contamination occurring in the field of biomedical research, assessing its magnitude, identifying the equipment that can be contaminated with higher probability and monitoring the evolution of the contaminations production taking into account the radioisotopes and the activities uses, and the radiation protection control applied. The data used for this study correspond to a very lengthy period of time and it have been collected in the radioactive facility, of the Centro Nacional de Biotecnologia (CSIC), a very large biological research centre that can be used perfectly as a reference for this area. The results obtained show a gradual and significant decrease in the incidence of the radioactive contamination. This is due to the optimization of radiation protection standards applied and the implementation or a systematic operational radiation protection program. (Author) 13 refs.

  10. Radioactivity in surface and coastal waters of the British Isles, 1986

    International Nuclear Information System (INIS)

    Hunt, G.J.

    1987-01-01

    The report presents the results of the environmental monitoring programme carried out during 1986 by staff of the Directorate of Fisheries Research, Lowestoft, United Kingdom. The programme was set up to verify the satisfactory control of liquid radioactive waste discharges to the aquatic environment, and to ensure that the resulting public radiation exposure is within nationally-accepted limits. The environmental programme includes monitoring the environmental consequences of discharges of liquid radioactive wastes from four British Nuclear Fuels plc sites - at Sellafield, Springfield, Capenhurst and Chapelcross, and monitoring the environment impact of liquid radioactive discharges from Winfrith and Dounraey. Monitoring is also carried out near nuclear power stations operated by the electricity boards, near Naval establishments, near Amersham International plc, and the marine environment of the Channel Islands States. Results are also presented on the monitoring of the freshwater environment for radioactivity from the Chernobyl reactor accident. (U.K.)

  11. Evaluation of indigenously developed plastic scintillator sheet detector for surface radioactive contamination monitoring application

    International Nuclear Information System (INIS)

    Sahani, R.M.; Chaudhary, H.S.; Mahala, V.K.; Senwar, K.R.; Meena, J.P.

    2018-01-01

    Radioactive contamination may be caused by release of radioactivity in the environment due to accident at nuclear plant/reactor or spillage of loose radioactive materials in a laboratory. The protection of workers from potentially hazardous radiations emitted by the contaminants is a matter of prime concern. The detection of such radiations requires a monitoring system capable of measuring the level of radioactivity at the contaminated site. Plastic scintillators are widely used for large area radiation monitoring due to the ease of preparation in different shape and sizes. These detectors are sensitive to beta and gamma radiation therefore can be used for monitoring of beta and gamma contamination. In this paper, performance results of indigenously developed plastic scintillator sheet of area 800 cm 2 are reported

  12. Radioactivity in surface and coastal waters of the British Isles, 1988

    International Nuclear Information System (INIS)

    Hunt, G.J.

    1989-01-01

    This report presents the results of the aquatic environmental monitoring programme performed during 1988 by the Ministry of Agriculture, Fisheries and Food's (MAFF's) Directorate of Fisheries Research (DFR). Radioactivity measurements are made in aquatic organisms and environmental materials in the vicinity of nuclear establishments including BNFL, UKAEA, nuclear power stations operated by the electricity boards, defence establishments and Amersham International. A summary of estimated public radiation exposures in 1988, relating to liquid radioactive waste discharges from nuclear establishments is presented. (UK)

  13. Socio-economic and other non-radiological impacts of the near surface disposal of radioactive waste

    International Nuclear Information System (INIS)

    2002-09-01

    The objective of this report is to introduce, in a generic sense, the elements that could comprise a socio-economic and non-radiological environmental impact assessment. The various social, economic and environmental impacts that could be associated with surface and near surface disposal are discussed through factors that could apply at the local, regional or national level. Impact management is also discussed. The report also introduces concepts to help Member States develop their own approaches to undertaking impact assessment and management. The report is intended to complement IAEA documents on the technology and safety aspects of the near surface disposal of radioactive waste. The scope of this report includes a discussion of a range of social, economic and nonradiological environmental impacts relevant to surface and near surface disposal and illustrations of some impact management measures

  14. Standard criteria for disposal of liquid radioactive wastes from nuclear power plants into surface waters (river systems)

    International Nuclear Information System (INIS)

    Pisarev, V.V.; Tsybizov, I.S.

    1976-01-01

    Radioactive products discharge into natural water streams results in the necessity to regulate nuclear power plant discharges to ensure radiation safety (RS) for population using a river and surrounding river territory. To ensure RS it is necessary to set scientific-founded standards of permissible discharge level of liquid radioactive wastes (LRW) from nuclear power plant assuring observance of hygienic requirements for surface water puring. Volume of permissible LRW discharge into river systems must be set both with provision for concrete physical-geographycal conditions, specficity of utilizing the river and river valley and social-economical peculiarities of crtical population groups. The value of permissible LRW discharge into river systems is determined by three criterion groups: radiological, ecological and hydrological ones. By means of radiological group the internal and external irradiation doses for the whole body and its separate organs are set and RS of population is determined. Ecological criteria include a number of parameters (coefficients of accumulation, distribution and transition) determining quantitative ratios between radioactive element contents in water and separate links of biological chains: soil/water, fish/water, vegetables/water and others. Hydrological criteria determine the degree of waste dilution in rivers, control radioactive contamination of flood-lands areas and in common with ecological criteria determine radionuclide contents in soil and food products. A method of determining average annual values of LRW dilution in river waters is presented [ru

  15. Development of performance assessment methodology for establishment of quantitative acceptance criteria of near-surface radioactive waste disposal

    Energy Technology Data Exchange (ETDEWEB)

    Kim, C. R.; Lee, E. Y.; Park, J. W.; Chang, G. M.; Park, H. Y.; Yeom, Y. S. [Korea Hydro and Nuclear Power Co., Ltd., Seoul (Korea, Republic of)

    2002-03-15

    The contents and the scope of this study are as follows : review of state-of-the-art on the establishment of waste acceptance criteria in foreign near-surface radioactive waste disposal facilities, investigation of radiological assessment methodologies and scenarios, investigation of existing models and computer codes used in performance/safety assessment, development of a performance assessment methodology(draft) to derive quantitatively radionuclide acceptance criteria of domestic near-surface disposal facility, preliminary performance/safety assessment in accordance with the developed methodology.

  16. Handling of radioactive sources in Ecuador

    International Nuclear Information System (INIS)

    Benitez, Manuel

    2000-01-01

    This document describes the following aspects: sealed and unsealed radioactive sources, radiation detectors, personnel and area monitoring, surface pollution, radioactive wastes control and radioactive sources transferring. (The author)

  17. Study of a high surface gas triode for detecting atomic or nuclear particles; Etude d'une triode a gaz a grande surface detectrice de particules atomiques ou nucleaires

    Energy Technology Data Exchange (ETDEWEB)

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

    1967-06-15

    A triode filled with xenon at atmospheric pressure can be used as an X-ray detector since it produces an appreciable amount of light per quantum absorbed. Various methods are described for studying and reducing the deadtime after the passage of a spark. This detector can be used in medicine for the detection of tumours and also for the rapid recording of diffraction diagrams. (author) [French] Une triode, remplie de xenon a la pression atmospherique, sert de detecteur de rayors X en fournissant une quantite de lumiere importante par quantum absorbe. Diverses methodes sont decrites permettant d'etudier et de reduire le temps mort apres le passage d'une etincelle. Ce detecteur sert a la localisation de tumeurs en medecine et a l'enregistrement rapide de diagrammes de diffraction. (auteur)

  18. Study of a high surface gas triode for detecting atomic or nuclear particles; Etude d'une triode a gaz a grande surface detectrice de particules atomiques ou nucleaires

    Energy Technology Data Exchange (ETDEWEB)

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

    1967-06-15

    A triode filled with xenon at atmospheric pressure can be used as an X-ray detector since it produces an appreciable amount of light per quantum absorbed. Various methods are described for studying and reducing the deadtime after the passage of a spark. This detector can be used in medicine for the detection of tumours and also for the rapid recording of diffraction diagrams. (author) [French] Une triode, remplie de xenon a la pression atmospherique, sert de detecteur de rayors X en fournissant une quantite de lumiere importante par quantum absorbe. Diverses methodes sont decrites permettant d'etudier et de reduire le temps mort apres le passage d'une etincelle. Ce detecteur sert a la localisation de tumeurs en medecine et a l'enregistrement rapide de diagrammes de diffraction. (auteur)

  19. Variations in uranium and radioactivity levels in surface and ground water at selected sites in British Columbia, April 1980 - March 1981

    International Nuclear Information System (INIS)

    1981-07-01

    This report summarizes field and analytical work carried out between April, 1980 and March, 1981 on a program to investigate uranium and radioactivity levels in potable surface and ground water in selected regions throughout British Columbia

  20. Design and operational considerations of United States commercial near-surface low-level radioactive waste disposal facilities

    International Nuclear Information System (INIS)

    Birk, S.M.

    1997-10-01

    In accordance with the Low-Level Radioactive Waste Policy Amendments Act of 1985, states are responsible for providing for disposal of commercially generated low-level radioactive waste (LLW) within their borders. LLW in the US is defined as all radioactive waste that is not classified as spent nuclear fuel, high-level radioactive waste, transuranic waste, or by-product material resulting from the extraction of uranium from ore. Commercial waste includes LLW generated by hospitals, universities, industry, pharmaceutical companies, and power utilities. LLW generated by the country''s defense operations is the responsibility of the Federal government and its agency, the Department of Energy. The commercial LLRW disposal sites discussed in this report are located near: Sheffield, Illinois (closed); Maxey Flats, Kentucky (closed); Beatty, Nevada (closed); West Valley, New York (closed); Barnwell, South Carolina (operating); Richland, Washington (operating); Ward Valley, California, (proposed); Sierra Blanca, Texas (proposed); Wake County, North Carolina (proposed); and Boyd County, Nebraska (proposed). While some comparisons between the sites described in this report are appropriate, this must be done with caution. In addition to differences in climate and geology between sites, LLW facilities in the past were not designed and operated to today''s standards. This report summarizes each site''s design and operational considerations for near-surface disposal of low-level radioactive waste. The report includes: a description of waste characteristics; design and operational features; post closure measures and plans; cost and duration of site characterization, construction, and operation; recent related R and D activities for LLW treatment and disposal; and the status of the LLW system in the US

  1. A hydrochemical and isotopic case study around a near surface radioactive waste disposal

    International Nuclear Information System (INIS)

    Szanto, Zs.; Svingor, E.; Futo, I.; Palcsu, L.; Molnar, M.; Rinyu, L.

    2007-01-01

    As part of the site characterisation program for the near surface radioactive waste treatment and disposal facility (RWTDF) at Puespoekszilagy, Hungary, water quality and environmental isotope investigations have been carried out. Water samples for major ion chemistry, tritium, 14 C and stable isotope ratio measurements (δ 18 O, δD, δ 34 S, δ 13 C) were taken quarterly from the observation wells, the streams and the precipitation during the period 1999-2001. The chemical composition of groundwaters presented a continuous transition from waters situated on one side to waters on the top and on the other slope of the disposal suggesting the mixing of the three hydrochemical ''endmembers''. Most of δD and δ 18 O data were situated between GMWL and LMWL (δD = 7.2 x δ 18 O - 1 permille) with Oligocene aquifer presenting recharge of Pleistocene origin and water on the top and the gentle slope of the hill presenting recharge of Holocene origin. δ 34 S values of dissolved sulphates varied in a wide range (-14.2 permille to +5.4 permille). The tritium in precipitation varied between 4.4 and 18.1 TU with an annual weighted average of 10 ± 0.3 TU. The streams showed larger fluctuations than the wells, but the changes of δ 18 O, δD and T were small compared to those in precipitation (showing seasonal variation). Stable isotope, tritium and radiocarbon data proved that the replenishment of groundwater is slow on the steeper side and the direction of water movement is toward the gentle slope of the hill. It was judged that this path is the one that is most likely to give rise to high doses and, therefore, was used in the hydrological modelling of the safety assessment that followed the present work. The possibility that there may also be transport through the unsaturated zone and systems of perched water tables in layers 1 and 2 to both the Szilagyi and Nemedi streams cannot be excluded; the transport along these pathways is likely to be intermittent. (orig.)

  2. Preparation of safety analysis reports (SARs) for near surface radioactive waste disposal facilities. Format and content of SARs

    International Nuclear Information System (INIS)

    1995-02-01

    All facilities at which radioactive wastes are processed, stored and disposed of have the potential for causing hazards to humans and to the environment. Precautions must be taken in the siting, design and operation of the facilities to ensure that an adequate level of safety is achieved. The processes by which this is evaluated is called safety assessment. An important part of safety assessment is the documentation of the process. A well prepared safety analysis report (SAR) is essential if approval of the facility is to be obtained from the regulatory authorities. This TECDOC describes the format and content of a safety analysis report for a near surface radioactive waste disposal facility and will serve essentially as a checklist in this respect

  3. A case study on the safety assessment for groundwater pathway in a near-surface radioactive waste disposal facility

    International Nuclear Information System (INIS)

    Park, Joo Wan; Chang, Keun Moo; Kim, Chang Lak

    2002-01-01

    A safety assessment is carried out for the near-surface radioactive waste disposal in the reference engineered vault facility. The analysis is mainly divided into two parts. One deals with the release and transport of radionuclide in the vault and unsaturated zone. The other deals with the transport of radionuclide in the vault and unsaturated zone. The other deals with the transport of radionuclide in the saturated zone and radiological impacts to a human group under well drinking water scenario. The parameters for source-term, geosphere and biosphere models are mainly obtained from the site specific data. The results show that the annual effective doses are dominated by long lived, mobile radionuclides and their associated daughters. And it is found that the total effective dose for drinking water is far below the general criteria of regulatory limit for radioactive waste disposal facility

  4. 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)

  5. Radioactivity in surface and coastal waters of the British Isles, 1980

    International Nuclear Information System (INIS)

    Hunt, G.J.

    1982-01-01

    Results are presented for an environmental monitoring programme performed during 1980 by the Fisheries Radiobiological Loaboratory. The programme was set up to verify the satisfactory control of liquid radioactive waste discharges from UK nuclear establishments to the aquatic environment. The results showed that all exposures were well within the ICRP-recommended limit for members of the public. Discharges from BNFL's Sellafield Site gave rise to the highest exposures. The collective effective dose equivalent to the UK population from liquid radioactive discharges in 1980 was 100 man-Sv, a reduction from 130 man-Sv reported for 1979. (U.K.)

  6. Radioactive contamination of some rubber or plastic surfaces by fission products. Decontamination tests; Contamination radioactive de quelques surfaces en caoutchouc ou en matiere plastique par des produits de fission. Essais de decontamination

    Energy Technology Data Exchange (ETDEWEB)

    Mestre, E.; Sautiez, N.

    1957-10-15

    With the objective of notably addressing the contamination and decontamination of gloves and floor covering, this report first presents some characteristics of contaminating radioactive materials (nature, physical and chemical condition), of contaminated surfaces (surface condition, surface nature), and of decontamination processes (physical, chemical or mechanical action). It describes the operational modality implemented to test decontamination processes on various glove or flooring materials: sample preparation, counting, decontamination, reproducibility of decontamination tests, results in terms of activity reduction. It more precisely describes the tested samples: short gloves, gloves from glove boxes, floor and wall coverings. Results are presented and discussed in terms of sample susceptibility to contamination, and of decontamination, but also for re-contamination tests after a Nab-based decontamination (susceptibility to contamination, decontamination gain)

  7. A model to determine the radiological implications of non-fixed radioactive contamination on the surfaces of packages and conveyances

    International Nuclear Information System (INIS)

    Hughes, J.S.; Warner Jones, S.M.; Lizot, M.T.; Perrin, M.L.; Thierfeld, S.; Schroedl, E.; Schwarz, G.; Rawl, R.; Munakata, M.; Hirose, M.

    2004-01-01

    The surfaces of packages and conveyances used to transport radioactive materials can sometimes become contaminated with radioactive material. This usually occurs as a result of the transfer of radioactive material from areas in which these packages and conveyances are handled. This contamination may subsequently be transferred to transport equipment, workers and to areas accessible to the public. This can represent a significant radiation safety issue that requires careful management. The current regulatory limits for non-fixed contamination on packages and conveyances have been in use for over 40 years, and are based on a simple exposure model. However, the bases on which these limits were derived have been subject to changes, as a result of successive revisions of international recommendations. In recognition of this need for a review and analysis of the current contamination limits an IAEA Co-ordinated Research Project (CRP) on the ''Radiological Aspects of Package and Conveyance Non-Fixed Contamination'' was initiated to review the scientific basis for the current regulatory limits for surface contamination. The CRP was also to develop guidance material for evaluating the radiological significance of surface contamination to workers and the public in light of state-of-the-art research, technical developments and current transport practices. The specific objectives of the work undertaken within this multi-national CRP were, in accordance with the terms of reference: To ensure that appropriate models exist for all package types including consideration of the aspects pertinent for assessing and revising a surface contamination model for transport. To collect - where possible - contamination, operational and dosimetric data to ensure modelling consistency. To use models for assessing the limitations and optimisation of radiation doses incurred in transport operations, and to consider preventive methods for package and conveyance contamination

  8. Surface storage of vitrified high-level radioactive waste in reinforced-concrete casks

    International Nuclear Information System (INIS)

    Beale, H.; George, M.W.; Robertson, T.J.M.

    1982-06-01

    The feasibility of storing canisters containing vitrified high level radioactive waste in reinforced concrete casks is examined. This preliminary study identifies the limitations and probable cost of such a store and leads to the conclusion that the concept is feasible. (author)

  9. Transport processes associated with the initial elevated concentrations of Chernobyl radioactivity in surface air in the United States

    International Nuclear Information System (INIS)

    Larsen, R.J.; Haagenson, P.L.; Reiss, N.M.

    1989-01-01

    Elevated concentrations of radioactivity from the Chernobyl accident were encountered in the surface air over the United States along the east coast and in the north-west on 9 and 10 May 1986. The nearly simultaneous arrival of radioactive debris at widely separated locations resulted from different paths being taken by the debris released at different times during the course of the accident. Debris released during the explosion at the Chernobyl reactor was transported across the Arctic, within the lower troposphere, and zonally across Asia and the North Pacific Ocean, within the mid-troposphere. This debris descended into the planetary boundary layer along the east coast of the US. The descent was associated with a quasi-stationary cyclone located over the western North Atlantic Ocean. Debris that had a different composition of radioactivity was released from the damaged reactor during the week immediately following the initial explosion. This debris was then transported zonally across Asia and the North Pacific Ocean within the planetary boundary layer and lower troposphere and was swept into the north-western US. (author)

  10. 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.)

  11. Risk-based approach to long-term safety assessment for near surface disposal of radioactive waste in Korea

    International Nuclear Information System (INIS)

    Jeong, C.W.; Kim, K.I.; Lee, J.I.

    2000-01-01

    This paper presents the Korean regulatory approach to safety assessment consistent with probabilistic, risk-based long-term safety requirements for near surface disposal facilities. The approach is based on: (1) From the standpoint of risk limitation, normal processes and probabilistic disruptive events should be integrated in a similar manner in terms of potential exposures; and (2) The uncertainties inherent in the safety assessment should be reduced using appropriate exposure scenarios. In addition, this paper emphasizes the necessity of international guidance for quantifying potential exposures and the corresponding risks from radioactive waste disposal. (author)

  12. Radioactivity on the surfaces of computer monitors and television screens due to progeny palatal

    International Nuclear Information System (INIS)

    Abdel-Nady, A.; Morsy, A.A.

    2002-01-01

    Computer monitors and television screens can collect radon progeny. Radon decay forming meta-stable progeny, namely, Po-218, Po-214, and Po-210, which are found mostly in positively, charged aerosol particles. These particles are attract by the large negative field of a video display terminals (VDT) leading to buildup of radioactivity on the VDT screen. The charged aerosol particles might drift in the electric field between the VDT and the operator and be accelerated into the operator's face. The aim of this work is to measure these phenomena set of ultra-sensitive TASTRAK detectors used to measure the plate out of positively charged radioactive radon progeny. The track detectors were fixed on the outer monitor screen. For an occupational computer worker spending 200 days per year for 6 hours a day. It was found that the mean dose equivalent was 1.77 mSv, 0.25 mSv/year for normal CRT and LCD monitors respectively

  13. Development of a quality assurance safety assessment database for near surface radioactive waste disposal

    International Nuclear Information System (INIS)

    Park, J. W.; Kim, C. L.; Park, J. B.; Lee, E. Y.; Lee, Y. M.; Kang, C. H.; Zhou, W.; Kozak, M. W.

    2003-01-01

    A quality assurance safety assessment database, called QUARK (QUality Assurance program for Radioactive waste management in Korea), has been developed to manage both analysis information and parameter database for safety assessment of Low- and Intermediate-Level radioactive Waste (LILW) disposal facility in Korea. QUARK is such a tool that serves QA purposes for managing safety assessment information properly and securely. In QUARK, the information is organized and linked to maximize the integrity of information and traceability. QUARK provides guidance to conduct safety assessment analysis, from scenario generation to result analysis, and provides a window to inspect and trace previous safety assessment analysis and parameter values. QUARK also provides default database for safety assessment staff who construct input data files using SAGE(Safety Assessment Groundwater Evaluation), a safety assessment computer code

  14. Radioactivity in surface and coastal waters of the British Isles, 1985

    International Nuclear Information System (INIS)

    Hunt, G.J.

    1986-01-01

    A summary of estimated public radiation exposures in 1985 resulting from liquid radioactive waste discharges from nuclear establishments monitored by the Directorate of Fisheries Research is presented in tabular form. The exposures are expressed in terms of the committed effective dose equivalents to, or as doses to skin of, members of the critical groups. Results for internal exposures incorporate the enhanced gut transfer factor for plutonium except where a more appropriate value is justified. (author)

  15. Environmental radioactivity monitoring in surface water from an ecological point of view

    International Nuclear Information System (INIS)

    Huebel, K.

    1981-01-01

    For each bigger river section, ecological transition factors for the individual relevant media are to be determined. Because of the great biologic variability long-term investigations are necessary. For most of the nuclides, the deviations are more than two orders of magnitude; therefore, many values are necessary for guaranteeing the statistics. Here, the 'general environmental radioactivity monitoring' is offered. There are results (Bavaria) from 25 years which represent extensive material for the purposes of radio-ecology. (DG) [de

  16. The decontamination of soft-plated nickel surfaces compared to alternative surface materials used in radioactive transport and storage containers

    International Nuclear Information System (INIS)

    Zwicky, H.U.; Bedenig, D.O.; Bohringer, I.M.; Petrik, F.

    1983-01-01

    Surfaces of raw, nickel-plated, and epoxy-coated spheroidal graphite cast iron, together with stainless steel, were contaminated with a modified fission product solution then conditioned by heat treatment. This was followed by a variety of simple decontamination techniques. It was shown that the ease of removal of contaminations similar to those expected on a dry storage container surface is significantly affected by the roughness of the surface. The raw cast iron surface was virtually impossible to significantly decontaminate. Highest decontamination factors were obtained on nickel-plated and epoxy-painted surfaces using steam/detergent mixtures. Stainless steel only performed well in a polished condition. In a supplementary irradiation experiment, scanning electron microscopy indicated visible decomposition of an epoxy-painted surface at a gamma dose of 3.1 X 10 6 Gy (3.1 X 10 8 rad). A nickel-plated surface did not undergo any visible changes at the same dose

  17. Study of 'inadvertent human intrusion or rare natural event scenarios' for sub-surface disposal of radioactive waste

    International Nuclear Information System (INIS)

    Nakatani, Takayoshi; Ishitoya, Kimihide; Funabashi, Hideyuki; Sugaya, Toshikatsu; Sone, Tomoyuki; Shimada, Hidemitsu; Nakai, Kunihiro

    2010-03-01

    Japan Atomic Energy Agency (JAEA) is making preparations for the sub-surface disposal of radioactive wastes, in an integrated fashion according to the properties of the waste material regardless of the generators or waste sources. In this study, 'Inadvertent Human Intrusion or Rare Natural Event Scenarios' of 'Three Types scenarios' was considered according to the standard of the Atomic Energy Society of Japan (AESJ) on the sub-surface disposal system that was based on 'Basic Policy for Safety Regulation Concerning Land Disposal of Low-Level Radioactive Waste (Interim Report)' by Nuclear Safety Commission of Japan (NSC). Selection of the assessed scenarios, development of the assessment tool and preliminary exposure dose assessment for general public were conducted. Among the assessed scenarios, the exposure dose of 'well water drinking scenario' was the highest under the very conservative assessment condition. This scenario assumed that the groundwater in Excavation Disturbed Zone (EDZ) was directly used as drinking water without any dilution. Although this was very conservative condition and the result exceeded 10 mSv/y, it stayed under the upper limit of standard dose value for 'Inadvertent Human Intrusion or Rare Natural Event Scenarios' (10 - 100 mSv/y). (author)

  18. Safety assessment on the human intrusion scenarios of near surface disposal facility for low and very low level radioactive waste

    Energy Technology Data Exchange (ETDEWEB)

    Hong, Sung Wook; Park, Jin Baek [Korea Radioactive Waste Agency, Daejeon (Korea, Republic of); Park, Sang Ho [Chungnam National University, Daejeon (Korea, Republic of)

    2016-03-15

    The second-stage near surface disposal facility for low and very low level radioactive waste's permanent disposal is to be built. During the institutional control period, the inadvertent intrusion of the general public is limited. But after the institutional control period, the access to the general public is not restricted. Therefore human who has purpose of residence and resource exploration can intrude the disposal facility. In this case, radioactive effects to the intruder should be limited within regulatory dose limits. This study conducted the safety assessment of human intrusion on the second-stage surface disposal facility through drilling and post drilling scenario. Results of drilling and post drilling scenario were satisfied with regulatory dose limits. The result showed that post-drilling scenario was more significant than drilling scenario. According to the human intrusion time and behavior after the closure of the facility, dominant radionuclide contributing to the intruder was different. Sensitivity analyses on the parameters about the human behavior were also satisfied with regulatory dose limits. Especially, manual redistribution factor was the most sensitive parameter on exposure dose. A loading plan of spent filter waste and dry active waste was more effective than a loading plan of spent filter waste and other wastes for the radiological point of view. These results can be expected to provide both robustness and defense in depth for the development of safety case further.

  19. Surface erosion and hydrology of earth covers used in shallow land burial of low-level radioactive waste

    International Nuclear Information System (INIS)

    Bent, G.C.

    1988-01-01

    Shallow land burial is the current method of disposal of low-level radioactive waste in the United States. The most serious technical problems encountered in shallow land burial are water-related. Water is reported to come into contact with the waste by erosion of earth covers or through infiltration of precipitation through the earth covers. The objectives of this study were to: compare and evaluate the effects of crested wheatgrass and streambank wheatgrass on surface erosion of simulated earth covers at Idaho National Engineering Laboratory (INEL), characterize the surface hydrology, and estimate cumulative soil loss for average and extreme rainfall events and determine if the waste will become exposed during its burial life due to erosion. 30 refs., 26 figs., 21 tabs

  20. Radioactivity in surface and coastal waters of the British Isles, 1989

    International Nuclear Information System (INIS)

    Hunt, G.J.

    1990-01-01

    This report presents the results of the environmental monitoring programme carried out during 1989 by staff of the Ministry of Agriculture, Fisheries and Food's (MAFF's) Directorate of Fisheries Research (DFR), Lowestoft. To set the monitoring results from the regular programme in context, liquid radioactive discharges from UK nuclear establishments to the aquatic environment in 1989 are first summarised. Before the results are presented, an explanatory section gives details of methods of analysis and presentation and explains how results are interpreted in terms of public radiation exposures. (author)

  1. Radioactivity in surface and coastal waters of the British Isles, 1990

    International Nuclear Information System (INIS)

    Camplin, W.C.

    1992-01-01

    This report presents the results of the environmental monitoring programme carried out during 1990 by staff of the Ministry of Agriculture, Fisheries and Food's (MAFF's) Directorate of Fisheries Research (DFR), Lowestoft. To set the monitoring results from the regular programme in context, liquid radioactive discharges from UK nuclear establishments to the aquatic environment in 1990 are first summarised. Before the results are presented, and explanatory section gives details of methods of analysis and presentation and a sub-section explains how results are interpreted in terms of public radiation exposures. (author)

  2. Bentonite engineered barrier building method for radioactive waste on sub-surface disposal test project

    International Nuclear Information System (INIS)

    Mori, Takuo; Takahashi, Shinichi; Takeuchi, Kunifumi; Namiki, Kazuto

    2008-01-01

    The engineering barriers such as clay and concrete materials are planned to use for covering radioactive waste in cavern-type disposal facility. The requirement to clay barrier is very low permeability, which could be satisfied by high density Bentonite, and such a compaction method will be needed. Two methods, compaction and air shot, were tested in engineering scale for constructing a high-density clay barrier. Two types of compaction equipments, 'Teasel plate' and 'Plate compacter', were developed and engineering scale experiments were performed for compacting Bentonite only and Bentonite-sand-aggregate mixture. As a result, the Teasel plate can reach higher density Bentonite in relatively short time in comparison to other equipments. While, regarding air shot method, an air-shot machine in a tunnel construction site was tested by different water adding methods (wet, dry, and half wet). It is concluded that the dry and half wet constructing methods will achieve reasonable workability. As a result, the best construction option can be chosen according to the locations of radioactive waste facility. (author)

  3. Radioactivity in surface and coastal waters of the British Isles, 1979

    International Nuclear Information System (INIS)

    Hunt, G.J.

    1981-01-01

    A report is presented on the results of an environmental monitoring programme carried out during 1979 by the Directorate's Aquatic Environment Protection Division at the Fisheries Radiobiological Laboratory (FRL). The programme was set up to verify the satisfactory control of liquid radioactive waste discharges from nuclear establishments to the aquatic environment and to ensure that the resulting public radiation exposure is within nationally-accepted limits. The monitoring results mainly concerned British Nuclear Fuels at Sellafield, Springfields, Capenhurst and Chapelcross; the United Kingdom Atomic Energy Authority at Winfrith and Dounreay; the nuclear power stations operated by the electricity boards at Berkeley, Bradwell, Dungeness, Hartlepool, Heysham, Hinkley Point, Hunterston, Sizewell, Trawsfyndd and Wylfa. Monitoring results are also presented for UK Naval establishments, Amersham International Limited and the Channel Islands. A summary of estimated public radiation exposures in 1979 resulting from liquid radioactive discharges to the aquatic environment from nuclear establishments monitored by FRL showed that all exposures were well within the ICRP dose equivalent limit. (U.K.)

  4. Radioactivity in surface and coastal waters of the British Isles, 1982

    International Nuclear Information System (INIS)

    Hunt, G.J.

    1984-01-01

    The subject is covered in sections, entitled: introduction: discharges of [liquid, solid] radioactive waste; methods of analysis and of presentation and interpretation of results; British Nuclear Fuels plc (BNFL) Sellafield, Cumbria (the fish and shellfish consumption pathway; external exposure; porphyra/ laverbread pathway; other surveys); Springfields, Lancashire; Capenhurst, Cheshire; Chapelcross, Dumfriesshire); United Kingdom Atomic Energy Authority (Atomic Energy Establishment, Winfrith, Dorset; Dounreay Nuclear Power Development Establish-ment, Caithness); nuclear power stations operated by the electricity boards (Berkeley, Gloucestershire and Oldbury, Avon; Bradwell, Essex; Dungeness, Kent; Hartlepool, Cleveland; Heysham, Lancashire; Hinkley Point, Somerset; Hunterston, Ayrshire; Sizewell, Suffolk; Trawsfynydd, Gwynedd; Wylfa, Gwynedd; naval establishments; Amersham International plc; Channel Islands monitoring; summary and conclusions. (U.K.)

  5. Technical considerations in the design of near surface disposal facilities for radioactive waste

    International Nuclear Information System (INIS)

    2001-11-01

    Good design is an important step towards ensuring operational as well as long term safety of low and intermediate level waste (LILW) disposal. The IAEA has produced this report with the objective of outlining the most important technical considerations in the design of near surface disposal facilities and to provide some examples of the design process in different countries. This guidance has been developed in light of experience gained from the design of existing near surface disposal facilities in a range of Member States. In particular the report provide information on design objective, design requirements, and design phases. The report focuses on: near surface disposal facilities accepting solidified LILW; disposal facilities on or just below the ground surface, where the final protective covering is of the order of a few metres thick; and disposal facilities several tens of metres below the ground surface (including rock cavern type facilities)

  6. Uses of ANSI/HPS N13.12-1999, "Surface and Volume Radioactivity Standards for Clearance" and Comparison with Existing Standards

    Energy Technology Data Exchange (ETDEWEB)

    Stansbury, Paul S.; Strom, Daniel J.

    2001-04-30

    In August of 1999, the American National Standards Institute (ANSI) approved a standard for clearance of materials contaminated with residual levels of radioactivity. "Clearance," as used in the standard, means the movement of material from the control of a regulatory agency to a use or disposition that has no further regulatory controls of any kind. The standard gives derived screening levels (DSLs) in Bq/g and Bq/cm2 for 50 radionuclides. Items or materials with residual surface and volume radioactivity levels below the DSLs can be cleared, that is, managed without regard to their residual radioactivity. Since federal agencies are to use voluntary, industry standards developed by the private sector whenever possible, the standard should play an important role in DOE's regulatory process. The thrust of this report is to explain the standard, make simple observations on its usefulness to DOE, and to explore uses of the standard within DOE facilities beyond the clearance of radioactive materials.

  7. CESARR V.2 manual: Computer code for the evaluation of surface storage of low and medium level radioactive waste

    International Nuclear Information System (INIS)

    Moya Rivera, J.A.; Bolado Lavin, R.

    1997-01-01

    CESARR (Code for the safety evaluation of low and medium level radioactive waste storage). This code was developed for the safety probabilistic evaluations in the facilities of low-and medium level radioactive waste storage

  8. Statistical approach for derivation of quantitative acceptance criteria for radioactive wastes to near surface disposal facility

    International Nuclear Information System (INIS)

    Park, Jin Beak; Park, Joo Wan; Lee, Eun Yong; Kim, Chang Lak

    2003-01-01

    For reference human intrusion scenarios constructed in previous study, a probabilistic safety assessment to derive the radionuclide concentration limits for the low- and intermediate- level radioactive waste disposal facility is conducted. Statistical approach by the latin hypercube sampling method is introduced and new assumptions about the disposal facility system are examined and discussed. In our previous study of deterministic approach, the post construction scenarios appeared as most limiting scenario to derive the radionuclide concentration limits. Whereas, in this statistical approach, the post drilling and the post construction scenarios are mutually competing for the scenario selection according to which radionuclides are more important in safety assessment context. Introduction of new assumption shows that the post drilling scenario can play an important role as the limiting scenario instead of the post-construction scenario. When we compare the concentration limits between the previous and this study, concentrations of radionuclides such as Nb-94, Cs-137 and alpha-emitting radionuclides show elevated values than the case of the previous study. Remaining radionuclides such as Sr-90, Tc-99 I-129, Ni-59 and Ni-63 show lower values than the case of the previous study

  9. Radioactivity in surface air and precipitation in Japan after the Chernobyl accident

    International Nuclear Information System (INIS)

    Higuchi, Hideo; Fukatsu, Hiroko; Hashimoto, Takeo; Nonaka, Nobuhiro; Yoshimizu, Katsumi; Omine, Mamoru; Takano, Naoto; Abe, Toshihiko

    1988-01-01

    Radioactive plumes from the Chernobyl reactor accident first passed over Japan on 3 May 1986. Measurements of 103 Ru, 131 I and 137 Cs in rainfall and airborne dust collected at Chiba near Tokyo show that, in fact, at least two or more kinds of plume arrived during May. Their altitudes were calculated to be about 1500 m in early May and 6300 m in late May. Radionuclides detected in 33 precipitation samples collected by the network of radiation monitoring stations from 1 to 22 May were 7 Be, 89 Sr, 90 Sr, 95 Zr, 95 Nb, 103 Ru, 106 Ru, sup(110m)Ag, 125 Sb, sup(129m)Te, 131 I, 132 Te, 132 I, 134 Cs, 136 Cs, 137 Cs, 140 Ba, 140 La, 141 Ce and 144 Ce. The radiation was characterized by higher levels of the volatile nuclides, such as 103 Ru, 132 Te, 131 I and 137 Cs, than fallout levels in nuclear weapons testing, and by activity ratios of 0.48 and 14 for, respectively, 134 Cs/ 137 Cs and 89 Sr/ 90 Sr, as on 26 April. the fallout activity was higher in Northwestern Japan, the average depositions of 90 Sr and 137 Cs in Japan from 1 May (or 30 April) to 22 May being 1.4 Bq m -2 and 95 Bq m -2 , inventories which are 14 and 550 times higher than the pre-Chernobyl values. (author)

  10. Une perspective interactionniste

    Directory of Open Access Journals (Sweden)

    Joëlle Morrissette

    2010-02-01

    Full Text Available Cet article vise à montrer l’intérêt de puiser à la sociologie pour conduire des recherches dans le domaine de l’éducation. Plus précisément, il sera question de la contribution d’une perspective interactionniste pour appréhender un objet attaché à l’évaluation des apprentissages des élèves. Comme on le verra, s’inspirer en particulier d’auteurs attachés à la tradition de l’interactionnisme symbolique amène à se situer en marge des manières de dire et de faire habituelles des investigations portant sur cet objet, de la phase de problématisation à celle de l’analyse, au profit d’un point de vue (resocialisant et contextualisant. Pour illustrer le propos, je prendrai appui sur le format d’une recherche ayant documenté le savoir-faire d’un groupe d’enseignantes du primaire en matière d’évaluation formative, et ayant adopté une perspective interactionniste comme posture générale de recherche.An Interactionist PerspectiveAn Alternative Approach to Learning AssessmentThis article aims to show the usefulness of drawing from sociology to conduct research in the field of education. Specifically, it discusses the contribution of an interactionist perspective in understanding the objects attached to student learning assessment. As we shall see, drawing especially from authors working in the tradition of Symbolic Interactionism leads us outside the usual ways of thinking and doing in investigations related to assessment objects, from problematization to analysis, in favour of a (resocializing and contextualizing perspective. To illustrate this point, I will examine the format of a study documenting the expertise of a group of elementary school teachers with regard to formative assessment, and having an interactionist perspective as its basis of research.Una perspectiva interaccionista: otro punto de vista sobre la evaluación del aprendizajeEste artículo tiene como objetivo el demostrar el interés de

  11. Développement et analyse rhéologique d'une surface polymère nanocomposite anti-friction

    OpenAIRE

    Al-Kawaz , Ammar

    2015-01-01

    The goal of this thesis is the identification of couplings (nanoparticles / matrix poly (methyl methacrylate) PMMA) which ensure PMMA surface rigidity while maintaining maximum transparency. The choice fell on three types of carbonaceous nanoparticles: Few layer graphene (FLG), graphene oxide (GO) and carbon nanotubes (MWCNT). A first part describes the preparation and functionalization of these three types of nanoparticles to provide a better dispersion in the matrix. Two methods were used t...

  12. Assessment of Radioactive Materials and Heavy Metals in the Surface Soil around the Bayanwula Prospective Uranium Mining Area in China.

    Science.gov (United States)

    Bai, Haribala; Hu, Bitao; Wang, Chengguo; Bao, Shanhu; Sai, Gerilemandahu; Xu, Xiao; Zhang, Shuai; Li, Yuhong

    2017-03-14

    The present work is the first systematic and large scale study on radioactive materials and heavy metals in surface soil around the Bayanwula prospective uranium mining area in China. In this work, both natural and anthropogenic radionuclides and heavy metals in 48 surface soil samples were analyzed using High Purity Germanium (HPGe) γ spectrometry and inductively coupled plasma-mass spectrometry (ICP-MS). The obtained mean activity concentrations of 238 U, 226 Ra, 232 Th, 40 K, and 137 Cs were 25.81 ± 9.58, 24.85 ± 2.77, 29.40 ± 3.14, 923.0 ± 47.2, and 5.64 ± 4.56 Bq/kg, respectively. The estimated average absorbed dose rate and annual effective dose rate were 76.7 ± 3.1 nGy/h and 83.1 ± 3.8 μ Sv, respectively. The radium equivalent activity, external hazard index, and internal hazard index were also calculated, and their mean values were within the acceptable limits. The estimated lifetime cancer risk was 3.2 × 10 -4 /Sv. The heavy metal contents of Cr, Ni, Cu, Zn, As, Cd, and Pb from the surface soil samples were measured and their health risks were then assessed. The concentrations of all heavy metals were much lower than the average backgrounds in China except for lead which was about three times higher than that of China's mean. The non-cancer and cancer risks from the heavy metals were estimated, which are all within the acceptable ranges. In addition, the correlations between the radionuclides and the heavy metals in surface soil samples were determined by the Pearson linear coefficient. Strong positive correlations between radionuclides and the heavy metals at the 0.01 significance level were found. In conclusion, the contents of radionuclides and heavy metals in surface soil around the Bayanwula prospective uranium mining area are at a normal level.

  13. Radioactivity measurement

    International Nuclear Information System (INIS)

    Bohme, R.F.; Lazerson, M.M.

    1984-01-01

    A problem with ore sorting arrangements is that radiation is difficult to measure accurately while particles are moving at speed past the detector. This is particulary so when dealing with ores such as gold ores which have weak emissions. A method of measuring radioactive emissions from moving radioactive material includes the steps of shielding the radiation detector(s) so that the angle of acceptance of the receptor surface is restricted, and further shielding the shielded portion of the detector with a second material which is less radiation emissive than the material of the first shield. This second shield is between the first shield and the detector

  14. Method of storing radioactive wastes

    International Nuclear Information System (INIS)

    Adachi, Toshio; Hiratake, Susumu.

    1980-01-01

    Purpose: To reduce the radiation doses externally irradiated from treated radioactive waste and also reduce the separation of radioactive nuclide due to external environmental factors such as air, water or the like. Method: Radioactive waste adhered with radioactive nuclide to solid material is molten to mix and submerge the radioactive nuclide adhered to the surface of the solid material into molten material. Then, the radioactive nuclide thus mixed is solidified to store the waste in solidified state. (Aizawa, K.)

  15. Identification of candidate sites for a near surface repository for radioactive waste

    International Nuclear Information System (INIS)

    Motiejunas, S.

    2004-01-01

    This Report comprises results of the area survey stage, which involves regional screening to define the regions of interest and identification of potential sites within suitable regions. The main goal was to define a few sites potentially suitable for constructing of the near surface repository. It was concluded that a vicinity of Ignalina NPP is among the best suitable regions for the near surface repository. At the present investigation level a ridge in Galilauke village has the most favorable conditions. However, Apvardai site is potentially suitable for the repository too

  16. The development of the American national standard, ''control of radioactive surface contamination on materials, equipment and facilities to be released for uncontrolled use''

    International Nuclear Information System (INIS)

    Shapiro, J.

    1980-01-01

    The American National Standard, Control of Radioactive Surface Contamination on Materials, Equipment and Facilities to be Released for Uncontrolled Use, was developed under the procedures of ANSI for ANSI Main Committee N13 (Radiation Protection) by a working group of the Health Physics Society Standards Committee. This standard provides criteria for the control of materials, equipment and facilities contaminated with radioactivity proposed to be released for uncontrolled use. Permissible contamination limits are specified as well as methods assessing the levels of contamination. This paper reviews the proceedings of the Subcommittee on Radioactive Surface Contamination, the comments received by reviewers of the standard, the resolution of the committee, and the bases for reaching the final limits, recommendations, and measurement procedures. (H.K.)

  17. Radioactive waste safety appraisal. An international peer review of the licence application for the Australian near surface radioactive waste disposal facility. Report of the IAEA International Review Team

    International Nuclear Information System (INIS)

    2004-05-01

    Radioactive waste has been generated in Australia for a number of decades from the production and use of radioactive materials in medicine and industry, from the processing of various minerals containing natural radionuclides and from various research activities. It has been decided in the overall interest of safety and security to develop a radioactive waste disposal facility to accommodate the low level and short lived intermediate level waste, which make up the bulk of the waste, other than mining and minerals processing residues. A site selection process has been undertaken and environmental impact statement report prepared and approved. A licence application has been submitted to the national nuclear regulatory authority, the Australian Radiation Protection and Nuclear Safety Agency (ARPANSA) for siting, construction and operation of the facility. In order to assist the CEO of ARPANSA with his deliberations in this regard a request was made to the IAEA, in terms of its statutory mandate to establish international safety standards for radioactive waste safety and to provide for their application, to undertake an international peer review of the licence application and to advise the CEO accordingly. The outcome and recommendations of this peer review are presented in the report

  18. UNE APPROCHE REGULATIONNISTE DE LA ...

    African Journals Online (AJOL)

    Administrateur

    en ressources naturelles ont enregistré des performances économiques, moins bonnes par .... de gestion», à financer des augmentations de salaires; augmentations qui, très ... entreprises), dans la mesure où, d'une façon générale, elle introduit une plus .... Outre le contrôle strict de la création monétaire, un autre élément.

  19. Safety cases for the co-ordinated research project on improvement of safety assessment methodologies for near surface radioactive waste disposal facilities (ISAM)

    International Nuclear Information System (INIS)

    Kozak, M.W.; Torres-Vidal, C.; Kelly, E.; Guskov, A.; Blerk, J. van

    2002-01-01

    A Co-ordinated Research Project (CRP) has recently been completed on the Improvement of Safety Assessment Methodologies for Near-Surface Radioactive Waste Disposal Facilities (ISAM). A major aspect of the project was the use of safety cases for the practical application of safety assessment. An overview of the ISAM safety cases is given in this paper. (author)

  20. The "AQUASCOPE" simplified model for predicting 89, 90Sr, 131l and 134, 137Cs in surface waters after a large-scale radioactive fallout

    NARCIS (Netherlands)

    Smith, J.T.; Belova, N.V.; Bulgakov, A.A.; Comans, R.N.J.; Konoplev, A.V.; Kudelsky, A.V.; Madruga, M.J.; Voitsekhovitch, O.V.; Zibolt, G.

    2005-01-01

    Simplified dynamic models have been developed for predicting the concentrations of radiocesium, radiostrontium, and 131I in surface waters and freshwater fish following a large-scale radioactive fallout. The models are intended to give averaged estimates for radionuclides in water bodies and in fish

  1. Site characterization field manual for near surface geologic disposal of low-level radioactive waste

    International Nuclear Information System (INIS)

    McCray, J.G.; Nowatzki, E.A.

    1985-01-01

    This field manual has been developed to aid states and regions to do a detailed characterization of a proposed near-surface low-level waste disposal site. The field manual is directed at planners, staff personnel and experts in one discipline to acquaint them with the requirements of other disciplines involved in site characterization. While it can provide a good review, it is not designed to tell experts how to do their job within their own discipline

  2. Natural radionuclides tracing in marine surface waters along the northern coast of Oman Sea by combining the radioactivity analysis, oceanic currents and the SWAN model results

    International Nuclear Information System (INIS)

    Zare, Mohammad Reza; Mostajaboddavati, Mojtaba; Kamali, Mahdi; Tari, Marziyeh; Mosayebi, Sanaz; Mortazavi, Mohammad Seddigh

    2015-01-01

    Highlights: • This study estimates radioactive pollution diffusion in coastline of the Oman Sea. • 36 high volume surface water samples were analyzed using a portable HPGe detector. • Oceanic currents in the northern coast of Oman Sea were investigated. • The spectral wave model SWAN was used for wave parameters simulation. • Currents and preferable wave directions were coupled with higher radioactivity. - Abstract: This study aims to establish a managed sampling plan for rapid estimate of natural radio-nuclides diffusion in the northern coast of the Oman Sea. First, the natural radioactivity analysis in 36 high volume surface water samples was carried out using a portable high-resolution gamma-ray spectrometry. Second, the oceanic currents in the northern coast were investigated. Then, the third generation spectral SWAN model was utilized to simulate wave parameters. Direction of natural radioactivity propagation was coupled with the preferable wave vectors and oceanic currents direction that face to any marine pollution, these last two factors will contribute to increase or decrease of pollution in each grid. The results were indicated that the natural radioactivity concentration between the grids 8600 and 8604 is gathered in the grid 8600 and between the grids 8605 and 8608 is propagated toward middle part of Oman Sea

  3. Monitoring of surface deformation and microseismicity applied to radioactive waste disposal through hydraulic fracturing at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Stow, S.H.; Haase, C.S.; Switek, J.; Holzhausen, G.R.; Majer, E.

    1985-01-01

    Low-level liquid nuclear wastes are disposed of at Oak Ridge National Laboratory by the hydrofracture process. Wastes are mixed with cement and other additives to form a slurry that is injected into shale of low permeability at 300 m depth. The slurry spreads radially along bedding plane fractures before setting as a grout. Different methods for monitoring the location and behavior of the fractures have been investigated. Radioactive grout sheets can be located by gamma-ray logging of cased observation wells. Two other methods are based on the fact that the ground surface is deformed by the injection. The first entails surface leveling of a series of benchmarks; uplift up to 2.5 cm occurs. The second method involves use of tiltmeters that are sensitive and measure ground deformation in real time during an injection. Both methods show subsidence during the weeks following an injection. Interpretive models for the tiltmeter data are based on the elastic response of isotropic and anisotropic media to the inflation of a fluid-filled fracture. A fourth monitoring method is based on microseismicity. Geophone arrays were used to characterize the fracture process and to provide initial assessment of the feasibility of using seismic measurements to map the fractures as they form. An evaluation of each method is presented. 8 refs., 6 figs

  4. Monitoring of surface deformation and microseismicity applied to radioactive waste disposal through hydraulic fracturing at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Stow, S.H.; Haase, C.S.; Switek, J.; Holzhausen, G.R.; Majer, E.; Applied Geomechanics, Inc., Santa Cruz, CA; Lawrence Berkeley Lab., CA)

    1985-01-01

    Low-level liquid nuclear wastes are disposed of at Oak Ridge National Laboratory by the hydrofracture process. Wastes are mixed with cement and other additives to form a slurry that is injected into shale of low permeability at 300 m depth. The slurry spreads radially along bedding plane fractures before setting as a grout. Different methods for monitoring the location and behavior of the fractures have been investigated. Radioactive grout sheets can be located by gamma-ray logging of cased observation wells. Two other methods are based on the fact that the ground surface is deformed by the injection. The first entails surface leveling of a series of benchmarks; uplift up to 2.5 cm occurs. The second method involves use of tiltmeters that are sensitive and measure ground deformation in real time during an injection. Both methods show subsidence during the weeks following an injection. Interpretive models for the tiltmeter data are based on the elastic response of isotropic and anisotropic media to the inflation of a fluid-filled fracture. A fourth monitoring method is based on microseismicity. Geophone arrays were used to characterize the fracture process and to provide initial assessment of the feasibility of using seismic measurements to map the fractures as they form. An evaluation of each method is presented

  5. Safety during sea transport of radioactive materials. Probabilistic safety analysis of package fro sea surface fire accident

    International Nuclear Information System (INIS)

    Matsuoka, Takeshi; Obara, Isonori; Akutsu, Yukio; Aritomi, Masanori

    2000-01-01

    The ships carrying irradiated nuclear fuel, plutonium and high level radioactive wastes(INF materials) are designed to keep integrity of packaging based on the various safety and fireproof measures, even if the ship encounters a maritime fire accident. However, granted that the frequency is very low, realistic severe accidents should be evaluated. In this paper, probabilistic safety assessment method is applied to evaluate safety margin for severe sea fire accidents using event tree analysis. Based on our separate studies, the severest scenario was estimated as follows; an INF transport ship collides with oil tanker and induces a sea surface fire. Probability data such as ship's collision, oil leakage, ignition, escape from fire region, operations of cask cooling system and water flooding systems were also introduced from above mentioned studies. The results indicate that the probability of which packages cannot keep their integrity during the sea surface fire accident is very low and sea transport of INF materials is carried out very safely. (author)

  6. Validation and application of help code used for design and review of cover of low and intermediate level radioactive waste disposal in near-surface facilities

    International Nuclear Information System (INIS)

    Fan Zhiwen; Gu Cunli; Zhang Jinsheng; Liu Xiuzhen

    1996-01-01

    The authors describes validation and application of HELP code used by the United States Environmental Protective Agency for design and review of cover of low and intermediate level radioactive waste disposal in near-surface facilities. The HELP code was validated using data of field aerated moisture movement test by China Institute for Radiation Protection. The results show that simulation of HELP code is reasonable. Effects of surface layer thickness and surface treatment on moisture distribution in a cover was simulated with HELP code in the conditions of south-west China. The simulation results demonstrated that surface plantation of a cover plays very important role in moisture distribution in the cover. Special attention should be paid in cover design. In humid area, radioactive waste disposal safety should take full consideration with functions of chemical barrier. It was recommended that engineering economy should be added in future cover research so as to achieve optimization of cover design

  7. Radioactivity determination of sealed pure beta-sources by surface dose measurements and Monte Carlo simulations

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Chang Heon [Interdisciplinary Program in Radiation Applied Life Science, Seoul National University College of Medicine, Seoul (Korea, Republic of); Jung, Seongmoon [Program in Biomedical Radiation Sciences, Department of Transdisciplinary Studies, Graduate School of Convergence Science and Technology, Seoul National University, Seoul (Korea, Republic of); Choi, Kanghyuk; Son, Kwang-Jae; Lee, Jun Sig [Hanaro Applications Research, Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Ye, Sung-Joon, E-mail: sye@snu.ac.kr [Interdisciplinary Program in Radiation Applied Life Science, Seoul National University College of Medicine, Seoul (Korea, Republic of); Program in Biomedical Radiation Sciences, Department of Transdisciplinary Studies, Graduate School of Convergence Science and Technology, Seoul National University, Seoul (Korea, Republic of); Center for Convergence Research on Robotics, Advance Institutes of Convergence Technology, Seoul National University, Suwon (Korea, Republic of)

    2016-04-21

    This study aims to determine the activity of a sealed pure beta-source by measuring the surface dose rate using an extrapolation chamber. A conversion factor (cGy s{sup −1} Bq{sup −1}), which was defined as the ratio of surface dose rate to activity, can be calculated by Monte Carlo simulations of the extrapolation chamber measurement. To validate this hypothesis the certified activities of two standard pure beta-sources of Sr/Y-90 and Si/P-32 were compared with those determined by this method. In addition, a sealed test source of Sr/Y-90 was manufactured by the HANARO reactor group of KAERI (Korea Atomic Energy Research Institute) and used to further validate this method. The measured surface dose rates of the Sr/Y-90 and Si/P-32 standard sources were 4.615×10{sup −5} cGy s{sup −1} and 2.259×10{sup −5} cGy s{sup −1}, respectively. The calculated conversion factors of the two sources were 1.213×10{sup −8} cGy s{sup −1} Bq{sup −1} and 1.071×10{sup −8} cGy s{sup −1} Bq{sup −1}, respectively. Therefore, the activity of the standard Sr/Y-90 source was determined to be 3.995 kBq, which was 2.0% less than the certified value (4.077 kBq). For Si/P-32 the determined activity was 2.102 kBq, which was 6.6% larger than the certified activity (1.971 kBq). The activity of the Sr/Y-90 test source was determined to be 4.166 kBq, while the apparent activity reported by KAERI was 5.803 kBq. This large difference might be due to evaporation and diffusion of the source liquid during preparation and uncertainty in the amount of weighed aliquot of source liquid. The overall uncertainty involved in this method was determined to be 7.3%. We demonstrated that the activity of a sealed pure beta-source could be conveniently determined by complementary combination of measuring the surface dose rate and Monte Carlo simulations.

  8. The efficacy of surface active substances to decontaminate radioactive pollution of animals

    International Nuclear Information System (INIS)

    Kossakowski, S.

    1975-01-01

    The purpose of the work was to determine the efficacy of native surface-active substances in the decontamination of pig pollution with 90 Sr, 131 J, 144 Ce and 137 Cs. The appraisal was performed on the basis of indices of final activity. It was found that an Ixi solution was the most efficient against 137 Cs, E powder and Kokosal against 144 Ce and 90 Sr respectively, and also E powder against 137 J. The most universal proved to be enzymatic powders E and R, and then the detergens Ixi, Bis, FF and Kokosal. (author)

  9. Le soja local en Allemagne, une demande soutenue, une offre qui s’étoffe

    Directory of Open Access Journals (Sweden)

    Recknagel Jürgen

    2015-09-01

    Full Text Available Depuis 2009, la sole de soja ne cesse d’augmenter en Allemagne, surtout dans le sud du pays mais aussi à l’est et un peu partout dans les régions au climat propice. Un programme national a permis de créer les références nécessaires pour un conseil qualifié apporté aux agriculteurs via un réseau de développement. Ainsi toute une filière soja est déjà bien avancée dans le sud et en cours de mise en place dans le reste du pays, pour organiser la collecte auprès des producteurs et obtenir une offre groupée pour les transformateurs pour l’alimentation animale et humaine. Le soja allemand ne veut pas rivaliser avec le soja OGM ni pour instant avec le soja non-OGM des Amériques mais vise plutôt les filières courtes régionales et le marché bio qui est encore plus déficitaire en auto-approvisionnement que le conventionnel. Avec 10 000 ha en 2014, dont 25 % en bio, le soja en Allemagne est encore loin de la surface du maïs grain (2008–2014 autour de 500 000 ha. En pratique, 20 % de ces surfaces de maïs au climat a priori propice pourraient représenter le potentiel réel pour le soja en Allemagne, sous condition de prix garantissant une rentabilité suffisante par rapport aux autres grandes cultures. Pour les programmes non-OGM des grands distributeurs, il faut de toute façon une base de production élargie comme celle proposée par l’initiative Danube-Soja, qui dans une version Europe-Soja engloberait aussi la France. Avec le verdissement de la PAC et la montée du cours du Dollar par rapport à l’Euro, les perspectives pour une augmentation de la surface de production de soja en Allemagne et en Europe paraissent bonnes. Maintenant il faut travailler sur les débouchés pour garantir l’absorption de la production grandissante par les marchés et les consommateurs à tous les niveaux : régional, national et européen.

  10. Model feasibility study of radioactive pathways from atmosphere to surface water

    International Nuclear Information System (INIS)

    Smith, R.E.; Summer, R.M.; Ferreira, V.A.

    1990-03-01

    A feasibility study of the atmosphere to surface-water radionuclide pathways was performed for small catchments, using a physically-based hydro-ecosystem model, Opus. Detailed time-intensity precipitation records from Arizona and Georgia were used as input to drive the model. Tests of model sensitivity to distribution coefficients, Kd, for Cs-137, Cs-134, and Sr-90 illustrated different vegetation-soil-erosion-runoff pathways, in response to agricultural management practices. Results reflected the fact that low Kd values allow a radionuclide to infiltrate into the soil profile and isolate it from subsequent runoff and erosion. Of the radionuclides and physical settings studied, only the Sr-90, with low Kd values, is sufficiently mobile and long-lived to be removed from the system via percolation below the root zone. Conversely, highly-adsorbed radionuclides were subject to removal by adsorption to sediment particles and subsequent runoff. Comparison of different effective half-lives of I-131 demonstrated the importance of the timing of an erosion-runoff storm event during or immediately after a fallout event. Seasonal timing of a fallout event and crop management also affect the fate of this short-lived radionuclide. Removal by solution to surface-water runoff was negligible for all nuclides studied. 34 refs., 14 figs., 2 tabs

  11. Control of water infiltration into near surface LLW [low-level radioactive waste] disposal units

    International Nuclear Information System (INIS)

    Schulz, R.K.; Ridky, R.W.; O'Donnell, E.O.

    1990-12-01

    Three kinds of waste disposal unit covers a barriers to water infiltration are being investigated. They are: (1) resistive layer barrier, (2) conductive layer barrier, and (3) bioengineering management. The resistive layer barrier consists of compacted earthen material (e.g. clay). The conductive layer barrier consists of a conductive layer in conjunction with a capillary break. As long as unsaturated flow conditions are maintained the conductive layer will wick water around the capillary break. Below grade layered covers such as (1) and (2) will fail if there is appreciable subsidence of the cover. Remedial action for this kind of failure will be difficult. A surface cover, called bioengineering management, is meant to overcome this problem. The bioengineering management surface barrier is easily repairable if damaged by subsidence; therefore, it could be the system of choice under active subsidence conditions. The bioengineering management procedure also has been shown to be effective in dewatering saturated trenches and could be used for remedial action efforts. After cessation of subsidence, that procedure could be replaced by a resistive layer barrier, or perhaps even better, a resistive layer barrier/conductive layer barrier system. This latter system would then give long-term effective protection against water entry to waste and without institutional care. These various concepts are being assessed in six large (70ft x 45ft x 10ft each) lysimeters at Beltsville, Maryland. 6 refs., 20 figs.,

  12. Radioactivity of surface water and freshwater fish in Finland in 1988-1990

    International Nuclear Information System (INIS)

    Saxen, R.; Koskelainen, U.

    1992-02-01

    Changes over time in the activity concentrations of radionuclides in surface water and in the five largest rivers and some smaller rivers discharging into the Baltic Sea were monitored in 1988-1990. The dominant gamma-emitting radionuclides were 137 Cs and 134 Cs. The effect of the uneven distribution of Chernobyl deposition is still seen in the results. The activity concentrations of 137 Cs in surface water have decreased significantly: In the drainage area where the activity concentrations were highest after the Chernobyl accident, the concentrations in October 1990 were only about 1-4% of the maximum values in May 1986. The decrease in the activity concentrations of 90 Sr was much slighter. The study of areal and temporal changes in the activity concentrations of 137 Cs in fish, started in 1986, continued in 1988-1990. In all, about 2400 fish samples from southern and middle Finland (excluding Lappland) were analyzed gammaspectrometrially during these three years. Seventeen different fish species were included in the study. (20 refs., 14 figs., 30 tabs.)

  13. Inventory of radioactive corrosion products on the primary surfaces and release during shutdown in Ringhals 2

    International Nuclear Information System (INIS)

    Aronsson, O.

    1994-01-01

    In Ringhals 2 a retrospective study using gamma scans of system surfaces, fuel crud sampling and reactor coolant analyses during operation and shutdown has been done. The data have been used to prepare a balance of activity inventory. The inventory has been fairly stable from 1986 to 1993, expressed as a gamma source term. The steam generator replacement in 1989 removed some 40-50% of the Co-60 inventory in the reactor system. After the steam generator replacement, the gamma source term has got an increasing contribution from Co-58, absolutely as well as relatively. The reason for this is probably the switch from high pH operation to modified pH operation. Corrosion from fresh alloy 690 surfaces in the new steam generators is probably another contributing factor. The inventory and production rate of Co-60 is decreasing over the years. It has also been found that clean-up of the reactor coolant during start-up, operation, and shutdown as well as the fuel pool during refuelling removes about the same amounts of Co-60. (author). 11 figs., 15 refs

  14. A Solution for the Storage of Radioactive Sludge in the Ground at Marcoule; Une Solution de Stockage dans le Sol des Boues Radioactives de Marcoule; 0420 0415 0428 0414 ; Solucion para el Almacenamiento de Lodos Radiactivos en el Suelo de Marcoule

    Energy Technology Data Exchange (ETDEWEB)

    Cohen, P.; Gailledreau, C. [Service de Controle des Radiations et de Genie Radioactif, Commissariat a L' Energie Atomique, Saclay (France)

    1960-07-01

    This paper deals with radioactive sludge from the radioactive effluents of the plant at Marcoule. The sludge is stored in drums, and the authors have investigated the hazard created at Marcoule by the seepage of this radioactive sludge through the soil with the gradual deterioration of the drums. This economic solution may be applicable in certain cases. (author) [French] Il s'agit de boues radioactives en provenance de la station des effluents radioactifs de Marcoule: ces boues sont stockees dans des futs, et nous avons etudie le danger presente par la percolation a travers le sol de Marcoule de ces boues radioactives apres degradation progressive du fut. Cette solution economique peut etre applicable dans certains cas. (author) [Spanish] Se trata de los lodos radiactivos procedentes de la estacion de efluentes radiactivos de Marcoule: los lodos se depositan en toneles, y el autor ha estudiado el peligro que ofrece la infiltracion de los lodos radiactivos a traves del suelo de Marcoule a causa del deterioro progresivo del tonel. Esta solucion economica se puede aplicar en determinados casos. (author) [Russian] V dannom doklade rassmatrivajutsja radioaktivnye grjazi, ishodjashhie iz stancii radioaktivnyh zhidkih othodov v Markule. Jeti grjazi zahoronjajutsja v cisternah; v svjazi s jetim izuchalas' opasnost', vyzyvaemaja perkoljaciej cherez pochvu Markulja jetih radioaktivnyh grjazej posle postepennoj porchi cistern. Jeto jekonomicheskoe reshenie mozhet primenjat'sja v otdel'nyh sotuchajah. (author)

  15. Radionuclide transport from near-surface repository for radioactive waste - The unsaturated zone approach

    Energy Technology Data Exchange (ETDEWEB)

    Jakimaviciute-Maseliene, V. [Vilnius University (Lithuania); Mazeika, J. [Nature Research Centre (Lithuania); Motiejunas, S. [Radioactive Waste Management Agency (Lithuania)

    2014-07-01

    About 100 000 m{sup 3} of solid conditioned Low and Intermediate Level Waste (LILW), generated during operation and decommissioning of the Ignalina nuclear power plant (INPP), are to be disposed of in a near-surface repository (NSR) - a 'hill'-type repository with reinforced concrete vaults and with engineered and natural barriers. The northeastern Lithuania and the environment of the INPP in particular were recognized as the areas most suitable for a near-surface repository (Stabatiske Site). The engineered barriers of the repository consist of concrete cells surrounded by clay-based material of low permeability with about the same isolating capacity in all directions. The clay materials must be effectively compactable so that required hydraulic conductivity is reached. The Lithuanian Triassic clay turned out to be sufficiently rich in smectites and was proposed as main candidate for sealing of the repository. When the concrete vaults are filled, the repository cover will be constructed. The surface of the mound will be planted with grass. In this study a computer code FEFLOW 5.0 was applied for simulating the transport of the most mobile radionuclides ({sup 3}H, {sup 14}C, {sup 59}Ni and {sup 94}Nb) with moisture through an unsaturated vault of the near-surface repository in Stabatiske Site. The HYDRUS-1D analysis was used to assess the radionuclide transport in the repository and to estimate initial activity concentrations of radionuclides transported from the cemented waste matrix. Radionuclide release from the vault in the unsaturated conditions after closure of the repository and consequent contaminant plume transport has been assessed taking into account site-specific natural and engineering conditions and based on a normal evolution scenario. The highest peak radionuclide activity concentrations were estimated applying the FEFLOW code. The highest value of {sup 14}C activity concentration(about 1.3x10{sup 8} Bq/m{sup 3}) at the groundwater table

  16. Surface of allogra on bone-cow of Eprgdnyr by radioactive tracing

    International Nuclear Information System (INIS)

    Tong Jian; Zhang Hongwei; Li Huaifen; Niu Huisheng

    2008-01-01

    Growth bone tissue engineering is one of the creative medical fields in reconstruction of bone defect. It can provide the surface of the material with condition of rich osteoblast multiplication through bioactive materials such as Eprgdnyr (RGD peptide) and cell factor introduced in frame material. A quantity measure of the degree that the pieces of calf bone activated by the radiation of the ultra-violet couple RGD peptide onto the pieces of calf bone under the function of the EDC was given by tracer technique 125 I-Eprgdnyr. The result shows that the amount that RGD peptide couples onto the bone pieces has positive correlation to that of Eprgdnyr and EDC, aimed at providing scientific basis for facial modification of bone reconstruct and support material. (authors)

  17. Assessment of the dynamics of the radioactivity contents in surface waters in contaminated areas

    International Nuclear Information System (INIS)

    Komissarov, F.D.; Datskevich, P.I.; Golikov, Y.N.; Basharina, L.P.; Churack, T.N.; Khvaley, O.D.

    1997-01-01

    In the connection with Chernobyl APS accident, since 1988 a network of sites was established for radioecological monitoring of surface water systems, mainly, small rivers on all Belarus territory. Small rivers are the principal way of radionuclides run off in liquid and solid discharges during rains and high-floods and their re-distribution in landscapes. The components of water systems radio-monitoring were water and water suspensions, area water-collection, bottom deposits and biota. In the paper the data are cited of radioecological studies of water systems components. Their analysis is done and some conclusions made which may be used for the development of radioecological prognosis and for taking environmental measures

  18. Silicon surface barrier detector and study of energy spectrum of alpha particles from radioactive source

    International Nuclear Information System (INIS)

    Verma, S.D.; Sinha, Vijaya

    1986-01-01

    The principles of working of three commonly used radiation detectors, namely ionization chambers, scintillation counters with photomultiplier tube (PMT) systems and semiconductor detectors are briefly discussed. Out of the semiconductor detectors, the silicon surface barrier (SSB) detector has distinct advantages for detection of radiations, alpha particles in particular. The experimental setup to obtain the energy spectrum of alpha particles from 241 Am source using SSB fabricated in the Physics Department of Gujarat University, Ahmedabad is described. Its performance is compared with scintillation counter using PMT. SSB detector shows a sharp peak of #approx # 3 per cent energy resolution. The factors affecting the peak, namely, electronic noise, source dependent factors and detector-dependent factors are discussed. A method of calibrating SSB detectors based on energy loss mechanism of alpha particles in thin absorbers is described. Applications of such detectors are indicated. (M.G.B.)

  19. Assessment of Radioactive Materials and Heavy Metals in the Surface Soil around the Bayanwula Prospective Uranium Mining Area in China

    Directory of Open Access Journals (Sweden)

    Haribala Bai

    2017-03-01

    Full Text Available The present work is the first systematic and large scale study on radioactive materials and heavy metals in surface soil around the Bayanwula prospective uranium mining area in China. In this work, both natural and anthropogenic radionuclides and heavy metals in 48 surface soil samples were analyzed using High Purity Germanium (HPGe γ spectrometry and inductively coupled plasma-mass spectrometry (ICP-MS. The obtained mean activity concentrations of 238U, 226Ra, 232Th, 40K, and 137Cs were 25.81 ± 9.58, 24.85 ± 2.77, 29.40 ± 3.14, 923.0 ± 47.2, and 5.64 ± 4.56 Bq/kg, respectively. The estimated average absorbed dose rate and annual effective dose rate were 76.7 ± 3.1 nGy/h and 83.1 ± 3.8 μSv, respectively. The radium equivalent activity, external hazard index, and internal hazard index were also calculated, and their mean values were within the acceptable limits. The estimated lifetime cancer risk was 3.2 × 10−4/Sv. The heavy metal contents of Cr, Ni, Cu, Zn, As, Cd, and Pb from the surface soil samples were measured and their health risks were then assessed. The concentrations of all heavy metals were much lower than the average backgrounds in China except for lead which was about three times higher than that of China’s mean. The non-cancer and cancer risks from the heavy metals were estimated, which are all within the acceptable ranges. In addition, the correlations between the radionuclides and the heavy metals in surface soil samples were determined by the Pearson linear coefficient. Strong positive correlations between radionuclides and the heavy metals at the 0.01 significance level were found. In conclusion, the contents of radionuclides and heavy metals in surface soil around the Bayanwula prospective uranium mining area are at a normal level.

  20. ORNL results for Test Case 1 of the International Atomic Energy Agency's research program on the safety assessment of Near-Surface Radioactive Waste Disposal Facilities

    International Nuclear Information System (INIS)

    Thorne, D.J.; McDowell-Boyer, L.M.; Kocher, D.C.; Little, C.A.; Roemer, E.K.

    1993-01-01

    The International Atomic Energy Agency (IAEA) started the Coordinated Research Program entitled '''The Safety Assessment of Near-Surface Radioactive Waste Disposal Facilities.'' The program is aimed at improving the confidence in the modeling results for safety assessments of waste disposal facilities. The program has been given the acronym NSARS (Near-Surface Radioactive Waste Disposal Safety Assessment Reliability Study) for ease of reference. The purpose of this report is to present the ORNL modeling results for the first test case (i.e., Test Case 1) of the IAEA NSARS program. Test Case 1 is based on near-surface disposal of radionuclides that are subsequently leached to a saturated-sand aquifer. Exposure to radionuclides results from use of a well screened in the aquifer and from intrusion into the repository. Two repository concepts were defined in Test Case 1: a simple earth trench and an engineered vault

  1. Strippable core-shell polymer emulsion for decontamination of radioactive surface contamination

    International Nuclear Information System (INIS)

    Hwang, Ho-Sang; Seo, Bum-Kyoung; Lee, Kune-Woo

    2011-01-01

    In this study, the core-shell composite polymer for decontamination from the surface contamination was synthesized by the method of emulsion polymerization and blends of polymers. The strippable polymer emulsion is composed of the poly(styrene-ethyl acrylate) [poly(St-EA)] composite polymer, poly(vinyl alcohol) (PVA) and polyvinylpyrrolidone (PVP). The morphology of the poly(St-EA) composite emulsion particle was core-shell structure, with polystyrene (PS) as the core and poly(ethyl acrylate) (PEA) as the shell. Core-shell polymers of styrene (St)/ethyl acrylate (EA) pair were prepared by sequential emulsion polymerization in the presence of sodium dodecyl sulfate (SDS) as an emulsifier using ammonium persulfate (APS) as an initiator. Related tests and analysis confirmed the success in synthesis of composite polymer. The products are characterized by FT-IR spectroscopy, TGA that were used, respectively, to show the structure, the thermal stability of the prepared polymer. Two-phase particles with a core-shell structure were obtained in experiments where the estimated glass transition temperature and the morphologies of emulsion particles. Decontamination factors of the strippable polymeric emulsion were evaluated with the polymer blend contents. (author)

  2. Permeability and pore structure connectivity of basic concrete formulations to use in near-surface repositories for radioactive wastes

    International Nuclear Information System (INIS)

    Tolentino, Evandro; Santos, Carlos Eduardo de Oliveira; Tello, Clédola Cássia Oliveira de

    2017-01-01

    The main concern of engineers who prepare concrete specifications for a particular application is to predict the deteriorative exposures that could cause concrete degradation over its intended service life. A durable concrete is able to resist destructive environmental conditions, without requiring excessive maintenance. Durability of cementitious materials largely depends on the possibilities of penetration of hazardous ions into the porous material with water as medium. Therefore, the water permeability of cementitious materials is related to its durability. Permeability and porosity should not instinctively be regarded as manifestations of the same phenomenon. Usually, when permeability increases, porosity increases as well. The connectivity of pore network exerts an important control on preferential flow into cementitious materials. This work presents results of quantitative evaluation of permeability and pore connectivity of Portland cement concretes. Two concrete mixture proportions with limestone and gneiss as coarse aggregate were produced. A modified polycarboxyl ether plasticizer GLENIUM 51 was added to one of the concrete mixtures in order to reduce the water content. Permeability tests were performed on all the specimens and a geometric modeling considering pore with cylindrical shape was applied in order to evaluate the pore network connectivity. The results showed that pore structure connectivity of concrete with plasticizer admixture decreased. The purpose of this research is to expand the knowledge concerning concrete durability and to provide the technical requirements related to the production the Brazilian near-surface repository of radioactive wastes. (author)

  3. Permeability and pore structure connectivity of basic concrete formulations to use in near-surface repositories for radioactive wastes

    Energy Technology Data Exchange (ETDEWEB)

    Tolentino, Evandro; Santos, Carlos Eduardo de Oliveira [Centro Federal de Educação Tecnológica de Minas Gerais (CEFET-MG), Timóteo, MG (Brazil); Tello, Clédola Cássia Oliveira de, E-mail: tolentino@timoteo.cefetmg.br, E-mail: tellocc@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2017-07-01

    The main concern of engineers who prepare concrete specifications for a particular application is to predict the deteriorative exposures that could cause concrete degradation over its intended service life. A durable concrete is able to resist destructive environmental conditions, without requiring excessive maintenance. Durability of cementitious materials largely depends on the possibilities of penetration of hazardous ions into the porous material with water as medium. Therefore, the water permeability of cementitious materials is related to its durability. Permeability and porosity should not instinctively be regarded as manifestations of the same phenomenon. Usually, when permeability increases, porosity increases as well. The connectivity of pore network exerts an important control on preferential flow into cementitious materials. This work presents results of quantitative evaluation of permeability and pore connectivity of Portland cement concretes. Two concrete mixture proportions with limestone and gneiss as coarse aggregate were produced. A modified polycarboxyl ether plasticizer GLENIUM 51 was added to one of the concrete mixtures in order to reduce the water content. Permeability tests were performed on all the specimens and a geometric modeling considering pore with cylindrical shape was applied in order to evaluate the pore network connectivity. The results showed that pore structure connectivity of concrete with plasticizer admixture decreased. The purpose of this research is to expand the knowledge concerning concrete durability and to provide the technical requirements related to the production the Brazilian near-surface repository of radioactive wastes. (author)

  4. Assessment of radioactive materials and heavy metals in the surface soil around uranium mining area of Tongliao, China.

    Science.gov (United States)

    Haribala; Hu, Bitao; Wang, Chengguo; Gerilemandahu; Xu, Xiao; Zhang, Shuai; Bao, Shanhu; Li, Yuhong

    2016-08-01

    Natural and artificial radionuclides and heavy metals in the surface soil of the uranium mining area of Tongliao, China, were measured using gamma spectrometry, flame atomic absorption spectrophotometry, graphite furnace atomic absorption spectrophotometry and microwave dissolution atomic fluorescence spectrometry respectively. The estimated average activity concentrations of (238)U, (232)Th, (226)Ra, (40)K and (137)Cs are 27.53±16.01, 15.89±5.20, 12.64±4.27, 746.84±38.24 and 4.23±4.76Bq/kg respectively. The estimated average absorbed dose rate in the air and annual effective dose rate are 46.58±5.26nGy/h and 57.13±6.45μSv, respectively. The radium equivalent activity, external and internal hazard indices were also calculated and their mean values are within the acceptable limits. The heavy metal concentrations of Pb, Cd, Cu, Zn, Hg and As from the surface soil were measured and their health risks were then determined. Although the content of Cd is much higher than the average background in China, its non-cancer and cancer risk indices are all within the acceptable ranges. These calculated hazard indices to estimate the potential radiological health risk in soil and the dose rate are well below their permissible limit. In addition the correlations between the radioactivity concentrations of the radionuclides and the heavy metals in soil were determined by the Pearson linear coefficient. Copyright © 2016 Elsevier Inc. All rights reserved.

  5. The Possibility of Making a Quantitative Study of the Precipitin Reaction by Gamma-Radioactive Tracers; Possibilite d'une Etude Quantitative de la Reaction de Precipitation par Marquage a l'Aide d'Emetteurs Gamma; Vozmozhnost' kolichestvennogo opredeleniya reaktsii osazhdeniya s pomoshch'yu gamma-radioaktivnykh indikatorov; Estudio Cuantitativo de la Reaccion de Precipitacion con Ayuda de Indicadores Gamma

    Energy Technology Data Exchange (ETDEWEB)

    Bonev, L.; Todorov, S.; Robev, S. [Nauchno-Issledovatel' skij Institut Radiologii i Radiacionnoj Bezopasnosti, Sofija (Bulgaria)

    1965-10-15

    The paper presents the first results of the quantitative determination of the precipitin reaction (formation of an antigen-antibody complex) by labelling the precipitating components with gamma-radioactive tracers which do not chemically interact with albuminous molecules. As tracers it is possible to use chrome-manganese and nickel-copper compounds, whose tendency to hydrolyze permits the fixation of the radioactive tracer on the antigen and antibody respectively. The radioactivity of the components is determined by a multichannel pulse-height analyser. The results obtained show that the precipitation curve, plotted on the basis of radiometric data, closely corresponds to the curve plotted by the well-known quantitative methods used to determine albumin. The paper discusses the possibilities of using the method described. (author) [French] Les auteurs communiquent les premiers resultats d'une etude quantitative qu'ils ont faite de la reaction de precipitation (formation du complexe antigene-anticorps) en marquant les composants du precipites avec des emetteurs gamma qui ne reagissent pas chimiquement avec les molecules d'albumine. Pour le marquage, on peut utiliser des composes de chrome/manganese ou de fer qui subissent facilement l'hydrolyse et assurent de ce fait la fixation de la substance radioactive sur l'antigene et, partant, sur l'anticorps. La radioactivite des composants est determinee a l'aide d'un selecteur d'amplitudes a plusieurs canaux. Les resultats montrent que la courbe de precipitation obtenue avec les donnees radiometriques concorde parfaitement avec celle que l'on obtient par les methodes quantitatives connues servant au dosage de l'albumine. Les auteurs discutent les possibilites d'application de la methode etudiee. (author) [Spanish] Los autores presentan los primeros resultados de un estudio cuantitativo de la reaccion de precipitacion (formacion del complejo antigeno-anticuerpo) que efectuaron marcando los componentes de precipitacion con

  6. 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.)

  7. 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.)

  8. Derivation of quantitative acceptance criteria for disposal of radioactive waste to near surface facilities: Development and implementation of an approach for the post-closure phase

    International Nuclear Information System (INIS)

    Torres, C.

    2000-01-01

    The International Atomic Energy Agency has established a project to develop and illustrate, through practical examples, an approach that allows the derivation of quantitative waste acceptance criteria for near surface disposal of radioactive waste. The first phase focussed on the derivation of example post-closure safety waste acceptance criteria through the use of a safety assessment approach that allows for the derivation of values in a clear and well documented manner. The approach consists of five steps: the specification of the assessment context; the description of the disposal system; the development and justification of scenarios; the formulation and implementation of models; and the calculation and derivation of example values. The approach has been successfully used to derive activity values for the disposal of radioactive waste to illustrative near surface facilities. (author)

  9. Optimizing detection of noble gas emission at a former UNE site: sample strategy, collection, and analysis

    Science.gov (United States)

    Kirkham, R.; Olsen, K.; Hayes, J. C.; Emer, D. F.

    2013-12-01

    Underground nuclear tests may be first detected by seismic or air samplers operated by the CTBTO (Comprehensive Nuclear-Test-Ban Treaty Organization). After initial detection of a suspicious event, member nations may call for an On-Site Inspection (OSI) that in part, will sample for localized releases of radioactive noble gases and particles. Although much of the commercially available equipment and methods used for surface and subsurface environmental sampling of gases can be used for an OSI scenario, on-site sampling conditions, required sampling volumes and establishment of background concentrations of noble gases require development of specialized methodologies. To facilitate development of sampling equipment and methodologies that address OSI sampling volume and detection objectives, and to collect information required for model development, a field test site was created at a former underground nuclear explosion site located in welded volcanic tuff. A mixture of SF-6, Xe127 and Ar37 was metered into 4400 m3 of air as it was injected into the top region of the UNE cavity. These tracers were expected to move towards the surface primarily in response to barometric pumping or through delayed cavity pressurization (accelerated transport to minimize source decay time). Sampling approaches compared during the field exercise included sampling at the soil surface, inside surface fractures, and at soil vapor extraction points at depths down to 2 m. Effectiveness of various sampling approaches and the results of tracer gas measurements will be presented.

  10. Une proposition de nouveau cartogramme

    Directory of Open Access Journals (Sweden)

    Raymond Badel

    1990-05-01

    Full Text Available Le cartogramme proposé est une technique de recherche-exploration rapide grâce aux possibilités offertes par le micro-ordinateur et sa diffusion. La propriété foncière en vallée d'Aure lui sert de support.

  11. Review to give the public clear information on near surface disposal project of low-level radioactive wastes generated from research, industrial and medical facilities

    International Nuclear Information System (INIS)

    Shobu, Nobuhiro; Amazawa, Hiroya; Koibuchi, Hiroto; Nakata, Hisakazu; Kato, Masatoshi; Takao, Tomoe; Terashima, Daisuke; Tanaka, Yoshie; Shirasu, Hisanori

    2013-12-01

    Japan Atomic Energy Agency (hereafter abbreviated as “JAEA”) has promoted near surface disposal project for low-level radioactive wastes generated from research, industrial and medical facilities after receiving project approval from the government in November 2009. JAEA has carried out public information about low-level radioactive wastes disposal project on the web site. When some town meetings are held toward mutual understanding with the public, more detailed and clear explanations for safety management of near surface disposal are needed especially. Therefore, the information provision method to make the public understand should be reviewed. Moreover, a web-based survey should be carried out in order to get a sense of what the public knows, what it values and where it stands on nuclear energy and radiation issues, because the social environment surrounding nuclear energy and radiation issues has drastically changed as a result of the accident at the Fukushima Daiichi Nuclear Power Station on March 11, 2011. This review clarified the points to keep in mind about public information on near surface disposal project for low-level radioactive wastes generated from research, industrial and medical facilities, and that public awareness and understanding toward nuclear energy and radiation was changed before and after the accident at Fukushima Daiichi Nuclear Power Plant. (author)

  12. Drainage of radioactive areas

    International Nuclear Information System (INIS)

    1981-04-01

    This Code of Practice covers all the drainage systems which may occur in the radioactive classified area of an establishment, namely surface water, foul, process and radioactive drainage. It also deals with final discharge lines. The Code of Practice concentrates on those aspects of drainage which require particular attention because the systems are in or from radioactive areas and typical illustrations are given in appendices. The Code makes references to sources of information on conventional aspects of drainage design. (author)

  13. First Results of a Systematic Study of Internal Contamination Due to Fall-Out; Premiers Resultats d'une Etude Systematique des Contaminations Internes Consecutives aux Retombees Radioactives; 041f 0415 0420 0414 ; Resultados Iniciales de un Estudio Sistematico de las Contaminaciones Internas Debidas a la Precipitacion Radiactiva

    Energy Technology Data Exchange (ETDEWEB)

    Pellerin, P.; Moroni, J. P.; Remy, M. L. [Travail du Service Central de Protection Contre les Rayonnements Ionisants, Ministere de la Sante Publique, Paris (France)

    1964-11-15

    infer a maximum value for the isotope. (author) [French] Depuis septembre 1.961, plus de-500 examens a l'anthropoeamma- metre.ont ete pratiques par le Service central de protection contre les rayonnements ionisants. De nombreuses personnes sont soumises a des examens trimestriels ou semestriels et des radioanalyses urinaires sont frequemment associees a ces examens; une exploration systematique de l'echantillon d'urine par spectrometrie {gamma} precede en general l'etude radiochimique. L'etude comparative des resultats de ces divers examens permet de degager certains faits relatifs a la contamination interne due aux retombees radioactives: 1. Le cesium 137 est le seul radioisotope artificiel constamment retrouve par examen a l'anthropogamma- metre. L'evolution de la charge totale moyenne peut etre suivie durant toute la periode de temps couverte par l'ensemble des examens. On peut constater accessoirement la variation, par ailleurs classique, de la charge radioactive selon le sexe. 2. Les auteurs ont pu etudier, pour les faibles activites habituellement rencontrees, le rapport entre l'excretion urinaire du cesium-137 et la charge corporelle totale de ce radioisotope. Les resultats paraissent'confirmer les relations etablies par d'autres auteurs pour des contaminations plus importantes. 3. En ce qui concerne les produits de fission a vies moyennes, les zirconium 95 + niobium 95 en particulier (et plus accessoirement le ruthenium 103), leur presence a pu etre constatee de facon transitoire a certaines periodes. 4. La connaissance de la charge corporelle totale de strontium 90 serait une donnee capitale, mais la mesure directe de ce radioisotope a Tanthropogammametre ne peut etre realisee pour de faibles activites. Les auteurs ont donc tente d'evaluer l'ordre de grandeur de cette charge par deux voies differentes: tout d'abord, l'etude du cesium 137, dont le pourcentage dans les retombees radioactives evolue de facon sensiblement parallele a celui du strontium 90, permet

  14. Radioactivity concentrations in Bavarian surface water after the Chernobyl reactor accident. Radioaktive Belastungen des Wassers in Bayern nach dem Reaktorunfall in Tschernobyl

    Energy Technology Data Exchange (ETDEWEB)

    Amann, W; Friedmann, L; Lux, D

    1986-01-01

    The special investigation programme for monitoring radioactive immissions, which was primarily concerned with drinking water, initially led to the discovery of high rates of precipitate pollution by I-131, I-132, Cs-134, Cs-137 and Te-132. Since initial investigations had revealed no increases in total alpha and tritium values, gamma-spectrometric determinations were effected exclusively for single nuclides. Later on, a considerable accumulation of the nuclides Cs-134, Cs-137 and Ru-103 was discoverd in the sediments of surface bodies of water and in sewage sludges. The effects of the reactor accident on surface water are still being monitored in a long-term metering programme. (DG).

  15. Comparison of the surface contamination of class A shielded containment gloves and a standard shielded containment - professional practices evaluation radiopharmacy Public assistance Marseille hospitals; Comparaison de la contamination de surface des gants d'une enceinte blindee de classe A et d'une enceinte blindee Standard - EPP radiopharmacie APHM

    Energy Technology Data Exchange (ETDEWEB)

    Lopez, V.; Giraud, F.; Pisano, P.; Guillet, B. [CHU Nord, Marseille, Service de radiopharmacie, 13 (France); CHU Timone, service de radiopharmacie, 13 - Marseille (France)

    2010-07-01

    Purpose: The pole of Pharmacy of 'Assistance Publique des Hopitaux de Marseille' initiated a process of evaluation of professional practice. The two functional units of radiopharmacy are involved by comparing the surface contamination of gloves of a class A cell and a standard shielded cell, both in class D premises. Conclusions: In a shielded Class A cell placed in class D premises, there is microbial contamination of gloves probably due to the introduction of not disinfected equipment. In a standard shielded cell where contamination is most important, gloves cleaning should be performed several times during the workday, at least every four hours with a surface bactericidal and fungicidal agent. (N.C.)

  16. Radioactive Decay

    Science.gov (United States)

    Radioactive decay is the emission of energy in the form of ionizing radiation. Example decay chains illustrate how radioactive atoms can go through many transformations as they become stable and no longer radioactive.

  17. Groundwater monitoring and modelling of the “Vector” site for near-surface radioactive waste disposal in the Chornobyl exclusion zone

    Directory of Open Access Journals (Sweden)

    D. Bugai

    2017-12-01

    Full Text Available Results of purposeful groundwater monitoring and modelling studies are presented, which were carried out in order to better understand groundwater flow patterns from the “Vector” site for near-surface radioactive waste disposal and storage in the Chornobyl exclusion zone towards river network. Both data of observations at local-scale monitoring well network at “Vector” site carried out in 2015 - 2016 and modelling analyses using the regional groundwater flow model of Chornobyl exclusion zone suggest that the groundwater discharge contour for water originating from “Vector” site is Sakhan River, which is the tributary to Pripyat River. The respective groundwater travel time is estimated at 210 - 340 years. The travel times in subsurface for 90Sr, 137Cs, and transuranium radionuclides (Pu isotopes, 241Am are estimated respectively at thousands, tenths of thousands, hundreds of thousands – million of years. These results, as well as presented data of analyses of lithological properties of the geological deposits of the unsaturated zone at “Vector” site, provide evidence for good protection of surface water resources from radioactivity sources (e.g., radioactive wastes to be disposed in the near-sursface facilities at “Vector” site.

  18. Evaluation method of gas leakage rate from transportation casks of radioactive materials (gas leakage rates from scratches on O-ring surface)

    International Nuclear Information System (INIS)

    Aritomi, Masanori; Li Ninghua; Asano, Ryoji; Kawa, Tsunemichi

    2004-01-01

    A sealing function is essential for transportation and/or storage casks of radioactive materials under both normal and accidental operating conditions in order to prevent radioactive materials from being released into the environment. In the safety analysis report, the release rate of radioactive materials into the environment is evaluated using the correlations specified in the ANSI N14.5, 1987. The purposes of the work are to reveal the underlying problems on the correlations specified in the ANSI N14.5 related to gas leakage rates from a scratch on O-ring surface and from multi-leak paths, to offer a data base to study the evaluation method of the leakage rate and to propose the evaluation method. In this paper, the following insights were obtained and clarified: 1. If a characteristic value of a leak path is defined as D 4 /a ('D' is the diameter and 'a' is the length), a scratch on the O-ring surface can be evaluated as a circular tube. 2. It is proper to use the width of O-ring groove on the flange as the leak path length for elastomer O-rings. 3. Gas leakage rates from multi leak paths of the transportation cask can be evaluated in the same manner as a single leak path if an effective D4/a is introduced. (author)

  19. Study of a method of detection for natural carbon-14 using a liquid scintillator, recent variations in the natural radio-activity due to artificial carbon-14 (1963); Etude d'une methode de detection du carrons 14 naturel, utilisant un scintillateur liquide - variations recentes de l'activite naturelle dues au carbone 14 artificiel (1963)

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-06-15

    Among the various natural isotopes of carbon, a radioactive isotope, carbon-14, is formed by the action of secondary neutrons from cosmic rays on nitrogen in the air. Until 1950, the concentration of this isotope in ordinary carbon underwent weak fluctuations of about 2-3 per cent. The exact measurement of this concentration 6 X 10{sup 12} Ci/gm of carbon, and of its fluctuations, are difficult and in the first part of this report a highly sensitive method is given using a liquid scintillator. Since 1950 this natural activity has shown large fluctuations because of the carbon-14 formed during nuclear explosions, and in the second part, the evolution in France of this specific activity of carbon in the atmosphere and biosphere is examined. In the last part is studied the local increase in carbon activity in the atmosphere around the Saclay site, an increase caused by the carbon-14 given off as C{sup 14}O{sub 2}, by the reactors cooled partially with exterior air. (author) [French] Parmi les differents isotopes naturels du carbone, un isotope radioactif, le carbone 14, est forme par l'action de neutrons secondaires due aux rayons cosmiques sir l'azote de l'air. Jusqu'en 1950, la concentration de cet isotope dans le carbone ordinaire est soumise a des fluctuations de faible amplitude, de l'ordre de 2 a 3 pour cent. Les mesures precises de cette concentration, 6. 10{sup -12} Ci/g de carbone, et de ses fluctuations sont delicates, et dans la premiere partie de ce rapport, on decrit une methode de detection a grande sensibilite utilisant un scintillateur liquide. Depuis 1950, cette activite naturelle subit des fluctuations importantes dues au carbone 14 forme lors des explosions nucleaires, et dans la seconde partie, on examine l'evolution en France de l'activite specifique du carbone de l'atmosphere et ce la biosphere. Dans la derniere partie, on etudie l'accroissement local de l'activite du carbone de l'air aux environs du site de Saclay, accroissement provoque par le

  20. Study of a method of detection for natural carbon-14 using a liquid scintillator, recent variations in the natural radio-activity due to artificial carbon-14 (1963); Etude d'une methode de detection du carrons 14 naturel, utilisant un scintillateur liquide - variations recentes de l'activite naturelle dues au carbone 14 artificiel (1963)

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-06-15

    Among the various natural isotopes of carbon, a radioactive isotope, carbon-14, is formed by the action of secondary neutrons from cosmic rays on nitrogen in the air. Until 1950, the concentration of this isotope in ordinary carbon underwent weak fluctuations of about 2-3 per cent. The exact measurement of this concentration 6 X 10{sup 12} Ci/gm of carbon, and of its fluctuations, are difficult and in the first part of this report a highly sensitive method is given using a liquid scintillator. Since 1950 this natural activity has shown large fluctuations because of the carbon-14 formed during nuclear explosions, and in the second part, the evolution in France of this specific activity of carbon in the atmosphere and biosphere is examined. In the last part is studied the local increase in carbon activity in the atmosphere around the Saclay site, an increase caused by the carbon-14 given off as C{sup 14}O{sub 2}, by the reactors cooled partially with exterior air. (author) [French] Parmi les differents isotopes naturels du carbone, un isotope radioactif, le carbone 14, est forme par l'action de neutrons secondaires due aux rayons cosmiques sir l'azote de l'air. Jusqu'en 1950, la concentration de cet isotope dans le carbone ordinaire est soumise a des fluctuations de faible amplitude, de l'ordre de 2 a 3 pour cent. Les mesures precises de cette concentration, 6. 10{sup -12} Ci/g de carbone, et de ses fluctuations sont delicates, et dans la premiere partie de ce rapport, on decrit une methode de detection a grande sensibilite utilisant un scintillateur liquide. Depuis 1950, cette activite naturelle subit des fluctuations importantes dues au carbone 14 forme lors des explosions nucleaires, et dans la seconde partie, on examine l'evolution en France de l'activite specifique du carbone de l'atmosphere et ce la biosphere. Dans la derniere partie, on etudie l'accroissement local de l'activite du carbone de l'air aux

  1. Une offre publique de documents ?

    OpenAIRE

    Tesnière, Valérie

    2017-01-01

    TOUT NUMÉRIQUE ? LE LIVRE CONCURRENCÉ ? LA BIBLIOTHÈQUE CONCURRENCÉE ? La fracture numérique reste une réalité comme l’attestent encore des chiffres cités par Le Monde : une évolution de la couverture Internet dans le monde à l’horizon 2009-2030 donnerait la projection suivante : 24,7 % des 6,8 milliards d’habitants de la planète sont connectés en 2009 et l’on atteindrait 50 % pour 8,2 milliards d’habitants en 2030. Cela interroge indirectement le statut futur du papier : sera-t-il l’apanage ...

  2. Development of Risk Insights for Regulatory Review of a Near-Surface Disposal Facility for Radioactive Waste

    International Nuclear Information System (INIS)

    Esh, D.W.; Ridge, A.C.; Thaggard, M.

    2006-01-01

    Section 3116 of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005 (NDAA) requires the Department of Energy (DOE) to consult with the Nuclear Regulatory Commission (NRC) about non-High Level Waste (HLW) determinations. In its consultative role, NRC performs technical reviews of DOE's waste determinations but does not have regulatory authority over DOE's waste disposal activities. The safety of disposal is evaluated by comparing predicted disposal facility performance to the performance objectives specified in NRC regulations for the disposal of low-level waste (10 CFR Part 61 Subpart C). The performance objectives contain criteria for protection of the public, protection of inadvertent intruders, protection of workers, and stability of the disposal site after closure. The potential radiological dose to receptors typically is evaluated with a performance assessment (PA) model that simulates the release of radionuclides from the disposal site, transport of radionuclides through the environment, and exposure of potential receptors to residual contamination for thousands of years. This paper describes NRC's development and use of independent performance assessment modeling to facilitate review of DOE's non-HLW determination for the Saltstone Disposal Facility (SDF) at the Savannah River Site. NRC's review of the safety of near-surface disposal of radioactive waste at the SDF was facilitated and focused by risk insights developed with an independent PA model. The main components of NRC's performance assessment model are presented. The development of risk insights that allow the staff to focus review efforts on those areas that are most important to satisfying the performance objectives is discussed. Uncertainty analysis was performed of the full stochastic model using genetic variable selection algorithms. The results of the uncertainty analysis were then used to guide the development of simulations of other scenarios to understand the key risk

  3. Une introduction à MATLAB c

    OpenAIRE

    CREMONA, Christian; LABORATOIRE CENTRAL DES PONTS ET CHAUSSEES - LCPC

    2002-01-01

    MATLAB c présente toutes les fonctionnalités des approches récentes de la programmation : programmation objet basée sur des hiérarchies de classes, programmation événementielle du graphisme. MATLAB c présente une aide en ligne très complète sous format html des différentes fontions accessibles. COMPTE RENDU DE RECHERCHE

  4. Radioactive pollution, ch. 6

    International Nuclear Information System (INIS)

    Anon.

    1976-01-01

    Disposal of radioactive wastes from nuclear power plants into surface waters as well as the atmosphere is discussed. Man-rem data are compared and expected quantities for disposal by power plants in the Netherlands are tabulated

  5. Study of airborne particles during the impact of droplets on a dry surface or on a liquid film; Etude de la mise en suspension de micro-gouttelettes lors de l'impact d'une goutte sur une surface seche ou sur un film liquide

    Energy Technology Data Exchange (ETDEWEB)

    Motzkus, C.; Gensdarmes, F. [Institut de Radioprotection et de Surete Nucleaire (IRSN), Service d' Etudes et de Recherches en Aerodispersion des polluants et en Confinement, 91 - Gif sur Yvette (France); Motzkus, C.; Gehin, E. [Paris-12 Univ., Centre d' Etudes et de Recherches en Thermique, Environnement et Systeme, 94 - Creteil (France)

    2007-07-01

    The safety analyses of the nuclear facilities require extensive knowledge on the airborne micro-droplet, in order to assess the potential sources of contamination in the case of hypothetical scenarios of accidental falls of liquids caused by leakage or discharge from a container. There are very few data in the literature in the case of the impaction of millimeter-size droplets on the airborne particles. The objective of our work is to study experimentally the emission of the particles during the impaction on a dry or wet plane surface, in order to understand the mechanisms leading to the airborne icles. First experiments are carried out in order to study the airborne particles produced by the free falls of droplet according to the fall height. These results are faced with a semi empirical correlation, which describes the transition between deposition and splash. In the case of a dripping of 3.84 mm-diameter droplets, our results show that the splash occurs for a fall height above 30 cm, which leads to resuspension fractions between 1,9 10{sup -6} at 46 cm and 7,5 10{sup -6} at 80 cm. (authors)

  6. Using radioactivity

    International Nuclear Information System (INIS)

    1982-10-01

    The leaflet discusses the following: radioactivity; radioisotopes; uses of ionising radiations; radioactivity from (a) naturally occurring radioactive elements, and (b) artificially produced radioisotopes; uses of radioactivity in medicine, (a) clinical diagnostic, (b) therapeutic (c) sterilization of medical equipment and materials; environmental uses as tracers; industrial applications, e.g. tracers and radiography; ensuring safety. (U.K.)

  7. Radioactive aerosols

    International Nuclear Information System (INIS)

    Chamberlain, A.C.

    1991-01-01

    Radon. Fission product aerosols. Radioiodine. Tritium. Plutonium. Mass transfer of radioactive vapours and aerosols. Studies with radioactive particles and human subjects. Index. This paper explores the environmental and health aspects of radioactive aerosols. Covers radioactive nuclides of potential concern to public health and applications to the study of boundary layer transport. Contains bibliographic references. Suitable for environmental chemistry collections in academic and research libraries

  8. MRS [monitored retrievable storage] systems study Task G report: The role and functions of surface storage of radioactive material in the federal waste management system

    International Nuclear Information System (INIS)

    Wood, T.W.; Short, S.M.; Woodruff, M.G.; Altenhofen, M.K.; MacKay, C.A.

    1989-04-01

    This is one of nine studies undertaken by contractors to the US Department of Energy (DOE), Office of Civilian Radioactive Waste Management (OCRWM), to provide a technical basis for re-evaluating the role of a monitored retrievable storage (MRS) facility. The study investigates the functions that could be performed by surface storage of radioactive material within the federal radioactive waste management system, including enabling acceptance of spent fuel from utility owners, scheduling of waste-preparation processes within the system, enhancement of system operating reliability, and conditioning the thermal (decay heat) characteristics of spent fuel emplaced in a repository. The analysis focuses particularly on the effects of storage capacity and DOE acceptance schedule on power reactors. Figures of merit developed include the storage capacity [in metric tons of uranium (MTU)] required to be added beyond currently estimated maximum spent fuel storage capacities and its associated cost, and the number of years that spent fuel pools would remain open after last discharge (in pool-years) and the cost of this period of operation. 27 refs., 36 figs., 18 tabs

  9. Analysis of surface contributions to external doses in a radioactively contaminated urban environment designed by the EMRAS-2 Urban Areas Working Group

    International Nuclear Information System (INIS)

    Hwang, Won Tae; Jeong, Hae Sun; Jeong, Hyo Joon; Kim, Eun Han; Han, Moon Hee; Kim, In Gyu

    2013-01-01

    Highlights: ► External dose and contribution from radio-activated surface were evaluated for EMRAS-2 Urban Areas Working Group scenarios. ► The external doses showed a distinctive difference with the locations and precipitation. ► The contribution of contaminated surfaces for external dose depends on locations and precipitation. ► These results provide the essential information for decision-making support of countermeasures. - Abstract: The EMRAS-2 Urban Areas Working Group, which is supported by the IAEA, has designed a variety of accidental scenarios to test and improve the capabilities of the models used for an evaluation of radioactive contamination in an urban environment. A variety of models including a Korean model, METRO-K, are used for predictive results on the hypothetical scenarios. This paper describes the predictive results of METRO-K for the hypothetical scenarios designed in the Working Group. The external dose resulting from the air contamination of Co-60 was evaluated, and its contribution was analyzed with time as a function of the location of a receptor and precipitation conditions at the time of the contamination event. As a result, the external doses showed a distinctive difference with the locations to be evaluated and the precipitation conditions. Moreover, the contribution of contaminated surfaces for external doses was strongly dependent on the locations to be evaluated and the precipitation conditions. These results will provide essential information to assist the decision-making of appropriate countermeasures in an emergency situation of a radioactively contaminated urban environment

  10. Final report: survey and removal of radioactive surface contamination at environmental restoration sites, Sandia National Laboratories/New Mexico. Volume 1

    International Nuclear Information System (INIS)

    Lambert, K.A.; Mitchell, M.M.; Jean, D.; Brown, C.; Byrd, C.S.

    1997-09-01

    This report describes the survey and removal of radioactive surface contamination at Sandia's Environmental Restoration (ER) sites. Radiological characterization was performed as a prerequisite to beginning the Resource Conservation and Recovery Act (RCRA) corrective action process. The removal of radioactive surface contamination was performed in order to reduce potential impacts to human health and the environment. The predominant radiological contaminant of concern was depleted uranium (DU). Between October 1993 and November 1996 scanning surface radiation surveys, using gamma scintillometers, were conducted at 65 sites covering approximately 908 acres. A total of 9,518 radiation anomalies were detected at 38 sites. Cleanup activities were conducted between October 1994 and November 1996. A total of 9,122 anomalies were removed and 2,072 waste drums were generated. The majority of anomalies not removed were associated with a site that has subsurface contamination beyond the scope of this project. Verification soil samples (1,008 total samples) were collected from anomalies during cleanup activities and confirm that the soil concentration achieved in the field were far below the target cleanup level of 230 pCi/g of U-238 (the primary constituent of DU) in the soil. Cleanup was completed at 21 sites and no further radiological action is required. Seventeen sites were not completed since cleanup activities wee precluded by ongoing site activity or were beyond the original project scope

  11. Final report: survey and removal of radioactive surface contamination at environmental restoration sites, Sandia National Laboratories/New Mexico. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    Lambert, K.A.; Mitchell, M.M. [Brown and Root Environmental, Albuquerque, NM (United States); Jean, D. [MDM/Lamb, Inc., Albuquerque, NM (United States); Brown, C. [Environmental Dimensions, Inc., Albuquerque, NM 87109 (United States); Byrd, C.S. [Sandia National Labs., Albuquerque, NM (United States)

    1997-09-01

    This report describes the survey and removal of radioactive surface contamination at Sandia`s Environmental Restoration (ER) sites. Radiological characterization was performed as a prerequisite to beginning the Resource Conservation and Recovery Act (RCRA) corrective action process. The removal of radioactive surface contamination was performed in order to reduce potential impacts to human health and the environment. The predominant radiological contaminant of concern was depleted uranium (DU). Between October 1993 and November 1996 scanning surface radiation surveys, using gamma scintillometers, were conducted at 65 sites covering approximately 908 acres. A total of 9,518 radiation anomalies were detected at 38 sites. Cleanup activities were conducted between October 1994 and November 1996. A total of 9,122 anomalies were removed and 2,072 waste drums were generated. The majority of anomalies not removed were associated with a site that has subsurface contamination beyond the scope of this project. Verification soil samples (1,008 total samples) were collected from anomalies during cleanup activities and confirm that the soil concentration achieved in the field were far below the target cleanup level of 230 pCi/g of U-238 (the primary constituent of DU) in the soil. Cleanup was completed at 21 sites and no further radiological action is required. Seventeen sites were not completed since cleanup activities wee precluded by ongoing site activity or were beyond the original project scope.

  12. Examination of a measuring method for fallout radioactivity released by the accident of the Fukushima Dai-ichi NPS. Surface contamination measurement

    International Nuclear Information System (INIS)

    Yoshii, Taiki; Kawasaki, Satoru

    2013-08-01

    Radioactive nuclides were released in the atmosphere by the accident of TEPCO's Fukushima Dai-ichi Nuclear Power Station in March, 2011, and they are detected on the materials that had no artificial radioactive nuclides before the accident. Confronted with this situation, NISA issued a guideline titled 'A guideline regarding treatment of materials in nuclear facilities considering the influence of fallout released from the accident of TEPCO's Fukushima Dai-ichi Nuclear Power Station' on March 30, 2012. Nuclear Regulatory Authority refers to applying the existing bylaw until the time to make decision of the updated bylaw. The guideline shows that after judging whether there is the influence of fallout or not, the conventional clearance and NR systems can be used when there is no influence of fallout. On the other hand, the special treatment is required when it is judged that there is the influence. This report describes a specific example of measuring method to evaluate the influence of fallout, in case of surface contamination. This report focused surface contamination of flat object as target. Preliminary investigation shows that the distribution of surface contamination due to fallout is near to lognormal distribution. Therefore, the sampling measurement can be adopted. The average surface contamination of target is decided from sampling data by using 90% upper confidence limit of Chebyshev inequality. Also, the minimum sampling number is decided. The evaluation of the influence of fallout is judged from the result of surface contamination measurement, weight of target and surface area of target. (author)

  13. Adsorption and activation of methane and methanol on Pt(100) surface: a density functional study; Adsorption et activation du methane et du methanol sur la surface (100) du platine: une etude par la fonctionnelle de la densite

    Energy Technology Data Exchange (ETDEWEB)

    Moussounda, P.S

    2006-11-15

    The activation of methane (CH{sub 4}) and methanol (CH{sub 3}OH) on Pt(100) surface has been investigated using density functional theory calculations based on plane-wave basis and pseudo-potential. We optimised CH{sub 4}/Pt(100) system. The calculated adsorption energies over the top, bridge and hollow sites are small, weakly dependent on the molecular orientation. The nature of the CH{sub 4}-Pt interaction was examined through the electronic structure changes. The adsorption of methyl (CH{sub 3}) and hydrogen (H) and the co-adsorption of CH{sub 3}+H were also calculated. From these results, we examined the dissociation of CH{sub 4} to CH{sub 3}+H, and the activation energies found are in good agreement with the experimental and theoretical values. The activation of CH{sub 3}OH/Pt(100) has been studied. All the sites have almost the same adsorption energy. The adsorption of oxygen (O) and the co-adsorption of CH{sub 4} and O were also examined. In addition, the formation of CH{sub 3}OH assuming a one-step mechanism step via the co-adsorption of CH{sub 4}+O has been studied and the barrier height was found to be high. (authors)

  14. Radioactive thickness gauge (1962); Jauge d'epaisseur radioactive (1962)

    Energy Technology Data Exchange (ETDEWEB)

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

    1962-07-01

    The author describes a thickness gauge in which the scintillating crystal detector alternately 'sees' a radioactive source through the material which is to be measured and then a control source of the same material; the radiations are separated in time by an absorbing valve whose sections are alternately full and hollow. The currents corresponding to the two sources are separated beyond the photomultiplier tube by a detector synchronized with the rotation of the valve. The quotient of these two currents is then obtained with a standard recording potentiometer. It is found that the average value of the response which is in the form G = f(I{sub 1}/I{sub 2}) is not affected by decay of the radioactive sources, and that it is little influenced by variations of high tension, temperature, or properties of the air in the source detector interval. The performance of the gauge is given. (author) [French] L'auteur decrit une jauge d'epaisseur dans laquelle le cristal scintillant detecteur 'voit' alternativement une source radioactive a travers le materiau a mesurer, puis une source de reference de meme nature; la separation des rayonnements est faite dans le temps a l'aide d'un volet absorbeur a secteurs alternativement pleins et creux. Les courants correspondants aux deux sources sont separes apres le tube photomultiplicateur par un detecteur synchrone avec la rotation du volet. On fait ensuite le quotient de ces deux courants a l'aide d'un potientometre enregistreur classique. il resulte de cette disposition que la valeur moyenne de la reponse, qui est de la forme G = f(I{sub 1}/I{sub 2}) n'est pas affectee par la decroissance des sources radioactives, et qu'elle est peu sensible aux variations de haute tension, de temperature ou des proprietes de l'air dans l'intervalle source-detecteur. On donne les performances de cette jauge. (auteur)

  15. Management of Radioactive Wastes

    International Nuclear Information System (INIS)

    Tchokosa, P.

    2010-01-01

    Management of Radioactive Wastes is to protect workers and the public from the radiological risk associated with radioactive waste for the present and future. It application of the principles to the management of waste generated in a radioisotope uses in the industry. Any material that contains or is contaminated with radionuclides at concentrations or radioactivity levels greater than ‘exempt quantities’ established by the competent regulatory authorities and for which no further use is foreseen or intended. Origin of the Radioactive Waste includes Uranium and Thorium mining and milling, nuclear fuel cycle operations, Operation of Nuclear power station, Decontamination and decommissioning of nuclear facilities and Institutional uses of isotopes. There are types of radioactive waste: Low-level Waste (LLW) and High-level Waste. The Management Options for Radioactive Waste Depends on Form, Activity, Concentration and half-lives of the radioactive waste, Storage and disposal methods will vary according to the following; the radionuclides present, and their concentration, and radio toxicity. The contamination results basically from: Contact between radioactive materials and any surface especially during handling. And it may occur in the solid, liquid or gas state. Decontamination is any process that will either reduce or completely remove the amount of radionuclides from a contaminated surface

  16. The Impact of Biofilms upon Surfaces Relevant to an Intermediate Level Radioactive Waste Geological Disposal Facility under Simulated Near-Field Conditions

    Directory of Open Access Journals (Sweden)

    Christopher J. Charles

    2017-07-01

    Full Text Available The ability of biofilms to form on a range of materials (cementious backfill (Nirex Reference Vault Backfill (NRVB, graphite, and stainless steel relevant to potential UK intermediate level radioactive waste (ILW disposal concepts was investigated by exposing these surfaces to alkaliphilic flocs generated by mature biofilm communities. Flocs are aggregates of biofilm material that are able to act as a transport vector for the propagation of biofilms. In systems where biofilm formation was observed there was also a decrease in the sorption of isosaccharinic acids to the NRVB. The biofilms were composed of cells, extracellular DNA (eDNA, proteins, and lipids with a smaller polysaccharide fraction, which was biased towards mannopyranosyl linked carbohydrates. The same trend was seen with the graphite and stainless steel surfaces at these pH values, but in this case the biofilms associated with the stainless steel surfaces had a distinct eDNA basal layer that anchored the biofilm to the surface. At pH 13, no structured biofilm was observed, rather all the surfaces accumulated an indistinct organic layer composed of biofilm materials. This was particularly the case for the stainless steel coupons which accumulated relatively large quantities of eDNA. The results demonstrate that there is the potential for biofilm formation in an ILW-GDF provided an initiation source for the microbial biofilm is present. They also suggest that even when conditions are too harsh for biofilm formation, exposed surfaces may accumulate organic material such as eDNA.

  17. Radioactive wastes

    International Nuclear Information System (INIS)

    Straub, C.P.

    1975-01-01

    A review is presented on the environmental behavior of radioactive wastes. The management of high-level wastes and waste disposal methods were discussed. Some topics included were ore processing, coagulation, absorption and ion exchange, fixation, ground disposal, flotation, evaporation, transmutation and extraterrestrial disposal. Reports were given of the 226 Ra, 224 Ra and tritium activity in hot springs, 90 Sr concentrations in the groundwater and in White Oak Creek, radionuclide content of algae, grasses and plankton, radionuclides in the Danube River, Hudson River, Pacific Ocean, Atlantic Ocean, Lake Michigan, Columbia River and other surface waters. Analysis showed that 239 Pu was scavenged from Lake Michigan water by phytoplankton and algae by a concentration factor of up to 10,000. Benthic invertebrates and fish showed higher 239 Pu concentrations than did their pelagic counterparts. Concentration factors are also given for 234 Th, 60 Co, Fe and Mr in marine organisms. Two models for predicting the impact of radioactivity in the food chain on man were mentioned. In an accidental release from a light-water power reactor to the ocean, the most important radionuclides discharged were found to be 90 Sr, 137 Cs, 239 Pu and activation products 65 Zr, 59 Fe, and 95 Zr

  18. The development of the American National Standard 'control of radioactive surface contamination on materials equipment and facilities to be released for uncontrolled use'

    International Nuclear Information System (INIS)

    Shapiro, J.

    1980-01-01

    A new standard submitted by the Health Physics Society Standards Committee to the American National Standards Institute concerning radioactive surface contamination of materials and equipment is discussed. The chronological events in the development of this standard are given. The standard provides criteria for the release for uncontrolled use of materials, equipment and facilities contaminated or potentially contaminated with radioactivity. Permissible contamination limits are specified for: 1) long lived alpha emitters except natural uranium and thorium, 2) more hazardous beta-gamma emitters, 3) less hazardous beta-gamma emitters and 4) natural uranium and thorium. A contamination reference level of 1000 dpm/100 cm 2 for 90 Sr was set as the basis for assigning limits to radionuclides presenting an ingestion hazard and other radionuclides were grouped based on the values of their maximum permissible concentration (MPC) in water relative to 90 Sr. The contamination limit for 239 Pu was chosen as the basis for assigning limits based on MPC in air to radionuclides presenting an inhalation hazard; a value of 100 dpm/100 cm 2 was adopted in the standard. An upper limit of 5000 dpm/100 cm 2 for surface contamination was selected for the standard. (UK)

  19. Insuffler une énergie nouvelle : donner une voix et une visibilité aux ...

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

    22 oct. 2010 ... J'ai accepté, car cette méthode nous permettait de tenir une véritable consultation auprès des jeunes du Brésil. CRDI – Pouvez-vous nous expliquer en quoi consiste cette méthode ? Grzybowski – Les sondages d'opinion sont importants, mais c'est un peu comme si on tâtait le pouls d'un patient. De même ...

  20. Decontamination of radioactively contaminated surfaces - Method for testing and assessing the ease of decontamination (International Standard Publication ISO 8690:1988)

    International Nuclear Information System (INIS)

    Stefanik, J.

    2001-01-01

    The specifications laid down in this International Standard apply to the testing of surfaces which may become contaminated by radioactive materials. Decontaminability data obtained using this test method are not applicable to technical systems where layers of contaminating materials are formed as a result of long-term application of higher temperatures and pressures (for example primary circuits of nuclear reactors). The purpose of the test is to assess the ease of decontamination of surfaces under laboratory conditions. In practical applications, it may be important to consider other qualities, such as chemical, mechanical and radiation resistance and long-term stability in the selection of the materials to be used. It should be recognized that further decontamination tests under simulated service conditions may be needed

  1. A mathematical model for the performance assessment of engineering barriers of a typical near surface radioactive waste disposal facility

    Energy Technology Data Exchange (ETDEWEB)

    Antonio, Raphaela N.; Rotunno Filho, Otto C. [Universidade Federal, Rio de Janeiro, RJ (Brazil). Coordenacao dos Programas de Pos-graduacao de Engenharia. Lab. de Hidrologia e Estudos do Meio Ambiente]. E-mail: otto@hidro.ufrj.br; Ruperti Junior, Nerbe J.; Lavalle Filho, Paulo F. Heilbron [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil)]. E-mail: nruperti@cnen.gov.br

    2005-07-01

    This work proposes a mathematical model for the performance assessment of a typical radioactive waste disposal facility based on the consideration of a multiple barrier concept. The Generalized Integral Transform Technique is employed to solve the Advection-Dispersion mass transfer equation under the assumption of saturated one-dimensional flow, to obtain solute concentrations at given times and locations within the medium. A test-case is chosen in order to illustrate the performance assessment of several configurations of a multi barrier system adopted for the containment of sand contaminated with Ra-226 within a trench. (author)

  2. A mathematical model for the performance assessment of engineering barriers of a typical near surface radioactive waste disposal facility

    International Nuclear Information System (INIS)

    Antonio, Raphaela N.; Rotunno Filho, Otto C.

    2005-01-01

    This work proposes a mathematical model for the performance assessment of a typical radioactive waste disposal facility based on the consideration of a multiple barrier concept. The Generalized Integral Transform Technique is employed to solve the Advection-Dispersion mass transfer equation under the assumption of saturated one-dimensional flow, to obtain solute concentrations at given times and locations within the medium. A test-case is chosen in order to illustrate the performance assessment of several configurations of a multi barrier system adopted for the containment of sand contaminated with Ra-226 within a trench. (author)

  3. Radioactive source

    International Nuclear Information System (INIS)

    Drabkina, L.E.; Mazurek, V.; Myascedov, D.N.; Prokhorov, P.; Kachalov, V.A.; Ziv, D.M.

    1976-01-01

    A radioactive layer in a radioactive source is sealed by the application of a sealing layer on the radioactive layer. The sealing layer can consist of a film of oxide of titanium, tin, zirconium, aluminum, or chromium. Preferably, the sealing layer is pure titanium dioxide. The radioactive layer is embedded in a finish enamel which, in turn, is on a priming enamel which surrounds a substrate

  4. Radioactive beams produced by the ISOL method: development for laser ionization and for surface ionization; Faisceaux exotiques par methode ISOL: developpements pour l'ionisation par laser et l'ionisation de surface

    Energy Technology Data Exchange (ETDEWEB)

    Hosni, Faouzi

    2004-10-01

    The works were carried out in the framework of the research program PARRNe (production of radioactive neutron-rich nuclei). This program aims to determine optimal conditions to produce intense beams of neutron-rich isotopes. This thesis treats multiple technical aspects related to the production of separate radioactive isotopes in line (ISOL). It deals mainly with the development of the target-source unit which is the key element for projects such as SPIRAL-2 or EURISOL.The first part presents the various methods using fission as production mode and compares them: fission induced by thermal neutrons, induced by fast neutrons and photofission. The experiment carried out at CERN validated the interest of the photofission as a promising production mode of radioactive ions. That is why the institute of nuclear physics of Orsay decided to build a linear electron accelerator at the Tandem d'Orsay (ALTO).The second part of this thesis deals with the development of uranium targets. The X-rays diffraction and Scanning Electron Microscopy have been used as analysis techniques. They allowed to determine the chemical and structural characteristics of uranium carbide targets as function of various heating temperatures. After the production, the process of ionization has been studied. Two types of ion source have been worked out: the first one is a surface ion source and the second one is a source based on resonant ionization by laser. These two types of sources will be used for the ALTO project. (author)

  5. Radioactivity metrology

    International Nuclear Information System (INIS)

    Legrand, J.

    1979-01-01

    Some aspects of the radioactivity metrology are reviewed. Radioactivity primary references; absolute methods of radioactivity measurements used in the Laboratoire de Metrologie des Rayonnements Ionisants; relative measurement methods; traceability through international comparisons and interlaboratory tests; production and distribution of secondary standards [fr

  6. Radioactive wastes

    International Nuclear Information System (INIS)

    Teillac, J.

    1988-01-01

    This study of general interest is an evaluation of the safety of radioactive waste management and consequently the preservation of the environment for the protection of man against ionizing radiations. The following topics were developed: radiation effects on man; radioactive waste inventory; radioactive waste processing, disposal and storage; the present state and future prospects [fr

  7. Une herboristerie ethnique à Paris

    OpenAIRE

    Hamaïdi , Maurad

    2012-01-01

    Place de la Chapelle à Paris, dans le 18e arrondissement. L'enseigne de ce magasin est peu explicite, mais la vitrine laisse deviner le type de produits vendus. L'information est un peu plus développée dans la langue arabe car il y est précisé que la vente concerne tous types d'encens, ainsi que des plantes arabes : il s'agit d'une herboristerie. Il est également écrit que le magasin exporte vers le Maroc : le mot en arabe est ambigu puisqu'il s'agit de "Maghreb", mais en général, utilisé seu...

  8. Conceptual designs of near surface disposal facility for radioactive waste arising from the facilities using radioisotopes and research facilities for nuclear energy development and utilization

    International Nuclear Information System (INIS)

    Sakai, Akihiro; Yoshimori, Michiro; Okoshi, Minoru; Yamamoto, Tadatoshi; Abe, Masayoshi

    2001-03-01

    Various kinds of radioactive waste is generating from the utilization of radioisotopes in the field of science, technology, etc. and the utilization and development of nuclear energy. In order to promote the utilization of radionuclides and the research activities, it is necessary to treat and dispose of radioactive waste safely and economically. Japan Nuclear Cycle Development Institute (JNC), Japan Radioisotope Association (JRIA) and Japan Atomic Energy Research Institute (JAERI), which are the major waste generators in Japan in these fields, are promoting the technical investigations for treatment and disposal of the radioactive waste co-operately. Conceptual design of disposal facility is necessary to demonstrate the feasibility of waste disposal business and to determine the some conditions such as the area size of the disposal facility. Three institutes share the works to design disposal facility. Based on our research activities and experiences of waste disposal, JAERI implemented the designing of near surface disposal facilities, namely, simple earthen trench and concrete vaults. The designing was performed based on the following three assumed site conditions to cover the future site conditions: (1) Case 1 - Inland area with low groundwater level, (2) Case 2 - Inland area with high groundwater level, (3) Case 3 - Coastal area. The estimation of construction costs and the safety analysis were also performed based on the designing of facilities. The safety assessment results show that the safety for concrete vault type repository is ensured by adding low permeability soil layer, i.e. mixture of soil and bentonite, surrounding the vaults not depending on the site conditions. The safety assessment results for simple earthen trench also show that their safety is ensured not depending on the site conditions, if they are constructed above groundwater levels. The construction costs largely depend on the depth for excavation to build the repositories. (author)

  9. Radioactivity and nuclear waste

    International Nuclear Information System (INIS)

    Saas, A.

    1996-01-01

    Radioactive wastes generated by nuclear activities must be reprocessed using specific treatments before packaging, storage and disposal. This digest paper gives first a classification of radioactive wastes according to their radionuclides content activity and half-life, and the amount of wastes from the different categories generated each year by the different industries. Then, the radiotoxicity of nuclear wastes is evaluated according to the reprocessing treatments used and to their environmental management (surface storage or burial). (J.S.)

  10. Lethal Effect on Bacterium of Decay of Incorporated Radioactive Atoms ({sup 3}H, {sup 14}C, {sup 32}P); Effet Letal de la Desintegration d'Atomes Radioactifs ({sup 3}H, {sup 14}C, {sup 32}P) Incorpores dans une Bacterie

    Energy Technology Data Exchange (ETDEWEB)

    Apelgot, Sonia [Laboratoire Curie, Institut du Radium, Paris (France)

    1968-06-15

    The biological effect of decay of {sup 3}H, {sup 14}C and {sup 32}P incorporated into a bacterium depends on the nature of the organic molecule labelled, on the position of the isotope within it and on the isotope itself. In sum, results obtained to date show that: The decay of {sup 3}H atoms incorporated into certain macromolecules of a bacterium causes sterilization through ionization by the ss{sup -} particle emitted; transmutation is of negligible importance. This self-irradiation is comparable in effect with X-rays and is affected in a similar manner by the same factors: temperature, presence of a radioprotector, radiosensitivity of the strain. Decay of {sup 14}C or {sup 32}P atoms incorporated into bacterial DNA is lethal because of the transmutation effect; ionizations produced by emitted ss{sup -} particles may be disregarded. Survival curves for {sup 32}P transmutations depend on the experimental conditions. Some of the results obtained with {sup 32}P are similar to those obtained with X-rays, e.g. effects of temperature, radical capture and oxygen, while others are similar to those of u.v. light, e.g., effect of growth conditions. Comparative tests made with {sup 32}P indicate that the recoil energy of transmutation is not the phenomenon responsible for the lethal effect observed. Comparison of the results obtained after X-irradiation or decay of {sup 3}H or {sup 32}P incorporated into the DNA of bacteria of the same strain of E. coli shows that the efficiency of a {sup 32}P transmutation is about four times greater than that of an ionization produced at random within the same DNA. (author) [French] L'effet biologique de la desintegration de {sup 3}H, {sup 14}C et {sup 32}P incorpores dans une bacterie depend de la nature de la molecule organique marquee, de l'emplacement de l'isotope sur celle-ci et de la nature de l'isotope lui-meme. L'ensemble des resultats obtenus a ce jour montre que la desintegration des atomes de {sup 3}H incorpores dans certaines

  11. Floristic composition and plant succession on near-surface radioactive-waste-disposal facilities in the Los Alamos National Laboratory

    International Nuclear Information System (INIS)

    Tierney, G.D.; Foxx, T.S.

    1982-03-01

    Since 1946, low-level radioactive waste has been buried in shallow landfills within the confines of the Los Alamos National Laboratory. Five of these sites were studied for plant composition and successional patterns by reconnaissance and vegetation mapping. The data show a slow rate of recovery for all sites, regardless of age, in both the pinon-juniper and ponderosa pine communities. The sites are not comparable in succession or composition because of location and previous land use. The two oldest sites have the highest species diversity and the only mature trees. All sites allowed to revegetate naturally tend to be colonized by the same species that originally surrounded the sites. Sites on historic fields are colonized by the old field flora, whereas those in areas disturbed only by grazing are revegetated by the local native flora

  12. Floristic composition and plant succession on near-surface radioactive-waste-disposal facilities in the Los Alamos National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Tierney, G.D.; Foxx, T.S.

    1982-03-01

    Since 1946, low-level radioactive waste has been buried in shallow landfills within the confines of the Los Alamos National Laboratory. Five of these sites were studied for plant composition and successional patterns by reconnaissance and vegetation mapping. The data show a slow rate of recovery for all sites, regardless of age, in both the pinon-juniper and ponderosa pine communities. The sites are not comparable in succession or composition because of location and previous land use. The two oldest sites have the highest species diversity and the only mature trees. All sites allowed to revegetate naturally tend to be colonized by the same species that originally surrounded the sites. Sites on historic fields are colonized by the old field flora, whereas those in areas disturbed only by grazing are revegetated by the local native flora.

  13. Radioactive battery

    International Nuclear Information System (INIS)

    Deaton, R.L.; Silver, G.L.

    1975-01-01

    A radioactive battery is described that is comprised of a container housing an electrolyte, two electrodes immersed in the electrolyte and insoluble radioactive material disposed adjacent one electrode. Insoluble radioactive material of different intensity of radioactivity may be disposed adjacent the second electrode. If hydrobromic acid is used as the electrolyte, Br 2 will be generated by the radioactivity and is reduced at the cathode: Br 2 + 2e = 2 Br - . At the anode Br - is oxidized: 2Br - = Br 2 + 2e. (U.S.)

  14. Determination of the Concentration of Radioactive Nuclides of Surface Soils of some Hadhramout's Valleys in Yemen Using Gamma-Ray Spectrometry

    International Nuclear Information System (INIS)

    Bazohair, A. O.; Bayashoot, A. K.; AL-Shamy, A. A.

    2004-01-01

    In this research five surface soil samples have been taken from some Hadhramout's valleys in Yemen (Khrid , Arf , Huwayrah , Buwaish, Khirba ) in the years from (1999) to (2002) and analyzed using gamma-ray spectrometry. The spectra of samples were measured using multichannel analyzer (MCA) that was connected with measurement system for this purpose.A high purity germanium(Hp Ge) detector with resolution of (2.11 keV) at gamma-line(1332 keV) of radioactive source(Co-60) used for detecting ( U 238 , Th 232 , K 40 , Cs 137 ) in the samples. The results showed that the average concentration of radioactive nuclides in the samples of uranium ranged from(37.56 Bq/Kg) to(46.58 Bq/Kg) and for thorium ranged from(37.93 Bq/Kg) to(47.28 Bq/Kg) and for potassium ranged from(347.57 Bq/Kg) to(850.10 Bq/Kg) and for cesium ranged from(6.94 Bq/Kg) to(15.86 Bq/Kg) and the measured precision of samples ranged from(4.71%) to (9.23%). (authors)

  15. Xanthomatose normolipidemique a localisation nasale chez une ...

    African Journals Online (AJOL)

    Introduction : Exposer un cas de xanthomatose normolipidémique. Observation : il s'agit d'une adolescente de 18 ans qui a présenté une masse des cavités nasales dont le bilan paraclinique a plaidé en faveur d'un xanthogranulome juvénile. L'évolution à court terme a été satisfaisante après l'exérèse chirurgicale par une ...

  16. CONSIDERATIONS ON SOILS ISOLATIVE PROPERTIES FOR SITING OF A NEW NEAR-SURFACE RADIOACTIVE WASTE REPOSITORY IN POLAND IN THE LIGHT OF THE LONG TERM SAFETY

    Directory of Open Access Journals (Sweden)

    Monika Skrzeczkowska

    2012-07-01

    Full Text Available The paper presents a brief description of the occurrence of favorable isolative conditions for new surface radioactive waste repository in Poland. Selected soils may be used as a natural bottom layer or engineering barrier in multi-barrier system of RW repository. Currently, there is no regulation establishing standards for the bottom isolation, and the only quantifiable parameter with regard to water permeability is given for the repository objects, which in their case has to be lower than 10-9 m/s. For the purposes of this paper, treating on providing suitable bottom isolation for the new repository, this parameter has been transferred onto the consideration for soils suitability with a statement that it shall not be lower than the one given for the infrastructure. Submitted information should be taken into consideration by updating the information for the siting process according to IAEA Safety Standards.

  17. Materials and proportion's design of self-compacting mortar used for low diffusion layer in sub-surface radioactive waste disposal facility in Japan

    International Nuclear Information System (INIS)

    Niwase, Kazuhito; Sugihashi, Naoyuki; Tsuji, Yukikazu

    2010-01-01

    This paper describes the design procedure for the material selection and mix proportion of the self-compacting mortar used for low diffusion layer cementitious material in the sub-surface radioactive waste disposal facility in Japan. The low diffusion layer is required for reducing transportation by controlling diffusion of a radionuclide. Therefore the low diffusion, cracks control, and low leaching are the important matters in the mix design. The process to select mortar mix design of the low diffusion layer is explained in detail. Of 33 kinds mix proportions used in laboratory comparative testing, the combinations of low heat portland cement, fly ash, lime powder and expansive addition was provisionally set to the mix proportion of the self-compacting mortar used for low diffusion layer. (author)

  18. The International Atomic Energy Agency (IAEA) research program to improve safety assessment methodologies for near-surface radioactive waste disposal facilities (ISAM)

    International Nuclear Information System (INIS)

    Torres-Vidal, C.; Kozak, M.W.

    2000-01-01

    The International Atomic Energy Agency (IAEA) launched a Coordinated Research Program in November 1997 on Improvement of Safety Assessment Methodologies for Near Surface Radioactive Waste Disposal Facilities (ISAM). The purpose of this paper is to describe the program and its goals, and to describe achievements of the program to date. The main objectives of the ISAM program are outlined. The primary focus of ISAM is on the practical application of safety assessment methodologies. Three kinds of practical situations are being addressed in the program: safety assessments for large vaults typical of those in Western Europe and North America, smaller vaults for medium and industrial wastes typical in eastern Europe and the former Soviet Union, and a proposed borehole technology for disposal of spent sources in low-technology conditions. (author)

  19. Environmental radioactivity

    International Nuclear Information System (INIS)

    1985-01-01

    Outline summary of a report prepared under contract to the DOE: Research Priorities and UK Estuaries: An Overview identifying Research Requirements. Topics considered include the study of radionuclides released into the NE Irish Sea from BNFL, Sellafields, differences in the isotopic composition of stable lead in various sediments, the concentration and distribution of 'hot particles' derived from BNFL in the Irish Sea and adjacent areas, together with attempts to separate hot particles from sediments, and the composition and properties of marine surfaces in relation to uptake and loss of radionuclides, particularly in relation to the common mussel, Mytilus edulis. The problem of the presence of transuranic radionuclides in the bottom sediments of the NE Irish Sea is considered. Profiles of radioactivity are being developed at the shelf-break in order to determine the transfer of radionuclides from the sea surface to the deep sea and to coastal waters; organisms examined include phytoplankton, zooplankton and crustacea (shrimps). Organisms such as Acantharia have been examined to determine transfer of elements and radionuclides to skeletal structures eg Sr, Ba and Si. (U.K.)

  20. Stochastic and deterministic models to evaluate the critical distance of a near surface repository for the disposal of intermediate and low level radioactive wastes

    Energy Technology Data Exchange (ETDEWEB)

    Alves, A.S.M., E-mail: asergi@eletronuclear.gov.br [Eletrobrás Termonuclear – Eletronuclear S.A. , Rua da Candelária 65, 7° andar, GSN.T, 20091-906 Rio de Janeiro, RJ (Brazil); Melo, P.F. Frutuoso e, E-mail: frutuoso@nuclear.ufrj.br [Graduate Program of Nuclear Engineering, COPPE, Federal University of Rio de Janeiro, Av. Horácio Macedo 2030, Bloco G, sala 206, 21941-914 Rio de Janeiro, RJ (Brazil); Passos, E.M., E-mail: epassos@eletronuclear.gov.br [Eletrobrás Termonuclear – Eletronuclear S.A. , Rua da Candelária 65, 7° andar, GSN.T, 20091-906 Rio de Janeiro, RJ (Brazil); Fontes, G.S., E-mail: gsfontes@hotmail.com [Instituto Militar de Engenharia – IME, Praça General Tibúrcio 80, 22290-270 Rio de Janeiro, RJ (Brazil)

    2015-06-15

    Highlights: • The water infiltration scenario is evaluated for a near surface repository. • The main objective is the determination of the critical distance of the repository. • The column liquid height in the repository is governed by an Ito stochastic equation. • Practical results are obtained for the Abadia de Goiás repository in Brazil. - Abstract: The aim of this paper is to present the stochastic and deterministic models developed for the evaluation of the critical distance of a near surface repository for the disposal of intermediate (ILW) and low level (LLW) radioactive wastes. The critical distance of a repository is defined as the distance between the repository and a well in which the water activity concentration is able to cause a radiological dose to a member of the public equal to the dose limit set by the regulatory body. The mathematical models are developed based on the Richards equation for the liquid flow in the porous media and on the solute transport equation in this medium. The release of radioactive material from the repository to the environment is considered through its base and its flow is determined by Darcy's Law. The deterministic model is obtained from the stochastic approach by neglecting the influence of the Gaussian white noise on the rainfall and the equations are solved analytically with the help of conventional calculus (non-stochastic calculus). The equations of the stochastic model are solved analytically based on the Ito stochastic calculus and numerically by using the Euler–Maruyama method. The impact on the value of the critical distance of the Abadia de Goiás repository is analyzed, taken as a study case, when the deterministic methodology is replaced by the stochastic one, considered more appropriate for modeling rainfall as a stochastic process.

  1. Basic approaches to the limitation of doses and radiological risks from surface disposal of long-lived radioactive waste for future generations

    International Nuclear Information System (INIS)

    Likhtarev, I.; Kovgan, L.; Berkovskiy, V.

    2001-01-01

    National radiation standards of Ukraine (NRSU-97/D-2000) recently put into force, which consider the basic principles of radiological protection from the sources of potential exposure, introduce four groups of potential exposure sources depending on types and scope of the consequences of occurrence of different critical events. In the third group are those occurrence which are associated with the events that can take place in the future (including the distant future) at the exempted from regulation facilities as a result of natural abnormal processes and catastrophes as well as inadvertent human intrusions. Future generations living at the moment of the event occurrence can become the subject of exposure. These sources must be taken into account at the stage of radioactive waste repositories designing. Taking into account the peculiarity of sources of the third group of potential, that they are associated with those critical events, which can take place in the distant future (in hundreds and thousands of years) and as a consequence may result in the exposure of future generations of people NRSU-97/D2000 sets an additional principle for potential exposure from sources of third group which requires that the future generations are guaranteed to have at least the same level of radiation protection against actions undertaken nowadays as the present generation. This principle is implemented through setting a requirement that harm for human health of future generation must not exceed the harm corresponding to negligible risk which is 5 x 10 -7 year -1 . NRSU-97/D-2000 establishes two reference dose levels A and B (50 and 1 mSv year -1 ) depending on which the acceptability of surface (or near-surface) disposals of long-lived radioactive waste is determined. In presentation the requirements on the critical events occurrence probability, two groups of scenario, which can lead to the critical event, and five reference scenarios of exposure and their parameters are discussed

  2. Comparative evaluations of surface contamination detectors calibration with radioactive sources - used in the Goiania accident, and standard sources

    International Nuclear Information System (INIS)

    Becker, P.H.B.; Marecha, M.H.H.

    1997-01-01

    The construction of Cs-137 standard flat sources for calibration of surface contamination detectors, used in the Goiania accident in 1987, is described and the procedures adopted are reported. At that time, standard sources were not available. Nowadays the Instituto de Radioprotecao e Dosimetria has standard sources acquired from Amersham which are used as calibration standards for surface contamination detectors. Comparative evaluations between the standard flat sources constructed for the accident and the calibrated ones are presented

  3. Environmental radioactivity monitoring in Republic of Serbia

    International Nuclear Information System (INIS)

    Joksic, J.; Radenkovic, M.; Tanaskovic, I.; Vujovic, M.; Vuletic

    2011-01-01

    According to environmental radioactivity monitoring programme continuous measurements of radioactivity in different samples are performed. Measurements are performed in aerosol samples, fallout, soil, surface waters, drinking water, food of animal and plant origin, milk and feeding stuffs. [sr

  4. History and environmental setting of LASL near-surface land disposal facilities for radioactive wastes (Areas A, B, C, D, E, F, G, and T). A source document

    International Nuclear Information System (INIS)

    Rogers, M.A.

    1977-06-01

    The Los Alamos Scientific Laboratory (LASL) has been disposing of radioactive wastes since 1944. The LASL Materials Disposal Areas examined in this report, Areas A, B, C, D, E, F, G, and T, are solid radioactive disposal areas with the exception of Area T which is a part of the liquid radioactive waste disposal operation. Areas A, G, and T are currently active. Environmental studies of and monitoring for radioactive contamination have been done at LASL since 1944

  5. History and environmental setting of LASL near-surface land disposal facilities for radioactive wastes (Areas A, B, C, D, E, F, G, and T). A source document

    Energy Technology Data Exchange (ETDEWEB)

    Rogers, M.A.

    1977-06-01

    The Los Alamos Scientific Laboratory (LASL) has been disposing of radioactive wastes since 1944. The LASL Materials Disposal Areas examined in this report, Areas A, B, C, D, E, F, G, and T, are solid radioactive disposal areas with the exception of Area T which is a part of the liquid radioactive waste disposal operation. Areas A, G, and T are currently active. Environmental studies of and monitoring for radioactive contamination have been done at LASL since 1944.

  6. Dynamics of radioactive waste generation

    International Nuclear Information System (INIS)

    Dogaru, Daniela; Virtopeanu, Cornelia; Ivan, Alexandrina

    2008-01-01

    In Romania there are in operation three facilities licensed for collection, treatment and storage of radioactive waste resulted from industry, research, medicine, and agriculture, named institutional radioactive waste. The repository, which is of near surface type, is designed for disposing institutional radioactive waste. The institutional radioactive wastes generated are allowed to be disposed into repository according to the waste acceptance criteria, defined for the disposal facility. The radioactive wastes which are not allowed for disposal are stored on the site of each facility which is special authorised for this. The paper describes the dynamics of generation of institutional waste in Romania, both for radioactive waste which are allowed to be disposed into repository and for radioactive waste which are not allowed to be disposed of. (authors)

  7. Une masse palpébrale révélant une fistule carotidocaverneuse ...

    African Journals Online (AJOL)

    ... huit mois une masse palpébrale droite, avec une discrète exophtalmie et hémorragie sous conjonctivale, l'angio IRM a permis de confirmer le diagnostique d'une fistule carotidocaverneuse à haut débit, qui est responsable de cette symptomatologie. L'objectif de cet article est de mettre la lumière sur cette pathologie rare, ...

  8. ASAM - The international programme on application of safety assessment methodologies for near surface radioactive waste disposal facilities

    International Nuclear Information System (INIS)

    Batandjieva, B.

    2002-01-01

    The IAEA has launched a new Co-ordinated Research Project (CRP) on Application of Safety Assessment Methodologies for Near Surface Waste Disposal Facilities (ASAM). The CRP will focus on the practical application of the safety assessment methodology, developed under the ISAM programme, for different purposes, such as developing design concepts, licensing, upgrading existing repositories, reassessment of operating disposal facilities. The overall aim of the programme is to assist safety assessors, regulators and other specialists involved in the development and review of safety assessment for near surface disposal facilities in order to achieve transparent, traceable and defendable evaluation of safety of these facilities. (author)

  9. New radioactivities

    International Nuclear Information System (INIS)

    Greiner, W.; Sandulescu, A.

    1996-01-01

    Some atomic nuclei reorganize their structure by ejection of big protons and neutrons aggregates. The observation of these new radioactivities specifies the theories of the nuclear dynamics. (authors)

  10. Radioactive materials

    International Nuclear Information System (INIS)

    Sugiura, Yoshio; Shimizu, Makoto.

    1975-01-01

    The problems of radioactivity in the ocean with marine life are various. Activities in this field, especially the measurements of the radioactivity in sea water and marine life are described. The works first started in Japan concerning nuclear weapon tests. Then the port call to Japan by U.S. nuclear-powered naval ships began. On the other hand, nuclear power generation is advancing with its discharge of warm water. The radioactive pollution of sea water, and hence the contamination of marine life are now major problems. Surveys of the sea areas concerned and study of the radioactivity intake by fishes and others are carried out extensively in Japan. (Mori, K.)

  11. Radioactivity Handbook

    International Nuclear Information System (INIS)

    Firestone, R.B.; Browne, E.

    1985-01-01

    The Radioactivity Handbook will be published in 1985. This handbook is intended primarily for applied users of nuclear data. It will contain recommended radiation data for all radioactive isotopes. Pages from the Radioactivity Handbook for A = 221 are shown as examples. These have been produced from the LBL Isotopes Project extended ENDSF data-base. The skeleton schemes have been manually updated from the Table of Isotopes and the tabular data are prepared using UNIX with a phototypesetter. Some of the features of the Radioactivity Handbook are discussed here

  12. Alkaline Plume in the Aptian Sand Aquifer in the Context of Low-Level Radioactive Waste Surface Disposal

    Science.gov (United States)

    Cochepin, B.; Munier, I.; MADE, B.

    2017-12-01

    The storage vaults for low and intermediate-level short-lived radioactive waste in the East of France are settled on the Aptian sand layer. In the context of the periodic examination by the nuclear regulators, it has been recommended to assess more precisely the chemical conditions for a potential release of radionuclides in the underlying water table. In particular, this study aims at assessing the eventuality of spreading an alkaline plume in the Aptian sand pore water by the chemical degradation of the vault cementitious materials. The numerical approach developed for this purpose is supported by both experimental characterizations of tracers in the water table and results from preliminary numerical studies on the hydrology of the site and the hydraulic evolution of the storage. The results from these specific simulations were simplified in the reactive transport model to focus on the mechanistic description of the chemical processes taking place in the waste and vaults and on their consequences on the underlying water table. During the operating period of the disposal, the reactive transport modelling shows that the low water saturation in the vaults material and in the vadose zone prevents the aquifer from a significant increase of the water pH under the cement-based vaults. These results are in reasonable agreement with the pH regularly measured in the underlying water table. After storage closure, during the few hundred years of the monitoring period and furthermore beyond, the reactive transport modelling shows a noticeable release of hydroxyls and alkali ions under the disposal vaults and their spread downstream the storage site leading to pH values above 10. It is noteworthy that the pH is not buffered in the Aptian sands because of their low amount in clayey minerals. This effect is now considered for pH-sensitive radionuclide solutes in safety assessment calculations by weighting correspondingly their retention parameters.

  13. The Technological Consolidation of UNED in Spain

    Directory of Open Access Journals (Sweden)

    Lorenzo Garcia Aretio

    2001-07-01

    Full Text Available This article discusses the role of the technologies that have been utilized to advance distance teaching and learning by the National Distance Education University (Universidad Nacional de Educación a Distancia – UNED of Spain. Following a description of UNED's historical development and organizational structure, UNED's experience with various educational media is discussed. Printed teaching materials, in the form of didactic units, were one of the first methods to be utilized when UNED began its operations in 1972. In turn, the role of radio and audio recordings, television and video recordings, telephone, videoconferencing, computer systems and computer-mediated communications are also described. UNED's pioneering projects, including the virtual classroom, virtual campus, and a program for the physically handicapped, are also detailed. Recent experiments include providing access to radio and television programs on the Internet and adoption of WebCT. On the horizon for UNED are portals for cellular phones using WAP technology and gearing up for multiple applications in accordance with Universal Mobile Telecommunications Technology (UMTS.

  14. The IRSN publishes an assessment of doses received in Japan by external irradiation due to radioactive deposits caused by the Fukushima-Daiichi power plant accident; L'IRSN publie une estimation des doses recues au Japon par irradiation externe due aux depots radioactifs provoques par l'accident de la centrale de Fukushima-Daiichi

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This document first describes how dry and wet radioactive deposits are formed. It also indicates their main components: iodine 131 and 132, caesium 134, 136 and 137, tellurium 132, and barium 140. It describes the different exposure ways due to radioactive deposits in the environment. A map indicates dose level assessments few tens of kilometres around the Fukushima power plant. A brief comment of this map is proposed

  15. Radioactivity. Centenary of radioactivity discovery

    International Nuclear Information System (INIS)

    Charpak, G.; Tubiana, M.; Bimbot, R.

    1997-01-01

    This small booklet was edited for the occasion of the exhibitions of the celebration of the centenary of radioactivity discovery which took place in various locations in France from 1996 to 1998. It recalls some basic knowledge concerning radioactivity and its applications: history of discovery, atoms and isotopes, radiations, measurement of ionizing radiations, natural and artificial radioactivity, isotope dating and labelling, radiotherapy, nuclear power and reactors, fission and fusion, nuclear wastes, dosimetry, effects and radioprotection. (J.S.)

  16. A comparative study of the pore structures and surfaces of hardened cement pastes of potential use in radioactive waste repositories

    International Nuclear Information System (INIS)

    Rowan, S.M.; Donaldson, L.; White, S.

    1988-02-01

    Measurements of water vapour adsorption at 20 0 C and mercury intrusion have been used to compare the surfaces and pore structures of hardened cement pastes made from ordinary portland cement (OPC) and the additives blast furnace slag (BFS) and pulverised fuel ash (PFA). The results suggest that each additive, after taking part in the hydration reaction with OPC, produces a paste whose gel pore structure is similar to that derived from OPC alone. The BET adsorption surface area of the cement pastes, in the form of half inch diameter coupons was ca. 55 m 2 g -1 and was not influenced by the presence of the additives. However the pastes containing the additives have a larger and better interconnected meso and macropore structure than OPC which may account for larger diffusion coefficients reported elsewhere for caesium ions passing through concrete containing BFS in comparison with a concrete containing OPC alone. (author)

  17. Development of surface decontamination technology for radioactive waste using plasma. Dust behaviors in the treatment of oxide films using a low-pressure arc

    International Nuclear Information System (INIS)

    Adachi, Kazuo; Furukawa, Shizue; Amakawa, Tadashi; Fujiwara, Kazutoshi; Kanbe, Hiromu

    2002-01-01

    We are developing the surface treatment technique using low-pressure arc as a new decontamination technology for radioactive wastes from nuclear facilities. For the practical use, effective dust collection methods are necessary, because dust is generated from oxide films on the surface during the treatment. The method using gas stream and filters may be one of them, but the behavior of the dust has not been examined yet. We studied the basic behavior of the dust and the possibilities of dust control by gas stream as follows. 1. Most of the dust attached to the anode in the case of no gas blow. 2. Dust attachment to the anode was reduced to about half using small cross section type anode. It seems to be possible to reduce the dust attachment by proper choice of electrode shape. 3. The dust attachment was reduced to 10 to 40 percent by the gas blow to the side of arc. The dust control by gas stream might be possible. (author)

  18. Brief draft on surface and subsurface storage of high level and long-lived radioactive wastes. Spent fuels synthesis file

    International Nuclear Information System (INIS)

    Dumas, C.; Jaecki, P.

    2002-01-01

    This document makes a synthesis of the results of two brief draft studies performed in 2002 about the surface and subsurface storage of spent fuels. These studies stress on the long duration aspect of the disposal: feasibility of a secular disposal facility, potential risks and safety level of such a facility, estimation of the initial investment and of operation and maintenance costs. The main points of the specifications and the input data are presented first, and then the subsurface and surface draft studies are described. Content: specifications (imposed design principles and options, dry corrosion, input data); subsurface storage (description and design options, thermal dimensioning and ventilation, geotechnical stability of the facility, subsurface water management, dry corrosion, infrastructure durability, safety, monitoring, security and physical protection, technical-economical aspects, case of Mox fuel, case of glass packages); surface storage (description and design options, thermal dimensioning and ventilation, mechanical dimensioning of the facility, dry corrosion, infrastructure durability, safety, monitoring, security and physical protection, technical-economical aspects, case of Mox fuel, case of glass packages); conclusions and perspectives. (J.S.)

  19. Radioactive isotopes on the Moon

    International Nuclear Information System (INIS)

    Davis, R. Jr.

    1975-01-01

    A limited review of experiments and studies of radioactivity and isotope ratios in lunar materials is given. Observations made on the first few millimeters of the surface where the effects of solar flare particles are important, some measurements on individual rocks, and some studies of radioactivities produced deep in the lunar soil by galactic cosmic rays, are among the experiments discussed

  20. A reliability study on influence of the geosphere thickness over the activity release from a near surface radioactive waste repository

    Energy Technology Data Exchange (ETDEWEB)

    Aguiar, Lais Alencar de, E-mail: laguiar@cnen.gov.br [Comissao Nacional de Energia Nuclear (CNEN-RJ), Rio de Janeiro, RJ (Brazil); Damaso, Vinicius Correa, E-mail: vcdamaso@gmail.com [Estado-Maior do Exercito (EME/EB), Brasilia, DF (Brazil)

    2013-07-01

    Infiltration of water into a waste disposal facility and into the waste region is the main factor inducing the release of radionuclides from a disposal facility. Since infiltrating water flow is dependent on the natural percolation at the site and the performance of engineered barriers, its prediction requires modelling of unsaturated water flow through intact or partially/completely failed components of engineered barriers and through the rock layer of the geosphere on which the repository is constructed. The engineered barriers include the cover systems, concrete vault, backfill, waste forms, and overpacks. This paper aims to carry out a performance study regarding a near surface repository in terms of reliability engineering. It is assumed that surface water infiltrates through the barriers reaching the matrix where radionuclides are contained, thus releasing them into the environment. The repository consists of a set of barriers which are considered saturated porous medium. As results, this paper presents the relation between the thickness of the geosphere layer and the radionuclide release rate in terms of activity. Such results represent a useful information for choosing the repository sites in order to keep the released activity in acceptable levels over time. (author)

  1. Radioactivity in the Exclusive Economic Zone of east coast Peninsular Malaysia. Distribution trends of 137Cs in surface seawater

    International Nuclear Information System (INIS)

    Zaharudin Ahmad; Zal U'yun Wan Mahmood; Hidayah Shahar; Mei Wo Yii; Ahmad Sanadi Abu Bakar

    2011-01-01

    Large volumes of surface seawater samples were collected from thirty locations in the Exclusive Economic Zone (EEZ) of the east coast Peninsular Malaysia on June 2008 to study the activity concentrations of 137 Cs. The results will serve as additional information to the existing baseline data and is very useful for monitoring fresh input of anthropogenic radionuclide into Malaysian marine environment. In this study, the activity concentrations of 137 Cs were determined using co-precipitation technique, followed by Gamma Spectrometry measurement. The mean activity concentration of 137 Cs ranged between 3.40 and 5.89 Bq/m 3 . Higher activity concentrations were observed at the coastal and towards the south of Peninsular Malaysia and were aligned with the high turbidity. These may due to the rapid diffusion of 137 Cs from suspended particulates and fine sediments into surface seawater. The activity concentrations of 137 Cs observed in this study were slightly higher than the concentrations reported in seawater at the Straits of Malacca, Vietnam and Philippines. This might be because the study area received more input of 137 Cs that originated from global fallout and then deposited on land which later being transported subsequently into the coastal zone due to siltation and erosion processes. It could also be attributed to the intrusion of river waters containing higher concentrations of 137 Cs. (author)

  2. A reliability study on influence of the geosphere thickness over the activity release from a near surface radioactive waste repository

    International Nuclear Information System (INIS)

    Aguiar, Lais Alencar de; Damaso, Vinicius Correa

    2013-01-01

    Infiltration of water into a waste disposal facility and into the waste region is the main factor inducing the release of radionuclides from a disposal facility. Since infiltrating water flow is dependent on the natural percolation at the site and the performance of engineered barriers, its prediction requires modelling of unsaturated water flow through intact or partially/completely failed components of engineered barriers and through the rock layer of the geosphere on which the repository is constructed. The engineered barriers include the cover systems, concrete vault, backfill, waste forms, and overpacks. This paper aims to carry out a performance study regarding a near surface repository in terms of reliability engineering. It is assumed that surface water infiltrates through the barriers reaching the matrix where radionuclides are contained, thus releasing them into the environment. The repository consists of a set of barriers which are considered saturated porous medium. As results, this paper presents the relation between the thickness of the geosphere layer and the radionuclide release rate in terms of activity. Such results represent a useful information for choosing the repository sites in order to keep the released activity in acceptable levels over time. (author)

  3. Storage of radioactive waste

    International Nuclear Information System (INIS)

    Pittman, F.K.

    1974-01-01

    Four methods for managing radioactive waste in order to protect man from its potential hazards include: transmutation to convert radioisotopes in waste to stable isotopes; disposal in space; geological disposal; and surface storage in shielded, cooled, and monitored containers. A comparison of these methods shows geologic disposal in stable formations beneath landmasses appears to be the most feasible with today's technology. (U.S.)

  4. Performance assessment and licensing issues for United States commercial near-surface low-level radioactive waste disposal facilities

    International Nuclear Information System (INIS)

    Birk, S.M.

    1997-10-01

    The final objective of performance assessment for a near-surface LLW disposal facility is to demonstrate that potential radiological impacts for each of the human exposure pathways will not violate applicable standards. This involves determining potential pathways and specific receptor locations for human exposure to radionuclides; developing appropriate scenarios for each of the institutional phases of a disposal facility; and maintaining quality assurance and control of all data, computer codes, and documentation. The results of a performance assessment should be used to demonstrate that the expected impacts are expected to be less than the applicable standards. The results should not be used to try to predict the actual impact. This is an important distinction that results from the uncertainties inherent in performance assessment calculations. The paper discusses performance objectives; performance assessment phases; scenario selection; mathematical modeling and computer programs; final results of performance assessments submitted for license application; institutional control period; licensing issues; and related research and development activities

  5. Radioactivity concentrations and dose assessment in surface soil samples from east and south of Marmara region, Turkey.

    Science.gov (United States)

    Kiliç, Onder; Belivermis, Murat; Topçuoğlu, Sayhan; Cotuk, Yavuz; Coşkun, Mahmut; Cayir, Akin; Küçer, Rahmi

    2008-01-01

    The activity concentrations of 137Cs, 40K, 232Th, 238U and 226Ra were measured in surface soil samples from East and South of Marmara region, Turkey. The physico-chemical parameters (organic matter, CaCO3 contents and pH-value) of the soil samples were determined in the samples collected from 100 sampling stations. The average activity concentrations of 137Cs, 40K, 232Th, 238U and 226Ra were found to be 27.46+/-21.84, 442.51+/-189.85, 26.63+/-15.90, 21.77+/-12.08 and 22.45+/-13.31 Bq kg(-1), respectively. The mean value of total annual external gamma radiation dose equivalent for the natural radionuclides was calculated to be 54.86 microSv. The current data were compared with those found in the other locations of Turkey and different countries.

  6. Radioactive substance solidifying device

    International Nuclear Information System (INIS)

    Sakoda, Kotaro.

    1979-01-01

    Purpose: To easily solidify radioactive substances adhering to the surfaces of solid wastes without scattering in the circumference by paints, and further to reduce surface contamination concentrations. Constitution: Solid wastes are placed on a hanging plate, and dipped in paints within a paint dipping treatment tank installed at the lower part of a treatment tank by means of a monorail hoist, and the surfaces of said solid wastes are coated with paints, thereby to solidify the radioactivity on the surfaces of the solid wastes. After dipping, the solid wastes are suspended up to a paint spraying tank to dry the paints. After drying, non-contaminated paints are atomized to apply through an atomizing tube onto the solid wastes. After drying the atomized paints, the solid wastes are carried outside the treatment tank by means of the monorail hoist. (Yoshino, Y.)

  7. Noble Gas Surface Flux Simulations And Atmospheric Transport

    Energy Technology Data Exchange (ETDEWEB)

    Carrigan, Charles R. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Sun, Yunwei [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Simpson, Matthew D. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2017-09-30

    Signatures from underground nuclear explosions or UNEs are strongly influenced by the containment regime surrounding them. The degree of gas leakage from the detonation cavity to the surface obviously affects the magnitude of surface fluxes of radioxenon that might be detected during the course of a Comprehensive Test Ban Treaty On-Site Inspection. In turn, the magnitude of surface fluxes will influence the downwind detectability of the radioxenon atmospheric signature from the event. Less obvious is the influence that leakage rates have on the evolution of radioxenon isotopes in the cavity or the downwind radioisotopic measurements that might be made. The objective of this letter report is to summarize our attempt to better understand how containment conditions affect both the detection and interpretation of radioxenon signatures obtained from sampling at the ground surface near an event as well as at greater distances in the atmosphere. In the discussion that follows, we make no attempt to consider other sources of radioactive noble gases such as natural backgrounds or atmospheric contamination and, for simplicity, only focus on detonation-produced radioxenon gases. Summarizing our simulations, they show that the decay of radioxenon isotopes (e.g., Xe-133, Xe-131m, Xe-133m and Xe-135) and their migration to the surface following a UNE means that the possibility of detecting these gases exists within a window of opportunity. In some cases, seeps or venting of detonation gases may allow significant quantities to reach the surface and be released into the atmosphere immediately following a UNE. In other release scenarios – the ones we consider here – hours to days may be required for gases to reach the surface at detectable levels. These release models are most likely more characteristic of “fully contained” events that lack prompt venting, but which still leak gas slowly across the surface for periods of months.

  8. Batch versus column modes for the adsorption of radioactive metal onto rice husk waste: conditions optimization through response surface methodology.

    Science.gov (United States)

    Kausar, Abida; Bhatti, Haq Nawaz; Iqbal, Munawar; Ashraf, Aisha

    2017-09-01

    Batch and column adsorption modes were compared for the adsorption of U(VI) ions using rice husk waste biomass (RHWB). Response surface methodology was employed for the optimization of process variables, i.e., (pH (A), adsorbent dose (B), initial ion concentration (C)) in batch mode. The B, C and C 2 affected the U(VI) adsorption significantly in batch mode. The developed quadratic model was found to be validated on the basis of regression coefficient as well as analysis of variance. The predicted and actual values were found to be correlated well, with negligible residual value, and B, C and C 2 were significant terms. The column study was performed considering bed height, flow rate and initial metal ion concentration, and adsorption efficiency was evaluated through breakthrough curves and bed depth service time and Thomas models. Adsorption was found to be dependent on bed height and initial U(VI) ion concentration, and flow rate decreased the adsorption capacity. Thomas models fitted well to the U(VI) adsorption onto RHWB. Results revealed that RHWB has potential to remove U(VI) ions and batch adsorption was found to be efficient versus column mode.

  9. Features, events, processes, and safety factor analysis applied to a near-surface low-level radioactive waste disposal facility

    Energy Technology Data Exchange (ETDEWEB)

    Stephens, M.E.; Dolinar, G.M.; Lange, B.A. [Atomic Energy of Canada Limited, Ontario (Canada)] [and others

    1995-12-31

    An analysis of features, events, processes (FEPs) and other safety factors was applied to AECL`s proposed IRUS (Intrusion Resistant Underground Structure) near-surface LLRW disposal facility. The FEP analysis process which had been developed for and applied to high-level and transuranic disposal concepts was adapted for application to a low-level facility for which significant efforts in developing a safety case had already been made. The starting point for this process was a series of meetings of the project team to identify and briefly describe FEPs or safety factors which they thought should be considered. At this early stage participants were specifically asked not to screen ideas. This initial list was supplemented by selecting FEPs documented in other programs and comments received from an initial regulatory review. The entire list was then sorted by topic and common issues were grouped, and issues were classified in three priority categories and assigned to individuals for resolution. In this paper, the issue identification and resolution process will be described, from the initial description of an issue to its resolution and inclusion in the various levels of the safety case documentation.

  10. Radioactivity and radioprotection: the every day life in a nuclear installation. Press tour at CEA/GRENOBLE 18 november 1999; Radioactivite et radioprotection: la vie quotidienne dans une installation nucleaire. Voyage de presse au Centre CEA/CADARACHE 18 novembre 1999

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-11-01

    In the framework of the public information, this paper gives a general information on the radioactivity and the radioprotection at the CEA/Cadarache center. A first part is devoted to a presentation of the radioactivity with definitions and radiation effects on the human being and the environment. An other part presents the radioprotection activities and regulations. The last part deals with specific activities of the CEA/Cadarache: the CASCAD installations for spent fuels storage, the LECA Laboratory for the Examination of Active Fuels and a dismantling installation for big irradiated objects. Historical aspects of the CEA/Cadarache are also provided. (A.L.B.)

  11. Safety assessment of near surface radioactive waste disposal facilities: Model intercomparison using simple hypothetical data (Test Case 1). First report of NSARS. Part of the co-ordinated research programme on the safety assessment of near surface radioactive waste disposal facilities (NSARS)

    International Nuclear Information System (INIS)

    1995-11-01

    In many countries near surface disposal is the preferred option for the comparatively large volumes of low and intermediate level wastes which arise during nuclear power plant operations, nuclear fuel reprocessing and also for the wastes arising from radionuclide applications in hospitals and research establishments. Near surface disposal is also widely practised in the case of hazardous wastes from chemical industries. It is obviously necessary to show that waste disposal methods are safe and that both man and the environment will be adequately protected. Following a previous related Co-ordinated Research Programme (CRP) on ''Migration and Biological Transfer of Radionuclides from Shallow Land Burial'' during 1985 to 1989 (IAEA-TECDOC-579, Vienna, 1990), the issue of reliability of safety assessments was identified as an important topic for further support and development. A new CRP was formulated with the acronym NSARS (Near Surface Radioactive Waste Disposal Safety Assessment Reliability Study). This technical document is the first report of from the CRP and contains the intercomparison of results of the first test exercise (Test Case 1) on modelling of potential radiation exposures as a result of near surface disposal. Test Case 1 is based on entirely hypothetical data and includes consideration of exposures due to leaching and as a result of human intrusion into the site. Refs, figs and tabs

  12. Safety assessment of near surface radioactive waste disposal facilities: Model intercomparison using simple hypothetical data (Test Case 1). First report of NSARS. Part of the co-ordinated research programme on the safety assessment of near surface radioactive waste disposal facilities (NSARS)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-11-01

    In many countries near surface disposal is the preferred option for the comparatively large volumes of low and intermediate level wastes which arise during nuclear power plant operations, nuclear fuel reprocessing and also for the wastes arising from radionuclide applications in hospitals and research establishments. Near surface disposal is also widely practised in the case of hazardous wastes from chemical industries. It is obviously necessary to show that waste disposal methods are safe and that both man and the environment will be adequately protected. Following a previous related Co-ordinated Research Programme (CRP) on ``Migration and Biological Transfer of Radionuclides from Shallow Land Burial`` during 1985 to 1989 (IAEA-TECDOC-579, Vienna, 1990), the issue of reliability of safety assessments was identified as an important topic for further support and development. A new CRP was formulated with the acronym NSARS (Near Surface Radioactive Waste Disposal Safety Assessment Reliability Study). This technical document is the first report of from the CRP and contains the intercomparison of results of the first test exercise (Test Case 1) on modelling of potential radiation exposures as a result of near surface disposal. Test Case 1 is based on entirely hypothetical data and includes consideration of exposures due to leaching and as a result of human intrusion into the site. Refs, figs and tabs.

  13. Simulated Radioactivity

    Science.gov (United States)

    Boettler, James L.

    1972-01-01

    Describes the errors in the sugar-cube experiment related to radioactivity as described in Project Physics course. The discussion considers some of the steps overlooked in the experiment and generalizes the theory beyond the sugar-cube stage. (PS)

  14. Concentrating Radioactivity

    Science.gov (United States)

    Herrmann, Richard A.

    1974-01-01

    By concentrating radioactivity contained on luminous dials, a teacher can make a high reading source for classroom experiments on radiation. The preparation of the source and its uses are described. (DT)

  15. Radioactive wastes

    International Nuclear Information System (INIS)

    Grass, F.

    1982-01-01

    Following a definition of the term 'radioactive waste', including a discussion of possible criteria allowing a delimitation of low-level radioactive against inactive wastes, present techniques of handling high-level, intermediate-level and low-level wastes are described. The factors relevant for the establishment of definitive disposals for high-level wastes are discussed in some detail. Finally, the waste management organization currently operative in Austria is described. (G.G.)

  16. Radioactive pollution

    International Nuclear Information System (INIS)

    Steiner, R.

    1987-01-01

    In the wake of the Chernobyl reactor accident on April 26, 1986, many individual values for radioactivity in the air, in foodstuffs and in the soil were measured and published. Prof. Dr. Rolf Steiner, Wiesbaden, the author of this paper, evaluated the host of data - mostly official pollution data -, drew conclusions regarding the radioactivity actually released at Chernobyl, and used the data to test the calculation model adotped by the Radiation Protection Ordinance. (orig./RB) [de

  17. La culture, une arme de constructions massives.

    Directory of Open Access Journals (Sweden)

    Patrick Poncet

    2008-06-01

    Full Text Available Le recueil de texte que nous propose Jean-Michel Tobelem autour des questions de « diplomatie culturelle » peut être considéré comme un objet à double sens : une source et une exploration. Comme recueil de documents, le directeur d’ouvrage s’est attaché à réunir dans un volume somme toute restreint des contributions de spécialistes de divers sujets « culturels » à qui il était demandé de livrer leur savoir sous un angle valorisant le lien entre diplomatie et culture. ...

  18. Radioactive substance removing device

    International Nuclear Information System (INIS)

    Takeuchi, Jun; Tayama, Ryuichi; Teruyama, Hidehiko; Hikichi, Takayoshi.

    1992-01-01

    If inert gases are jetted from a jetting device to liquid metals in a capturing vessel, the inert gases are impinged on the inner wall surface of the capturing vessel, to reduce the thickness of a boundary layer as a diffusion region of radioactive materials formed between the inner wall surface of the capturing vessel and the liquid metals. Further, a portion of the boundary layer is peeled off to increase the adsorption amount of radioactive materials by the capturing vessel. When the inert gases are jetted on the inner or outer circumference of the capturing vessel to rotate the capturing vessel, the flow of the liquid metals is formed along with the rotation, and the thickness of the boundary layer is reduced or the boundary layer is peeled off to increase the absorption amount of the radioactive materials. If gas bubbles are formed in the liquid metals by the inert gases, the liquid metals are stirred by the gas bubbles to reduce the thickness of the boundary layer or peel it off, thereby enabling to increase the adsorption amount of the radioactive materials. Since it is not necessary to pass through the rotational member to the wall surface of the vessel, safety and reliability can be improved. (N.H.)

  19. Non-radioactive stand-in for radioactive contamination. I. Non-radioactive tests

    International Nuclear Information System (INIS)

    Rohe, M.J.; Rankin, W.N.; Postles, R.L.

    1985-01-01

    Candidate non-radioactive materials for use as a stand-in for radioactive contamination during application of a high-pressure, hot water decontamination were identified and evaluated. A stand-in for radioactive contamination is needed to evaluate the decontaminability of replacement canyon cranes at the manufacturers location where actual radioactive contamination cannot be used. This evaluation was conducted using high-pressure, hot-water at 420 psi, 190 0 F, and 20 gal/min through a 1/8-in.-diam nozzle, the decontamination technique preferred by SRP Separations Department for this application. A non-radioactive stand-in for radioactive contamination was desired that would be removed by direct blast stream contact but would remain intact on surfaces where direct contact does not occur. This memorandum describes identification of candidate non-radioactive stand-in materials and evaluation of these materials in screening tests and tests with high-pressure, hot-water blasting. The following non-radioactive materials were tested: carpenter's line chalk; typing correction fluid; dye penetrant developer; latex paint with attapulyite added; unaltered latex paint; gold enamel; layout fluid; and black enamel. Results show that blue layout fluid and gold enamel have similar adherence that is within the range expected for actual radioactive contamination. White latex paint has less adherence than expected for actual radioactive contamination. The film was removed at a rate of 2 . Black enamel has more adherence than expected from actual radioactive contamination. In these tests ASTM No. 2B surfaces were harder to clean than either ASTM No. 1 or electropolished surfaces which had similar cleaning properties. A 90 0 blast angle was more effective than a 45 0 blast angle. In these tests there was no discernible effect of blast distance between 1 and 3 ft

  20. Radioactive nuclide adsorption

    International Nuclear Information System (INIS)

    Fukushima, Kimichika.

    1982-01-01

    Purpose: To improve the efficiency of a radioactive nuclide adsorption device by applying a nickel plating on a nickel plate to render the surface active. Constitution: A capturing device for radioactive nuclide such as manganese 54, cobalt 60, 58 and the like is disposed to the inside of a pipeway provided on the upper portion of fuel assemblies through which liquid sodium as the coolant for LMFBR type reactor is passed. The device comprises a cylindrical adsorption body and spacers. The adsorption body is made of nickel and applied with a nickel plating on the surface thereof. The surface of the adsorption body is unevened to result in disturbance in the coolant and thereby improve the adsorptive efficiency. (Kawakami, Y.)

  1. The ''invisible'' radioactive scale

    International Nuclear Information System (INIS)

    Bjoernstad, T.; Ramsoey, T.

    1999-04-01

    Production and up-concentration of naturally occurring radioactive material (NORM) in the petroleum industry has attracted steadily increasing attention during the last 15 years. Most production engineers today associate this radioactivity with precipitates (scales) and sludges in production tubing, pumps, valves, separators, settling tanks etc., wherever water is being transported or treated. 226 Ra and 228 Ra are the most well known radioactive constituents in scale. Surprisingly little known is the radioactive contamination by 210 Pb and progeny 210 Bi and 210 Po. These are found in combination with 226 Ra in ordinary scale, often in layer of non-radioactive metallic lead in water transportation systems, but also in pure gas and condensate handling systems ''unsupported'' by 226 Ra, but due to transportation and decay of the noble gas 222 Rn in NG/LNG. This latter contamination may be rather thin, in some cases virtually invisible. When, in addition, the radiation energies are low enough for not being detectable on the equipment outer surface, its existence has for most people in the industry been a secret. The report discusses transportation and deposition mechanisms, detection methods and provides some examples of measured results from the North Sea on equipment sent for maintenance. It is concluded that a regular measurement program for this type of contamination should be mandatory under all dismantling processes of transportation and fluid handling equipment for fluids and gases offshore and onshore

  2. Management on radioactive wastes

    International Nuclear Information System (INIS)

    Balu, K.; Bhatia, S.C.

    1979-01-01

    The basic philosophy governing the radioactive waste management activities in India is to concentrate and contain as much activity as possible and to discharge to the environment only such of these streams that have radioactive content much below the nationally and internationally accepted standards. The concept of ''Zero Release'' is also kept in view. At Tarapur, the effluents are discharged into coastal waters after the radioactivity of the effluents is brought down by a factor 100. The effluents fΩm Rajasthan reactors are discharged into a lake keeping their radioactivity well within permissible limits and a solar evaporation plant is being set up. The plant, when it becomes operational, will be a step towards the concept of ''Zero Release''. At Kalpakkam, the treated wastes are proposed to be diluted by circulating sea water and discharged away from the shore through a long pipe. At Narora, ion exchange followed by chemical precipitation is to be employed to treat effluents and solar evaporation process for total containment. Solid wastes are stored/dispsed in the concrete trenches, underground with the water proofing of external surfaces and the top of the trench is covered with concrete. Highly active wastes are stored/disposed in tile holes which are vaults made of steel-lined, reinforced concrete pipes. Gas cleaning, dilution and dispersion techniques are adopted to treat gaseous radioactive wastes. (M.G.B.)

  3. Le microdosage des engrais, une innovation qui profite aux femmes

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

    non seulement une diminution de leurs revenus, mais doivent aussi composer avec une pénurie chronique de céréales. Au Niger, par exemple, 2,5 millions de personnes ont eu besoin d'une aide alimentaire en 2005, par suite d'une grave sécheresse (PAM, 2010). Cette situation s'est reproduite en 2010, la mauvaise.

  4. La Moyenne Vallée de l’Euphrate syrien : étude préliminaire pour la cartographie des états de surface et des systèmes de drainage en vue d’une analyse paléoenvironnementale

    Directory of Open Access Journals (Sweden)

    Ch. Chataigner

    2000-05-01

    Full Text Available La moyenne vallée de l’Euphrate syrien constitue l’une des zones clé pour la diffusion du néolithique. Mais elle est aussi une zone d’intense mise en valeur sous forme d’aménagements hydrauliques. La télédétection peut jouer un rôle important comme image récente d’un paysage à disparaître, et comme document palliatif à la carence de certaines données pour une analyse paléoenvironnementale.

  5. Une-Mati lood vene keeles

    Index Scriptorium Estoniae

    2004-01-01

    Dagmar Normeti lasteraamatu "Une-Mati, Päris-Mati ja Tups" tõlget vene keelde (tõlkijad Irina Belobrovtseva ja Vitali Belobrovtsev; ill. Siima Shkop) esitletakse täna Kirjanike Liidu saalis; vt. ka Postimees, 19. märts, lk. 14

  6. Les faits,une arme contre

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

    un_focus_pauvreté. Aux Philippines, les progrès reposent sur une information rigoureuse. Aux Philippines, le système de suivi communautaire de la pauvreté, d'abord projet pilote, s'est étendu, en 14 ans, à l'échelle nationale, appuyé par tous les ordres ...

  7. Vers une vision surnaturelle de la folie

    Directory of Open Access Journals (Sweden)

    Mabel Franzone

    2006-12-01

    Full Text Available A partir de la difficile notion de "folie", il s’agit d’aller vers l’exclusion dont cette maladie a fait l’objet dans le système occidental moderne. Un autre traitement de la maladie mentale se fait jour avec des penseurs contemporains, la résurgence d’autres cosmovisions et de philosophies anciennes. Ainsi les délires mystique, paranoïaque, schizophrénique peuvent être étudiés d’une part comme des ruptures de limites, d’autre part comme une mise en relation du corps avec l’esprit. Entre les deux, le langage fait oeuvre de trait d’union, langage qui, chez les malades, dénote une créativité, la poésie. Si cette poésie permet une sortie, une explosion des limites de la réalité vers des régions inconnues, peut-être peut-on voir la folie comme un déséquilibre par rapport au monde, au cosmos même, déséquilibre qui peut être traité en responsabilisant l’homme, en le pensant, en le mettant en question. De ce point de vue, la folie ressort comme quelque chose de positif, comme l’un des thèmes qui nous repositionnera face au monde, en mettant à notre portée d’autres ontologies.

  8. Environmental radioactivity in Hungary

    International Nuclear Information System (INIS)

    Kovacs, J.; Predmerszky, T.

    1979-01-01

    A comprehensive examination of radioactive contamination in air, soil, surface waters and food products, and of natural radioactiviy in air, soil, and building materials has been carried out. The investigated factors were as follows: a) air samples: yearly and monthly beta- and gamma activities of fallout, precipitation and aerosols in the period 1955-1976 in Budapest and some other towns; b) soil samples: 90 Sr concentration of soils of different quality and cultivation originating from sixteen regions of Hungary measured in the period 1974-1976; c) surface waters: annual mean beta activity of five rivers and of the Lake Balaton in the period 1965-1976, 3 H, 137 Cs and 90 Sr activity of the Danube in the year 1976; d) food products: radioactive contamination of spinach, lettuce and oxalis, originating from three different regions in the period 1959-1976 and mean radioactivity of fodder, corn, tobacco, milk, fish and animal bones in a period of 5-10 years; e) natural radioactivity: radon- and toron concentration of air, activity of 226 Ra fallout of the soil in the vicinity of power plants, 226 Ra, 228 Th and 40 K activity of different building materials, radiation doses inside buildings constructed by different technics. (L.E.)

  9. Radioactive wastes

    International Nuclear Information System (INIS)

    Dupuis, M.C.

    2007-01-01

    Managing radioactive wastes used to be a peripheral activity for the French atomic energy commission (Cea). Over the past 40 years, it has become a full-fledged phase in the fuel cycle of producing electricity from the atom. In 2005, the national radioactive waste management agency (ANDRA) presented to the government a comprehensive overview of the results drawn from 15 years of research. This landmark report has received recognition beyond France's borders. By broadening this agency's powers, an act of 28 June 2006 acknowledges the progress made and the quality of the results. It also sets an objective for the coming years: work out solutions for managing all forms of radioactive wastes. The possibility of recovering wastes packages from the disposal site must be assured as it was asked by the government in 1998. The next step will be the official demand for the creation of a geological disposal site in 2016

  10. Impact assessment of ionizing radiation on human and non-human biota from the vicinity of a near-surface radioactive waste repository.

    Science.gov (United States)

    Nedveckaite, T; Gudelis, A; Vives i Batlle, J

    2013-05-01

    This work describes the radiological assessment of the near-surface Maisiagala radioactive waste repository (Lithuania) over the period 2005-2012, with focus on water pathways and special emphasis on tritium. The study includes an assessment of the effect of post-closure upgrading, the durability of which is greater than 30 years. Both human and terrestrial non-human biota are considered, with local low-intensity forestry and small farms being the area of concern. The radiological exposure was evaluated using the RESRAD-OFFSITE, RESRAD-BIOTA and ERICA codes in combination with long-term data from a dedicated environmental monitoring programme. All measurements were performed at the Lithuanian Institute of Physics as part of this project. It is determined that, after repository upgrading, radiological exposure to humans are significantly lower than the human dose constraint of 0.2 mSv/year valid in the Republic of Lithuania. Likewise, for non-human biota, dose rates are below the ERICA/PROTECT screening levels. The potential annual effective inhalation dose that could be incurred by the highest-exposed human individual (which is due to tritiated water vapour airborne release over the most exposed area) does not exceed 0.1 μSv. Tritium-labelled drinking water appears to be the main pathway for human impact, representing about 83 % of the exposure. Annual committed effective dose (CED) values for members of the public consuming birch sap as medical practice are calculated to be several orders of magnitude below the CEDs for the same location associated with drinking of well water. The data presented here indicate that upper soil-layer samples may not provide a good indication of potential exposure to terrestrial deep-rooted trees, as demonstrated by an investigation of stratified (3)H in soil moisture, expressed on a wet soil mass basis, in an area with subsurface contamination.

  11. Impact assessment of ionizing radiation on human and non-human biota from the vicinity of a near-surface radioactive waste repository

    Energy Technology Data Exchange (ETDEWEB)

    Nedveckaite, T.; Gudelis, A. [Institute of Physics, Center for Physical Sciences and Technology, Vilnius (Lithuania); Vives i Batlle, J. [Belgian Nuclear Research Centre SCK-CEN, Mol (Belgium)

    2013-05-15

    This work describes the radiological assessment of the near-surface Maisiagala radioactive waste repository (Lithuania) over the period 2005-2012, with focus on water pathways and special emphasis on tritium. The study includes an assessment of the effect of post-closure upgrading, the durability of which is greater than 30 years. Both human and terrestrial non-human biota are considered, with local low-intensity forestry and small farms being the area of concern. The radiological exposure was evaluated using the RESRAD-OFFSITE, RESRAD-BIOTA and ERICA codes in combination with long-term data from a dedicated environmental monitoring programme. All measurements were performed at the Lithuanian Institute of Physics as part of this project. It is determined that, after repository upgrading, radiological exposure to humans are significantly lower than the human dose constraint of 0.2 mSv/year valid in the Republic of Lithuania. Likewise, for non-human biota, dose rates are below the ERICA/PROTECT screening levels. The potential annual effective inhalation dose that could be incurred by the highest-exposed human individual (which is due to tritiated water vapour airborne release over the most exposed area) does not exceed 0.1 μSv. Tritium-labelled drinking water appears to be the main pathway for human impact, representing about 83 % of the exposure. Annual committed effective dose (CED) values for members of the public consuming birch sap as medical practice are calculated to be several orders of magnitude below the CEDs for the same location associated with drinking of well water. The data presented here indicate that upper soil-layer samples may not provide a good indication of potential exposure to terrestrial deep-rooted trees, as demonstrated by an investigation of stratified {sup 3}H in soil moisture, expressed on a wet soil mass basis, in an area with subsurface contamination. (orig.)

  12. Control of the surface radioactive contamination in the field of biological research; Control de la contaminacion radiactiva superficial en el ambito de la investigacion biologica

    Energy Technology Data Exchange (ETDEWEB)

    Calvo, S.; Encina, A. de la; Gaspar, J.; Macias, M. T.; Sanchez, A.; Usera, F.

    2012-11-01

    The manipulation of unsealed sources in biomedical research involves significant risk of radioactive contamination. the aim of this study has been to analyze the radioactive contamination occurring in the field of biomedical research, assessing its magnitude, identifying the equipment that can be contaminated with higher probability and monitoring the evolution of the contaminations production taking into account the radioisotopes and the activities uses, and the radiation protection control applied. The data used for this study correspond to a very lengthy period of time and it have been collected in the radioactive facility, of the Centro Nacional de Biotecnologia (CSIC), a very large biological research centre that can be used perfectly as a reference for this area. The results obtained show a gradual and significant decrease in the incidence of the radioactive contamination. This is due to the optimization of radiation protection standards applied and the implementation or a systematic operational radiation protection program. (Author) 13 refs.

  13. Electrolyze radioactive contamination away

    International Nuclear Information System (INIS)

    Wedman, D.E.; Martinez, H.E.; Nelson, T.O.

    1996-01-01

    The Los Alamos National Laboratory Plutonium Facility is using electrolysis to clean the surfaces of hazardous materials. In the past, contaminated metals were cleaned with concentrated acids. Although these treatments make the surfaces safer, they produce other radioactive and toxic wastes in turn. Anodic current passes through a piece of stainless steel submersed in a sodium nitrate solution, and steel dissolves at the surfaces. Surface contamination strips away along with the surface layers. The authors are using this electrolysis approach to remove plutonium and americium from stainless steel and uranium. Unlike acid washing processes, electrolytic decontamination can be accomplished quickly. Little waste is generated regardless of how much material has to be removed from the surface. Material removal is proportional to the applied current, which gives the operator control over the rate and extent of decontamination

  14. Radioactive Waste.

    Science.gov (United States)

    Blaylock, B. G.

    1978-01-01

    Presents a literature review of radioactive waste disposal, covering publications of 1976-77. Some of the studies included are: (1) high-level and long-lived wastes, and (2) release and burial of low-level wastes. A list of 42 references is also presented. (HM)

  15. Radioactivity measurements

    International Nuclear Information System (INIS)

    Schwach, G.

    1986-01-01

    This is an overview of radioactivity monitoring work done in the Austrian Research Centre Seibersdorf in the wake of the Chernobyl accident. It consists of air, rainwater, food and personnel monitoring. Additional services to the public are: information and development of a database and a computer code for predicting future radionuclide concentration in air, soil, water and food. (G.Q.)

  16. Arthropathie destructrice des epaules au cours d�une acromegalie

    Directory of Open Access Journals (Sweden)

    Nessrine Akasbi

    2011-10-01

    Full Text Available L�acromegalie est une maladie endocrinienne rare, en rapport avec une hypersecretion d�hormone de croissance. Elle a des consequences rhumatologiques: l�arthropathie peripherique, l�atteinte rachidienne et les syndromes canalaires. L�atteinte articulaire accompagne une acromegalie active, sa survenue apres un traitement radical et une remission complete est rare. Nous presentons le cas d�une patiente de 70 ans ayant un antecedent d�acromegalie sur adenome hypophysaire il y a 25 ans, traitee chirurgicalement et declaree en remission complete, a developpe une arthropathie destructrice des deux epaules. Le but de notre observation est de mettre le point sur la possibilite d�une atteinte articulaire au cours de l�acromegalie et de son retentissement fonctionnelle.

  17. Disposal of radioactive wastes

    International Nuclear Information System (INIS)

    Dlouhy, Z.

    1982-01-01

    This book provides information on the origin, characteristics and methods of processing of radioactive wastes, as well as the philosophy and practice of their storage and disposal. Chapters are devoted to the following topics: radioactive wastes, characteristics of radioactive wastes, processing liquid and solid radioactive wastes, processing wastes from spent fuel reprocessing, processing gaseous radioactive wastes, fixation of radioactive concentrates, solidification of high-level radioactive wastes, use of radioactive wastes as raw material, radioactive waste disposal, transport of radioactive wastes and economic problems of radioactive wastes disposal. (C.F.)

  18. Application d'une équation d'état à la simulation du comportement thermodynamique des fluides dans les gisements et dans les installations de surface Application of an Equation of State to Simulating the Thermodynamic Behaviour of Fluids in Reservoirs and Surface Installations

    Directory of Open Access Journals (Sweden)

    Jain C.

    2006-11-01

    Full Text Available La connaissance des propriétés thermodynamiques des fluides pétroliers, en particulier des masses volumiques et des coefficients d'équilibre liquide-vapeur, intervient à divers stades de la production : primaire, secondaire par in-jection de gaz (C02 ou hydrocarbures miscibles, vapeur d'eau, séparation, réseau de collecte et de transport. L'ampleur du domaine de pression et de température à l'intérieur duquel on a besoin de connaître les propriétés des huiles et des gaz à condensat, et le fait que la compo-sition d'ensemble des mélanges diphasiques ne cesse de varier au cours de leur déplacement soit dans les gisements, soit dans les installations d'exploitation, rendent mani-feste l'intérêt de pouvoir calculer ces propriétés, en évi-tant d'avoir recours à des travaux de laboratoire beaucoup trop importants. Pour résoudre ces problèmes, une nouvelle équation d'état appelée Redlich-Kwong Développée (RKD a été mise au point. Au cours de cet exposé, nous verrons que cette équation restitue les enveloppes diphasiques de l'équilibre liquide-vapeur avec une qualité au moins égale à celles des méthodes de Soave et de Peng-Robinson qui jouissent actuellement d'une grande notoriété. L'avantage de ce modèle sur ces dernières méthodes est l'évaluation simultanée des propriétés volumétriques des phases en présence avec une bonne précision, ce qui est d'une grande utilité pour l'application de ce modèle aux problèmes industriels. Knowing the thermodynamic properties of petroleum fluids, and in particular the density and liquid-vapor equilibrium coefficients, is important at different stages of production, i. e. primary production, secondary production by gas flooding (CO2 or miscible hydrocarbons, steam, separation, gathering network and transportation. The pressure and temperature range within which the oil and gas-condensate properties must be known coupled with the fact that the overall composition of

  19. NRI's research on radioactive wastes

    International Nuclear Information System (INIS)

    Alexa, J.; Dlouhy, Z.; Kepak, F.; Kourim, V.; Napravnik, J.; Razga, J.; Ralkova, J.; Uher, E.; Vojtech, O.

    1976-01-01

    A survey is given (including 41 references) of work carried out at the Nuclear Research Institute. Discussed are sorption processes (a selective sorbent for 90 Sr based on BaSO 4 , etc.), sorption on inorganic ion exchangers (heteropolyacid salts, ferrocyanides for 137 Cs capture), on organic cation exchangers (separation of lanthanides), electrocoagulation. The process is described of vitrification of highly radioactive wastes, the arrest of emissions, the deposition of radioactive wastes and surface decontamination. (M.K.)

  20. The management of radioactive wastes

    International Nuclear Information System (INIS)

    1998-01-01

    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.)

  1. Design and Performance Assessment of a Conceptual Cover Cap of Near Surface Repository for Short Lived Low and Intermediate Level Radioactive Waste

    Energy Technology Data Exchange (ETDEWEB)

    Asaba, Ruth; Kim, Changlak [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2014-05-15

    The safety of the overall waste disposal system is determined by the performance of its individual components: waste form, waste container, engineered barrier and the host environment. The design of the cover cap helps in preventing percolation of water, and in retarding radionuclide migration from the disposal facility to the biosphere. The cover of a disposal facility is usually a combination of materials such as sand, gravel, concrete, clay and soil conditioned for vegetation growth. The cover system will be designed using models such as EPA's Hydrological Evaluation of Land fill Performance (HELP) code. This paper describes a conceptual design for a cover cap for a land fill as a preferred disposal facility for low and short lived intermediate radioactive waste in Uganda. Majority of the waste is generated from disused sealed and unsealed radioactive sources arising from medical, industrial applications, and research. Radioactive waste management has raised a lot of concern in both developed and developing countries. Each country has a responsibility to come up with a solution to prevent contamination of the environment and humans from radioactive waste. It is important to have thicker soil layers in cap designs so as to support vegetation growth since some activities such as erosion and settlements are expected. Help simulations in this study will assist to demonstrate that it is possible to design a cover cap which can contain radioactive waste packages for hundreds of years provided the proper institutional and performance monitoring schemes are implemented.

  2. D'une industrie... l'autre?

    NARCIS (Netherlands)

    Musso, S.; Nguyen, V.K.

    2013-01-01

    À partir d’une contextualisation du texte de Cindy Patton, les auteur-e-s invitent à penser l’actualité des questions évoquées à l’aune d’enjeux contemporains relatifs à la production d’identités et de communautés que donnent à voir l’établissement des « cibles » de la prévention et du traitement du

  3. Radioactive waste management

    International Nuclear Information System (INIS)

    2013-01-01

    This eighth chapter presents the radioactive wastes and waste disposal; classification of radioactive wastes; basis requests of the radioactive waste management; conditions for a radioactive waste disposal; registers and inventories; transport of radioactive wastes from a facility to another and the radioactive waste management plan

  4. Distribution of natural radioactivity in surface soil from the vicinity of Lynas Rare-Earth Plant at Gebeng, Kuantan and its potential radiation hazard to humans

    International Nuclear Information System (INIS)

    Wo, Y.M.; Zal U'yun Wan Mahmood; Faizal Azirin Abdul Razalim; Abdul Kadir Ishak

    2016-01-01

    The concentrations of natural gamma ray emitting radionuclides in the surface soil from the vicinity of Lynas Rare earth plant in Kuantan, Pahang were studied with the aim of evaluating the environmental radioactivity of that area. The concentration of "2"2"6Ra ranged between 8.7 - 95.4 Bq/ kg with a mean value of 34.6 Bq/ kg; "2"2"8Ra activity between 6.6 - 134 Bq / kg with a mean of 61.9 Bq/ kg; the activity of "2"3"8U varied from 8.7 to 106 Bq/ kg with a mean value of 38.0 Bq/ kg; for "2"3"2Th, it ranged from 6.2 to 130 Bq/ kg with a mean value of 60.3 Bq/ kg, while for "4"0K, the values were from 10.6 to 1160 Bq/ kg with a mean of 244.8 Bq/ kg. The activity standard deviation for "2"2"6Ra, "2"2"8Ra, "2"3"8U, "2"3"2Th and "4"0K was 15.8 Bq/ kg, 27.3 Bq/ kg, 16.9 Bq/ kg, 26.6 Bq/ kg and 218.7 Bq/ kg, respectively. To estimate the potential radiation hazard to human, the radium equivalent activity, external hazard index and dose rate in air from the terrestrial natural gamma radiation were calculated. The maximum value found for these three parameters was 335.9 Bq/ kg, 0.94 and 161.8 nGy/ h, respectively. The data was discussed and compared with those reported in the literatures. The study found that the dose equivalent could be received by an individual at the vicinity area (outdoor) of Lynas plant was estimated in between 10.9 - 204.3 μSv/ yr with mean value of 84.3 μSv/ yr. This value is well below the annual dose limit 1,000 μSv/ yr for general public. (author)

  5. Radioactive waste

    International Nuclear Information System (INIS)

    Berkhout, F.

    1991-01-01

    Focusing on radioactive waste management and disposal policies in the United Kingdom, Sweden and the Federal Republic of Germany, this book gives a detailed historical account of the policy process in these three countries, and draws out the implications for theory and public policy. This comparative approach underlines how profoundly different the policy process has been in different countries. By comparing the evolution of policy in three countries, fundamental questions about the formation and resolution of technical decisions under uncertainty are clarified. The analysis of nuclear strategy, the politics of nuclear power, and the shifting emphasis of government regulation redefines the issue of radwaste management and sets it at the heat of the current debate about power, the environment and society. The combination of up-to-date technological assessment with an account of the social and political implications of radwaste management makes'Radioactive Waste'particularly useful to students of environmental studies, geography and public administration. (author)

  6. Radioactive waste

    Energy Technology Data Exchange (ETDEWEB)

    Berkhout, F

    1991-01-01

    Focusing on radioactive waste management and disposal policies in the United Kingdom, Sweden and the Federal Republic of Germany, this book gives a detailed historical account of the policy process in these three countries, and draws out the implications for theory and public policy. This comparative approach underlines how profoundly different the policy process has been in different countries. By comparing the evolution of policy in three countries, fundamental questions about the formation and resolution of technical decisions under uncertainty are clarified. The analysis of nuclear strategy, the politics of nuclear power, and the shifting emphasis of government regulation redefines the issue of radwaste management and sets it at the heat of the current debate about power, the environment and society. The combination of up-to-date technological assessment with an account of the social and political implications of radwaste management makes'Radioactive Waste'particularly useful to students of environmental studies, geography and public administration. (author).

  7. Radioactive transformations

    CERN Document Server

    Rutherford, Ernest

    2012-01-01

    Radioactive Transformations describes Ernest Rutherford's Nobel Prize-winning investigations into the mysteries of radioactive matter. In this historic work, Rutherford outlines the scientific investigations that led to and coincided with his own research--including the work of Wilhelm Rӧntgen, J. J. Thomson, and Marie Curie--and explains in detail the experiments that provided a glimpse at special relativity, quantum mechanics, and other concepts that would shape modern physics. This new edition features a comprehensive introduction by Nobel Laureate Frank Wilczek which engagingly explains how Rutherford's early research led to a better understanding of topics as diverse as the workings of the atom's nucleus, the age of our planet, and the fusion in stars.

  8. Radioactive hazards

    International Nuclear Information System (INIS)

    Gill, J.R.

    1980-01-01

    The use of radioactive substances in hospital laboratories is discussed and the attendant hazards and necessary precautions examined. The new legislation under the Health and Safety at Work Act which, it is proposed, will replace existing legal requirements in the field of health and safety at work by a system of regulations and approved codes of practice designed to maintain or improve the standards of health, safety and welfare already established, is considered with particular reference to protection against ionising radiations. (UK)

  9. Radioactive substances

    International Nuclear Information System (INIS)

    Butler, G.C.; Hyslop, C.

    1980-01-01

    The purpose of this chapter is to show how to assess the detriment resulting from the release of radioactive materials to the environment. The minimum information required for the assessments is given for seven radionuclides of interest from the point of view of environmental contamination. The seven radionuclides are tritium, krypton-85, strontium-90, iodine-131, cesium-137, radium-226 and plutonium-239. Information is given on the radiation doses and the radiation effects on man due to these radioisotopes. (AN)

  10. Radioactive wastes

    International Nuclear Information System (INIS)

    Devarakonda, M.S.; Melvin, J.M.

    1994-01-01

    This paper is part of the Annual Literature Review issue of Water Environment Research. The review attempts to provide a concise summary of important water-related environmental science and engineering literature of the past year, of which 40 separate topics are discussed. On the topic of radioactive wastes, the present paper deals with the following aspects: national programs; waste repositories; mixed wastes; waste processing and decommissioning; environmental occurrence and transport of radionuclides; and remedial actions and treatment. 178 refs

  11. Impact d'une modulation duale sur les performances d'une liaison ...

    African Journals Online (AJOL)

    Le présent document présente la technique de modulation duale Fréquence - Amplitude dans le cas d'une liaison optique du type IM-DD. Ce travail révèle que la modulation duale Fréquence - Amplitude permet de générer un signal à bande latérale unique. Les performances d'une liaison optique IM-DD basée sur cette ...

  12. Pump station for radioactive waste water

    Science.gov (United States)

    Whitton, John P.; Klos, Dean M.; Carrara, Danny T.; Minno, John J.

    2003-11-18

    A pump station for transferring radioactive particle containing waste water, includes: (a.) an enclosed sump having a vertically elongated right frusto conical wall surface and a bottom surface and (b.) a submersible volute centrifugal pump having a horizontally rotating impeller and a volute exterior surface. The sump interior surface, the bottom surface and the volute exterior surface are made of stainless steel having a 30 Ra or finer surface finish. A 15 Ra finish has been found to be most cost effective. The pump station is used for transferring waste water, without accumulation of radioactive fines.

  13. Decontamination of radioactive isotopes

    International Nuclear Information System (INIS)

    Despotovic, R.; Music, S.; Subotic, B.; Wolf, R.H.H.

    1979-01-01

    Removal of radioactive isotopes under controlled conditions is determined by a number of physical and chemical properties considered radiocontaminating and by the characteristics of the contaminated object. Determination of quantitative and qualitative factors for equilibrium in a contamination-decontamination system provides the basis for rational and successful decontamination. The decontamination of various ''solid/liquid'' systems is interesting from the scientific and technological point of view. These systems are of great importance in radiation protection (decontamination of various surfaces, liquids, drinking water, fixation or collection of radiocontaminants). Different types of decontamination systems are discussed. The dependence of rate and efficiency of the preparation conditions and on the ageing of the scavenger is described. The influence of coagulating electrolyte on radioactive isotope fixation efficiency was also determined. The fixation of fission radionuclide on oxide scavengers has been studied. The connection between fundamental investigations and practical decontamination of the ''solid/liquid'' systems is discussed. (author)

  14. Radioactive waste management

    International Nuclear Information System (INIS)

    Pahissa Campa, Jaime; Pahissa, Marta H. de

    2000-01-01

    Throughout this century, the application of nuclear energy has produced many benefits, in industry, in research, in medicine, and in the generation of electricity. These activities generate wastes in the same way as do other human activities. The primary objective of radioactive waste management is to protect human health and environment now and in the future without imposing undue burden on future generations, through sound, safe and efficient radioactive waste management. This paper briefly describes the different steps of the management of short lived low and intermediate level wastes, and presents and overview of the state of art in countries involved in nuclear energy, describing their organizations, methodologies used in the processing of these wastes and the final disposal concepts. It also presents the Argentine strategy, its technical and legal aspects. Worldwide experience during the past 50 years has shown that short lived low and intermediate level wastes can be successfully isolated from human and environment in near surface disposal facilities. (author)

  15. Radioactive waste processing device

    International Nuclear Information System (INIS)

    Seki, Shuji.

    1992-01-01

    Liquid wastes are supplied to a ceramic filter to conduct filtration. In this case, a device for adding a powdery inorganic ion exchanger is disposed to the upstream of the ceramic filter. When the powdery inorganic ion exchanger is charged to the addition device, it is precoated to the surface of the ceramic filter, to conduct separation of suspended matters and separation of ionic nuclides simultaneously. Liquid wastes returned to a collecting tank are condensed while being circulated between the ceramic filter and the tank and then contained in a condensation liquid waste tank. With such a constitution, both of radioactive nuclides accompanied by suspended matters in the radioactive liquid wastes and ionic nuclides can be captured efficiently. (T.M.)

  16. Monitoring of environmental radioactivity

    International Nuclear Information System (INIS)

    1986-01-01

    The results are described of monitoring radioactivity of atmospheric fallout, surface waters, soils, plant feeds, cereals, and other agricultural produce. The results were obtained over a long time period. Radioactivity was also measured of milk, milk products, vegetables and fruits, meat and hen eggs, flour and bakery products with a view to radionuclide migration in the food chain. The daily intake of 90 Sr and 137 Cs from food was determined from the values obtained and the consumption of the individual types of food. Strontium-90 distribution was studied in the bones and the teeth of the population in Slovakia. With the commissioning of nuclear power plants, emissions and liquid wastes were monitored and their environmental impact assessed. (E.S.)

  17. 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)

  18. Radioactive liquid water processing method

    International Nuclear Information System (INIS)

    Yasumura, Keijiro; Noda, Tetsuya; Kobayashi, Fumio.

    1993-01-01

    Alkaline earth metals and heavy metals are added to radioactive liquid wastes containing a surface active agent comprising alkali metal salts of higher fatty acids. These metals form metal soaps with the surface active agent dissolved in the liquid wastes and crystallized. The crystallized metal soaps are introduced to a filtering column filled with a burnable polymeric fibrous filtering material. The filtering material is burnt. This can remove the surface active agent to remove COD without using an active carbon. (T.M.)

  19. Radioactive waste management - with evidence

    International Nuclear Information System (INIS)

    1988-01-01

    The select committee was appointed to report on the present (1988) situation and future prospects in the field of radioactive waste management in the European Community. The report covers all aspects of the subject. After an introduction the parts of the report are concerned with the control of radiation hazards, the nuclear fuel cycle and radioactive waste, the control of radioactive effluents, storage and disposal of solid radioactive wastes, research programmes, surface storage versus deep geological disposal of long-term wastes, the future of reprocessing and the public debate. Part 10 is a resume of the main conclusions and recommendations. It is recommended that the House of Lords debate the issue. The oral and written evidence presented to the committee is included in the report. (U.K.)

  20. Method of processing radioactive wastes

    International Nuclear Information System (INIS)

    Takahashi, Toshihiko; Maruko, Morihisa; Takamura, Yoshiyuki.

    1981-01-01

    Purpose: To effectively separate radioactive claddings from the slurry of wasted ion exchange resins containing radioactive claddings. Method: Wasted ion exchange resins having radioactive claddings (fine particles of iron oxides or hydroxide adhered with radioactive cobalt) are introduced into a clad separation tank. Sulfuric acid or sodium hydroxide is introduced to the separation tank to adjust the pH value to 3 - 6. Then, sodium lauryl sulfate is added for capturing claddings and airs are blown from an air supply nozzle to generate air bubbles. The claddings are detached from the ion exchange resins and adhered to the air bubbles. The air bubbles adhered with the claddings float up to the surface of the liquid wastes and then forced out of the separation tank. (Ikeda, J.)

  1. Method of processing radioactive wastes

    International Nuclear Information System (INIS)

    Katada, Katsuo.

    1986-01-01

    Purpose: To improve the management for radioactive wastes containers thereby decrease the amount of stored matters by arranging the radioactive wastes containers in the order of their radioactivity levels. Method: The radiation doses of radioactive wastes containers arranged in the storing area before volume-reducing treatment are previously measured by a dosemeter. Then, a classifying machine is actuated to hoist the containers in the order to their radiation levels and the containers are sent out passing through conveyor, surface contamination gage, weight measuring device and switcher to a volume-reducing processing machine. The volume-reduced products are packed each by several units to the storing containers. Thus, the storing containers after stored for a certain period of time can be transferred in an assembled state. (Kawakami, Y.)

  2. Method of solidifying radioactive wastes

    International Nuclear Information System (INIS)

    Fukazawa, Tetsuo; Ootsuka, Masaharu; Uetake, Naoto; Ozawa, Yoshihiro.

    1984-01-01

    Purpose: To prepare radioactive solidified wastes excellent in strength, heat resistance, weather-proof, water resistance, dampproof and low-leaching property. Method: A hardening material reactive with alkali silicates to form less soluble salts is used as a hardener for alkali silicates which are solidification filler for the radioactive wastes, and mixed with cement as a water absorbent and water to solidify the radioactive wastes. The hardening agent includes, for example, CaCO 3 , Ca(ClO 4 ) 2 , CaSiF 6 and CaSiO 3 . Further, in order to reduce the water content in the wastes and reduce the gap ratio in the solidification products, the hardener adding rate, cement adding rate and water content are selected adequately. As the result, solidification products can be prepared with no deposition of easily soluble salts to the surface thereof, with extremely low leaching of radioactive nucleides. (Kamimura, M.)

  3. Radioactivity telemetry

    International Nuclear Information System (INIS)

    Bouras, Florent; Legrand, Bernard; Montigaud, Jean-Marie; Grandin, Marc

    1969-05-01

    The authors present an assembly which aims at radio-transmitting from mobile stations information on radioactivity. It comprises 20 mobile stations which can be located within the Cadarache Centre or outside of it within a 10 km radius, and a central station which centralises information. The report proposes a general presentation of these stations, their characteristics and principles of operation. It describes operation sequences, central station functions (call programmer, address and memory management, recording, peripherals) and its energy supply, and mobile station functions. The last part presents the installation, its start-up and exploitation, its threshold devices and its safety device

  4. National radioactive wasterRepository Mochovce

    International Nuclear Information System (INIS)

    2000-01-01

    In this leaflet the scheme of the Mochovce National radioactive waste repository for the Slovak Republic is presented. The National radioactive waste repository in Mochovce is a surface type storage facility. It is intended for final disposal of solid and solidified low and intermediate radioactive waste produced during the operation of nuclear power plants and institutions located within the territory of the Slovak Republic. The Repository site is situated about 2 km northwest to the Mochovce NPP

  5. L'allocation universelle, une solution d'avenir?

    OpenAIRE

    Van Parijs, Philippe

    2012-01-01

    Le fait L’avenir de la sécurité sociale fait aussi débat en Suisse. Une initiative populaire vient d’être lancée “pour un revenu de base inconditionnel”. Si elle récolte 100000 signatures, cette proposition pourra être soumise à une votation pour devenir loi. Plus fort, une “initiative citoyenne européenne” sur cette question va être lancée en septembre. Objectif: un million de signatures. De quoi parle-t-on? Il s’agit d’une allocation universelle attribuée à toute personne individuellement, ...

  6. Business plan pour une application Smartphone : du concept au lancement

    OpenAIRE

    Vriamont, Gilles

    2015-01-01

    Création d'une application mobile pour Smartphone. Description théorique concernant la rédaction d'un business plan dans une première partie suivi d'une description théorique des caractéristiques des applications mobiles. Dans une seconde partie, analyse de l'industrie des Smartphones et des applications mobiles suivi de la partie pratique et du développement du produit, partant de la description du produit jusqu'à l'analyse des coûts. Master [120] en Ingénieur de gestion, Université catho...

  7. Une tumeur exceptionnelle du doigt: la tumeur fibreuse solitaire

    Directory of Open Access Journals (Sweden)

    Taoufiq Harmouch

    2011-12-01

    Full Text Available La tumeur Fibreuse solitaire (TFS est une proliferation fusocellulaire rare, souvent de localisation intrathoracique. Nous rapportons le cas d�une localisation exceptionnelle au niveau du 3eme doigt de la main droite. En l�absence de marqueur specifique l�interpretation de l�immunomarquage depend du contexte histomorphologique. La similitude avec les differents neoplasmes a cellules fusiformes des tissus mous rend le diagnostic de ces tumeurs mesenchymateuses difficile et tardif. Dans 20a 30 % des cas le comportement de la TFS est celui d�une tumeur maligne localement agressive et recidivante, avec des metastases rares et tardives. Ce comportement impose une surveillance prolongee apres exerese chirurgicale.

  8. Einstein une biographie dessinée

    CERN Document Server

    Maier, Corinne

    2015-01-01

    « Je m'appelle Albert Einstein. En voulant comprendre l'univers, j'ai libéré des forces de destruction terrifiantes. Mais il faut continuer à chercher le grand secret du cosmos. » Albert Einstein (1879-1955) est un immense génie devenu, sans le vouloir, une star de la science. Avec ses théories de la relativité restreinte puis de la relativité générale, il a radicalement transformé nos vies. Voici le récit de son existence passionnée et de ses contributions fondamentales.

  9. Commande adaptive d'une machine asynchrone

    Science.gov (United States)

    Slama-Belkhodja, I.; de Fornel, B.

    1996-06-01

    The paper deals with an indirect self-tuning speed control for an induction motor supplied by a chopper-filter-inverter system. Input/Output models are identified with the recursive least squares algorithm and the controller adaptation is based on a pole assignement strategy. Emphasis is put on the evaluation of the parameter identification in order to avoid instabilities because of disturbances or insufficient excitations. This is especially of importance when the adaptive control is carried out in closed loop systems and without additional test signals. Simulation results show the improvement of the dynamic responses and the robustness against load variations or parameters variations (rotor resistance, inertia). Cat article décrit une stratégie de commande adaptive indirecte à Placement de Pôles (PP), appliquée à la commande en vitesse d'une machine asynchrone alimentée par un ensemble hacheur-filtre-onduleur de tension. L'algorithme des Moindres Carrés Récursifs (MCR) est utilisé pour l'identification des modèles de comportement type entrées/sorties. Un intérêt particulier est porté à la mise en oeuvre de cet algorithme et à la discussion de ses résultats, tenant compte des erreurs de modélisation et de la nature peu riche en excitations des entrées du processus. Différents régimes transitoires ont été simulés pour apprécier l'apport de cette association (MCR-PP) : démarrages et inversion des sens de rotation, à vide et en charges, applications d'échelons de couple résistant, variations paramétriques. Les résultats permettent d'illustrer, tant au niveau des performances que de la robustesse, l'apport d'une telle commande adaptive pour des entraînements électriques avec une machine asynchrone.

  10. Pour une anthropologie de la communication Introduction

    OpenAIRE

    RIONDET, Odile

    2004-01-01

    Premier texte d'une série de 8.; For an anthropology of communication What do we mean by “anthropology of communication”? The term is used for the ethnographic analysis of human communication as well as for behavioural changes due to the application of new information technologies. We put forward an introduction (below), to be followed by seven texts: three reflections on “anthropology”, three on “communication” and one concerned with the overlap between these two concepts. Starting with Dece...

  11. Une hanche douloureuse révélatrice d'une histiocytose osseuse multifocale

    Science.gov (United States)

    Lahrach, Kamal; Alaoui, Adil; el Kadi, Khalid Ibn; Marzouki, Amine; Boutayeb, Fawzi

    2014-01-01

    L'histiocytose langerhansienne est une maladie rare qui touche principalement l'enfant et l'adulte jeune. Elle peut prendre plusieurs aspects, L'atteinte osseuse peut être uni- ou multifocale. Nous rapportons une observation d'histiocytose langerhansienne osseuse multifocale, révélée chez un patient âgé de 23 ans et ayant touché le col fémoral droit. La scintigraphie osseuse a permis de retrouver plusieurs localisations: l'os temporal, humérale et scapulaire droite. En raison du risque fracturaire, le patient a bénéficié d'une ostéosynthèse par vis-plaque DHS avec curetage biopsie de la lésion. L'examen histologique a révélé une histiocytose langerhansienne. L'évolution fut favorable après chimiothérapie par voie générale. PMID:25018840

  12. Regulation of radioactive waste management

    International Nuclear Information System (INIS)

    2002-01-01

    This bulletin contains information about activities of the Nuclear Regulatory Authority of the Slovak Republic (UJD). In this leaflet the regulation of radioactive waste management of the UJD are presented. Radioactive waste (RAW) is the gaseous, liquid or solid material that contains or is contaminated with radionuclides at concentrations or activities greater than clearance levels and for which no use is foreseen. The classification of radioactive waste on the basis of type and activity level is: - transition waste; - short lived low and intermediate level waste (LlLW-SL); - long lived low and intermediate level waste (LlLW-LL); - high level waste. Waste management (in accordance with Act 130/98 Coll.) involves collection, sorting, treatment, conditioning, transport and disposal of radioactive waste originated by nuclear facilities and conditioning, transport to repository and disposal of other radioactive waste (originated during medical, research and industrial use of radioactive sources). The final goal of radioactive waste management is RAW isolation using a system of engineered and natural barriers to protect population and environment. Nuclear Regulatory Authority of the Slovak Republic regulates radioactive waste management in accordance with Act 130/98 Coll. Inspectors regularly inspect and evaluate how the requirements for nuclear safety at nuclear facilities are fulfilled. On the basis of safety documentation evaluation, UJD issued permission for operation of four radioactive waste management facilities. Nuclear facility 'Technologies for treatment and conditioning contains bituminization plants and Bohunice conditioning centre with sorting, fragmentation, evaporation, incineration, supercompaction and cementation. Final product is waste package (Fibre reinforced container with solidified waste) acceptable for near surface repository in Mochovce. Republic repository in Mochovce is built for disposal of short lived low and intermediate level waste. Next

  13. Environmental Radioactivity. Chapter 4

    International Nuclear Information System (INIS)

    Muhamat Omar; Ismail Sulaiman; Zalina Laili

    2015-01-01

    This chapter explains several things which consist radioactivity measurements, regular and high background radioactivity, radioactive contaminated soil and radioactivity in fertilizers, rocks, building materials, food, water, environments, sediments, flora and fauna. Besides, the natural radioactive gas concentration of radon and toron in the environment also been discussed specifically in this chapter.

  14. Soil radium, soil gas radon and indoor radon empirical relationships to assist in post-closure impact assessment related to near-surface radioactive waste disposal.

    Science.gov (United States)

    Appleton, J D; Cave, M R; Miles, J C H; Sumerling, T J

    2011-03-01

    Least squares (LS), Theil's (TS) and weighted total least squares (WTLS) regression analysis methods are used to develop empirical relationships between radium in the ground, radon in soil and radon in dwellings to assist in the post-closure assessment of indoor radon related to near-surface radioactive waste disposal at the Low Level Waste Repository in England. The data sets used are (i) estimated ²²⁶Ra in the < 2 mm fraction of topsoils (eRa226) derived from equivalent uranium (eU) from airborne gamma spectrometry data, (ii) eRa226 derived from measurements of uranium in soil geochemical samples, (iii) soil gas radon and (iv) indoor radon data. For models comparing indoor radon and (i) eRa226 derived from airborne eU data and (ii) soil gas radon data, some of the geological groupings have significant slopes. For these groupings there is reasonable agreement in slope and intercept between the three regression analysis methods (LS, TS and WTLS). Relationships between radon in dwellings and radium in the ground or radon in soil differ depending on the characteristics of the underlying geological units, with more permeable units having steeper slopes and higher indoor radon concentrations for a given radium or soil gas radon concentration in the ground. The regression models comparing indoor radon with soil gas radon have intercepts close to 5 Bq m⁻³ whilst the intercepts for those comparing indoor radon with eRa226 from airborne eU vary from about 20 Bq m⁻³ for a moderately permeable geological unit to about 40 Bq m⁻³ for highly permeable limestone, implying unrealistically high contributions to indoor radon from sources other than the ground. An intercept value of 5 Bq m⁻³ is assumed as an appropriate mean value for the UK for sources of indoor radon other than radon from the ground, based on examination of UK data. Comparison with published data used to derive an average indoor radon: soil ²²⁶Ra ratio shows that whereas the published data are

  15. Seven years of experience in storage of solid radioactive wastes of low and medium activity on the surface or in concrete ditches

    International Nuclear Information System (INIS)

    Bardet, G.

    This experience in the transport and storage of radioactive waste leads to several reflections pertinent to large-scale nuclear installations throughout the world. The experience demonstrates that products of this kind can be centralized and confined by relatively simple processes which are safe and of reasonable cost. The necessary liaison between the producer of radioactive wastes and the group which takes charge of storage is emphasized for the choice of the waste conditioning procedure. It is a consistent part of the experience that the initial conditioning determines in large measure the handling and storage techniques. It is certain that the absence of a solution for long-term storage of radioactive wastes will lead the producers to consider and carry out conditioning which, although valuable, does not have all the same advantages for final disposition of the product. In the field of transport, the volumes and weights are important. It is desirable that a permanent storage center be near a railroad. It is stated that storage can be ensured under safe conditions and with acceptable costs of all solid wastes of low and average activity except those having more than a certain amount of alpha activity. For the latter products a solution can be found which is safe

  16. Michel Houellebecq : un homme, une (soumission

    Directory of Open Access Journals (Sweden)

    Marc Smeets

    2015-12-01

    Full Text Available Michel Houellebecq, l’auteur le plus controversé de la littérature française contemporaine, semble s’astreindre à une seule et unique mission : celle d’être « vrai » à n’importe quel prix. Observateur et peintre de la société actuelle dans tous ses états, l’auteur de Soumission s’inscrit dans une tradition littéraire qui remonte au XIXe siècle, prolongeant ainsi les fictions de Balzac, de Zola et de Huysmans. De ses prédécesseurs Houellebecq hérite d’un certain goût pour la controverse, talent qui fait naturellement la pluie et le beau temps dans la presse. Le rôle que jouent la documentation et la figure du célibataire permet de situer l’écrivain dans le sillage de la tradition réalistico-naturaliste.

  17. UNE INTERPRETATION DU TAUX DE CHANGE

    Directory of Open Access Journals (Sweden)

    Galina ULIAN

    2015-03-01

    Full Text Available Dans l’étude ci-dessous on a été réalisé une interprétation de l'impact des fluctuations des taux de change du leu moldave (MDL sur certaines variables économiques. La période considérée est Novembre-Décembre 2014 et le début de l'année 2015. Notamment au cours de cette période, le taux de la monnaie nationale par rapport aux principales devises de référence de change a commencé la voie de fortes dévaluations. Cette tendance, cependant, s’est placée dans le contexte des situations similaires dans la région, qui a ainsi permis sa dépréciation graduelle. Compte tenu que la dépréciation de la monnaie est un phénomène aux effets complexes et multilatérales, une fois arrivé dans un pays "X", celui-ci devrait, afin d'améliorer la situation, en premier lieu, augmenter leur présence sur d'autres marchés de ventes, plus stable et avec de plus grandes possibilités.

  18. L’UTOPIE – UNE FANTAISIE COMEPENSATOIRE ?

    Directory of Open Access Journals (Sweden)

    Ilinca BĂLAȘ

    2013-11-01

    Full Text Available La création du mot utopie n’est pas seulement l’acte de naissance d’un genre littéraire - le genre utopique, mais aussi la source d'une approche possible de l'utopie en tant que fantaisie compensatoire, à la suite du rapprochement entre le néologisme en linguistique et le néologisme en psychiatrie. Moyennant les concepts psychanalytiques de compensation et de régression, l'utopie pourrait être considérée soit comme une solution soit pour échapper à un complexe d'infériorité émanant d'un présent jugé comme insatisfaisant, soit comme un retour à des temps bienheureux de l'humanité. Dans les deux cas, la question angoissante qui en découle est si l’utopie relève du rêve ou bien plutôt du cauchemar.

  19. Theoretical study of the influence on surface temperature of a geometrical perturbation of wall of an electrically heated channel (1960); Etude theorique de l'influence, sur la temperature de surface, d'une perturbation geometrique de la paroi d'un canal chauffe electriquement (1960)

    Energy Technology Data Exchange (ETDEWEB)

    Gerber, R [Commissariat a l' Energie Atomique, Section des Transferts Thermiques, Grenoble (France).Centre d' Etudes Nucleaires; Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1960-07-01

    In experiments on forced convection heat transfer in an electrically heated channel, the temperature of the channel face in contact with the fluid is generally calculated from the measured temperature of the isolated face. A process for measuring this temperature leads to the study of the theoretical influence of a local perturbation of the wall thickness on the temperature distribution in this wall. Various problems at the limits, posed by this question of measurement, are dealt with. (author) [French] Dans les experiences de transfert thermique en convection forcee, dans un canal chauffe electriquement, la temperature de la face du canal en contact avec le fluide, est generalement calculee a partir de la temperature mesuree de la face isolee. Un procede de mesure de cette temperature conduit a etudier l'influence theorique d'une perturbation locale de l'epaisseur de la paroi sur la repartition de la temperature dans cette paroi. Divers problemes aux limites, posees par cette question de mesure, sont traites. (auteur)

  20. Public debate on radioactive wastes

    International Nuclear Information System (INIS)

    2005-01-01

    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.)

  1. Radioactive wastes handling facility

    International Nuclear Information System (INIS)

    Hirose, Emiko; Inaguma, Masahiko; Ozaki, Shigeru; Matsumoto, Kaname.

    1997-01-01

    There are disposed an area where a conveyor is disposed for separating miscellaneous radioactive solid wastes such as metals, on area for operators which is disposed in the direction vertical to the transferring direction of the conveyor, an area for receiving the radioactive wastes and placing them on the conveyor and an area for collecting the radioactive wastes transferred by the conveyor. Since an operator can conduct handling while wearing a working cloth attached to a partition wall as he wears his ordinary cloth, the operation condition can be improved and the efficiency for the separating work can be improved. When the area for settling conveyors and the area for the operators is depressurized, cruds on the surface of the wastes are not released to the outside and the working clothes can be prevented from being involved. Since the wastes are transferred by the conveyor, the operator's moving range is reduced, poisonous materials are fallen and moved through a sliding way to an area for collecting materials to be separated. Accordingly, the materials to be removed can be accumulated easily. (N.H.)

  2. Radioactive waste processing vessel

    International Nuclear Information System (INIS)

    Hayashi, Masaru; Suzuki, Osamu; Ishizaki, Kanjiro.

    1987-01-01

    Purpose: To obtain a vessel of a reduced weight and with no external leaching of radioactive materials. Constitution: The vessel main body is constituted, for example, with light weight concretes or foamed concretes, particularly, foamed concretes containing fine closed bubbles in the inside. Then, layers having dense texture made of synthetic resin such as polystylene, vinylchloride resin, etc. or metal plate such as stainless plate are integrally disposed to the inner surface of the vessel main body. The cover member also has the same structure. (Sekiya, K.)

  3. Safety against radioactive contamination

    International Nuclear Information System (INIS)

    Anon.

    1983-01-01

    The ALWIT anticontamination suit is briefly described, consisting of lasting antistatic ''NDMEX III''. It was specially developed for the fire brigade who are exposed to a particular kind of contamination while carrying out radiation measurements during fire fighting, rescue and clearing up work. The ALWIT suit reliably prevents radioactive contamination of the surface of the body while wearing a breathing apparatus, independent of the ambient air. Tightly fitting cuffs on the neck, arms and legs together with zippers placed behind prevent contamination even with extreme movement. (P.F.K.)

  4. Radioactive waste management

    International Nuclear Information System (INIS)

    Anon.

    1988-01-01

    The dossier published in this issue deals with all matters relating to radioactive waste management. It describes in detail the guidelines implemented by France in this field and provides a general overview of actions carried out at international level. The articles are assembled in several chapters, treating the following subjects: I. Upstream storage management. II. Storage (surface and underground). III. Research to back up the management program. There then follows a description of various processes and equipment developed by research laboratories and industrialists to provide, at the different stages, a number of operations required by the management programs [fr

  5. Radioactive colloids

    International Nuclear Information System (INIS)

    Bergqvist, L.

    1987-01-01

    Different techniques for the characterization of radioactive colloids, used in nuclear medicine, have been evaluated and compared. Several radioactive colloids have been characterized in vitro and in vivo and tested experimentally. Colloid biokinetics following interstitial or intravenous injection were evaluated with a scintillation camera technique. Lymphoscintigraphy with a Tc-99-labelled antimony sulphur colloid was performed in 32 patients with malignant melanoma in order to evaluate the technique. Based on the biokinetic results, absorbed doses in tissues and organs were calculated. The function of the reticuloendothelial system has been evaluated in rats after inoculation with tumour cells. Microfiltration and photon correlation spectroscopy were found to be suitable in determining activity-size and particle size distributions, respectively. Maximal lymph node uptake following subcutaneous injection was found to correspond to a colloid particle size between 10 and 50 nm. Lymphoscintigraphy was found to be useful in the study of lymphatic drainage from the primary tumour site in patients with malignant melanoma on the trunk. Quantitative analysis of ilio-inguinal lymph node uptake in patients with malignant melanoma on the lower extremities was, however, found to be of no value for the detection of metastatic disease in lymph nodes. High absorbed doses may be received in lymph nodes (up to 1 mGy/MBq) and at the injection site (about 10 mGy/MBq). In an experimental study it was found that the relative colloid uptake in bone marrow and spleen depended on the total number of intravenously injected particles. This may considerably affect the absorbed dose in these organs. (author)

  6. [Microbiological Aspects of Radioactive Waste Storage].

    Science.gov (United States)

    Safonov, A V; Gorbunova, O A; German, K E; Zakharova, E V; Tregubova, V E; Ershov, B G; Nazina, T N

    2015-01-01

    The article gives information about the microorganisms inhabiting in surface storages of solid radioactive waste and deep disposal sites of liquid radioactive waste. It was shown that intensification of microbial processes can lead to significant changes in the chemical composition and physical state of the radioactive waste. It was concluded that the biogeochemical processes can have both a positive effect on the safety of radioactive waste storages (immobilization of RW macrocomponents, a decreased migration ability of radionuclides) and a negative one (biogenic gas production in subterranean formations and destruction of cement matrix).

  7. Radioactivity of the JINR site environment

    International Nuclear Information System (INIS)

    Alenitskaya, S.I.; Bamblevskij, V.P.; Kargin, A.N.; Komochkov, M.M.

    1977-01-01

    The results of the study of the existing levels of enviromental radioactivity in the JINR region for 1971-1975; content of radioactive products in the grass and surface soil layer, levels of the total alpha - and beta-radioactivity of water of open reservoirs as well as the background of the gamma-radiation and charged particles are presented. The study testifies, that the operation of the JINR nuclear-physical installations does not significantly affect the radioactivity of the environment which is mainly conditioned by the products of the natural origin and the global fallouts

  8. Storage depot for radioactive material

    International Nuclear Information System (INIS)

    Szulinski, M.J.

    1983-01-01

    Vertical drilling of cylindrical holes in the soil, and the lining of such holes, provides storage vaults called caissons. A guarded depot is provided with a plurality of such caissons covered by shielded closures preventing radiation from penetrating through any linear gap to the atmosphere. The heat generated by the radioactive material is dissipated through the vertical liner of the well into the adjacent soil and thus to the ground surface so that most of the heat from the radioactive material is dissipated into the atmosphere in a manner involving no significant amount of biologically harmful radiation. The passive cooling of the radioactive material without reliance upon pumps, personnel, or other factor which might fail, constitutes one of the most advantageous features of this system. Moreover this system is resistant to damage from tornadoes or earthquakes. Hermetically sealed containers of radioactive material may be positioned in the caissons. Loading vehicles can travel throughout the depot to permit great flexibility of loading and unloading radioactive materials. Radioactive material can be shifted to a more closely spaced caisson after ageing sufficiently to generate much less heat. The quantity of material stored in a caisson is restricted by the average capacity for heat dissipation of the soil adjacent such caisson

  9. Radioactivity in the hydrologic environment

    International Nuclear Information System (INIS)

    Werner, L.B.

    1969-01-01

    Certain proposed uses of nuclear explosives for peaceful purposes will introduce radioactive debris into the natural hydrologic environment. Consideration must therefore be given in each situation to the extent and significance to man of resulting radioactively contaminated water. For contained underground detonations, space-time - concentration predictions of radioactive materials in ground water are dependent on several factors: radionuclide production and initial distribution, radioactive decay, sorption on geologic materials, and dispersion during hydrologic transport. For uncontained (cratering) detonations, other aspects of the hydrologic cycle, particularly rainfall, and watershed characteristics must be considered. Programs sponsored principally by the U.S. Atomic Energy Commission have investigated these factors. Examination of their net effects on radioactivity concentration in water shows that areas if any, underlain by water exceeding permissible concentrations tend first to increase in size, then decrease, and finally disappear. Hydrologic processes at the surface remove or redistribute radioactive debris deposited on a watershed to other locations. Where sufficient information is available, predictions of location and concentration of radionuclides in natural waters can be made. Any potentially hazardous conditions arising from a particular detonation can then be evaluated. (author)

  10. Radioactivity in the hydrologic environment

    Energy Technology Data Exchange (ETDEWEB)

    Werner, L B [Isotopes, Inc., Palo Alto, CA (United States)

    1969-07-01

    Certain proposed uses of nuclear explosives for peaceful purposes will introduce radioactive debris into the natural hydrologic environment. Consideration must therefore be given in each situation to the extent and significance to man of resulting radioactively contaminated water. For contained underground detonations, space-time - concentration predictions of radioactive materials in ground water are dependent on several factors: radionuclide production and initial distribution, radioactive decay, sorption on geologic materials, and dispersion during hydrologic transport. For uncontained (cratering) detonations, other aspects of the hydrologic cycle, particularly rainfall, and watershed characteristics must be considered. Programs sponsored principally by the U.S. Atomic Energy Commission have investigated these factors. Examination of their net effects on radioactivity concentration in water shows that areas if any, underlain by water exceeding permissible concentrations tend first to increase in size, then decrease, and finally disappear. Hydrologic processes at the surface remove or redistribute radioactive debris deposited on a watershed to other locations. Where sufficient information is available, predictions of location and concentration of radionuclides in natural waters can be made. Any potentially hazardous conditions arising from a particular detonation can then be evaluated. (author)

  11. Radioactive elements in Pennsylvania waters

    International Nuclear Information System (INIS)

    Rose, A.W.

    1990-01-01

    The first recognition of radioactive elements in natural waters dates back many years, but interest has accelerated in recent years with the advent of concern about the health effects of radioactivity. At the present time, extensive monitoring of public water supplies for radioactive substances is mandated by federal and state law, and monitoring near nuclear facilities is required by federal regulations, so that a great deal of information is accumulating on the amount and distribution of radioactivity in natural waters. These results reveal that small amounts of radioactive elements are universally present in natural waters, and that the concentration vary over an appreciable range as a result of natural processes and human activities. The purpose of this paper is to summarize the origin, behavior, abundance and hazard of the main radioactive species in Pennsylvania surface and ground waters. This treatment is intended to provide background to the interested reader in comprehending questions such as the hazard of radon in homes with private wells and pollution related to the nuclear power cycle

  12. The radioactivity of the sea

    International Nuclear Information System (INIS)

    Walker, M.I.; Rose, K.S.B.

    1990-01-01

    The radioactivity in the world's surface sea water averages 13.6 Bq/kg of water. Over 88% of this activity arises from a single natural radionuclide, 40 K, and 7% of the remainder results from nuclear weapon test fallout. Variations in the radioactivity occur due to changes in salinity, weapon test fallout and discharges of artificial radionuclides, and are examined here on the basis of published measurements. The most radioactive sea identified by these measurements is the Dead Sea, which averages 178 Bq/kg due to its high salinity. Other enclosed, highly saline waters can be expected to have similar levels. The radioactivity in open seas varies within a much narrower range, generally within 20% of the world average. The highest averages are found in the Persian Gulf (22 Bq/kg), the Red Sea (15 Bq/kg) and the Eastern Mediterranean (14.6 Bq/kg). The Irish Sea averaged 13.7 Bq/kg in 1987, with the effect of the Sellafield discharges being partly offset by lower than average salinity. Although higher levels occurred in the Irish Sea during the 1970s when the Sellafield discharges were higher, the average level has always been much less than that in the Dead Sea, so that the Irish Sea has never been the most radioactive sea in the world. Exceptionally low levels of radioactivity (4 Bq/kg) occur in the Baltic Sea due to dilution by fresh water. (author)

  13. MIMETISME ET IMITATION : UNE REVUE DE LA LITTERATURE

    African Journals Online (AJOL)

    l‟imitation «des idées pures», mais aussi l‟existence d‟un type de protection de .... gion qui diffuse les caractéristiques de la mode d‟une organisation à une autre. ... d‟amélioration des performances mais par besoin de légitimité. La.

  14. Une sémiotique à refaire?

    Directory of Open Access Journals (Sweden)

    Eric Landowski

    2013-12-01

    Full Text Available Le récit, c’est ce qui nous sert à donner un peu de signification et de valeur à la vie, en dépit de ce qu’elle peut avoir d’insignifiant par sa monotonie ou d’insensé par son aspect chaotique. Mais indépendamment des significations portées les récits, il nous arrive parfois, face à autrui, à une oeuvre, à un paysage, d’être saisis par la présence d’un sens qui s’impose à notre intuition bien qu’il n’émane d’aucun discours constitué. Ce sens second, toute une littérature, de Proust à Musil, de Svevo à Woolf, s’est employée à le dire en inventant les formes d’écriture de ce qu’on peut appeler le discours de l’expérience. Distinct du vécu, ce discours a le pouvoir d’en capter le mouvement en restituant la dynamique du rapport aux choses, à autrui, à soi-même sur laquelle se fonde l’expérience du sens dans son émergence en acte. Pour construire une sémiotique qui permette d’en rendre compte, ni la grammaire narrative standard ni ses prolongements relatifs aux passions et à la tensivité ne fournissent les instruments nécessaires. Il convient donc de compléter l’appareil théorique dont nous disposons. C’est ce qui justifie le réexamen critique des notions de narrativité et de discursivité auquel procède cet article, ainsi que la proposition finale d’un modèle tenant compte de la diversité des régimes possibles de production du sens dans l’interaction.

  15. Radioactive waste problems in Russia

    International Nuclear Information System (INIS)

    Bridges, O.; Bridges, J.W.

    1995-01-01

    The collapse of the former Soviet Union, with the consequent shift to a market driven economy and demilitarisation, has had a profound effect on the nuclear and associated industries. The introduction of tighter legislation to control the disposal of radioactive wastes has been delayed and the power and willingness of the various government bodies responsible for its regulation is in doubt. Previously secret information is becoming more accessible and it is apparent that substantial areas of Russian land and surface waters are contaminated with radioactive material. The main sources of radioactive pollution in Russia are similar to those in many western countries. The existing atomic power stations already face problems in the storage and safe disposal of their wastes. These arise because of limited on site capacity for storage and the paucity of waste processing facilities. Many Russian military nuclear facilities also have had a sequence of problems with their radioactive wastes. Attempts to ameliorate the impacts of discharges to important water sources have had variable success. Some of the procedures used have been technically unsound. The Russian navy has traditionally dealt with virtually all of its radioactive wastes by disposal to sea. Many areas of the Barents, Kola and the Sea of Japan are heavily contaminated. To deal with radioactive wastes 34 large and 257 small disposal sites are available. However, the controls at these sites are often inadequate and illegal dumps of radioactive waste abound. Substantial funding will be required to introduce the necessary technologies to achieve acceptable standards for the storage and disposal of radioactive wastes in Russia. (author)

  16. Well bore Flow Treatment Used to Predict Radioactive Brine Releases to the Surface from Future Drilling Penetrations into the Waste Isolation Pilot Plant (WIPP), New Mexico, USA

    International Nuclear Information System (INIS)

    Brien, D.G.O.; Stoelzel, D.M.; Hadgu, T.

    1999-01-01

    The Waste Isolation Pilot Plant (WIPP) is the U.S. Department of Energy's (DOE) mined geologic repository in southeastern New Mexico, USA.This site is designed for the permanent burial of transuranic radioactive waste generated by defense related activities.The waste produces gases when exposed to brine. This gas generation may result in increased pressures over time. Therefore, a future driller that unknowingly penetrates through the site may experience a blowout. This paper describes the methodology used to predict the resultant volumes of contaminated brine released

  17. What to do with radioactive wastes?

    International Nuclear Information System (INIS)

    2006-01-01

    This power point presentation (82 slides) gives information on what is a radioactive waste, radioactivity and historical review of radioactivity, radioactive period, natural radioactivity (with examples of data), the three main radiation types (α, β, γ), the origin of radioactive wastes (nuclear power, research, defense, other), the proportion of radioactive wastes in the total of industrial wastes in France, the classification of nuclear wastes according to their activity and period, the quantities and their storage means, the 1991 december 30 law (France) related to the radioactive waste management, the situation in other countries (Germany, Belgium, Canada, USA, Finland, Japan, Netherlands, Sweden, Switzerland), volume figures and previsions for the various waste types in 2004, 2010 and 2020, the storage perspectives, the French national debate on radioactive waste management and the objective of perpetuated solutions, the enhancement of the public information, the 15 June 2006 law on a sustainable management of radioactive materials and wastes with three main axis (deep separation and transmutation, deep storage, waste conditioning and long term surface storage), and the development of a nuclear safety and waste culture that could be extended to other types of industry

  18. Environmental radioactivity. Measurement and monitoring

    International Nuclear Information System (INIS)

    2009-11-01

    The contribution on environmental radioactivity covers the following issues: natural and artificial radioactivity; continuous monitoring of radioactivity; monitoring authorities and measurement; radioactivity in the living environment; radioactivity in food and feeding stuff; radioactivity of game meat and wild-growing mushrooms; radioactivity in mines; radioactivity in the research center Rossendorf.

  19. Mise en place d'une base de données pour une modélisation ...

    African Journals Online (AJOL)

    Mise en place d'une base de données pour une modélisation hydrologique distribuée du bassin versant du Bandama (Côte d'Ivoire) : apport d'un modèle numérique d'altitude, de la télédétection et du SIG Physitel.

  20. L’entomophagie : une question de culture ?

    OpenAIRE

    Mignon, Jacques

    2002-01-01

    L’entomophagie consiste à consommer des insectes. Loin d’être une curiosité limitée à quelques peuplades, cette pratique se rencontre sur tous les continents à l’exception de l’Europe et de l’Amérique du Nord. Pour beaucoup d’Européens, la consommation d’insectes est vécue comme un comportement primitif et répugnant. Pourtant, l’expérience montre que, sensibilisés et informés, ces mêmes personnes oublient rapidement leurs tabous pour s’initier progressivement à l’entomophagie, découvrant par ...

  1. Vers une illusio sans illusion ?

    Directory of Open Access Journals (Sweden)

    Pascal Durand

    2011-09-01

    Full Text Available À Daniel Giovannangeli« Peu importe la direction du vent, le soleil va toujours là où il doit aller. »Proverbe congolais« Une carrière ne se propose aux lettres, mais on use du mot à la façon de lyriques célébrant le parcours de l’astre jusqu’à sa hauteur accoutumée — que, tout à l’heure, il va toucher — ascension pas avancement. »Mallarmé, ConfrontationDe l’illusio en général et de l’illusio littéraire en particulierPar stratégie, terme quelque peu abandonné ensuite, de même que celui d’inté...

  2. Method for electrolytic decontamination of radioactive contaminated metals

    International Nuclear Information System (INIS)

    Tanaka, Akio; Horita, Masami; Onuma, Tsutomu; Kato, Koji

    1991-01-01

    The invention relates to an electrolytic decontamination method for radioactive contaminated metals. The contaminated sections are eluted by electrolysis after the surface of a piece of equipment used with radioactive substances has been immersed in an electrolyte. Metal contaminated by radioactive substances acts as the anode

  3. Promotion d'une gouvernance foncière inclusive pour une ...

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

    ... de développer des outils et des stratégies qui facilitent l'accès et le contrôle des femmes sur le foncier; et de formuler des recommandations stratégiques et pratiques permettant une mise en œuvre effective des politiques et des stratégies de gouvernance foncière inclusive qui reconnaissent la place et le rôle de la femme ...

  4. 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

    'un coefficient de diffusion pour l'emetteur utilise et a la mesure eventuelle de la vitesse du courant au point ou la mesure est effectuee (dans le cas decrit, le lac Leman). Dans une seconde etape, en correlation avec une etude de geophysique concernant le probleme general des retombees radioactives, les auteurs ont utilise l'apport des retombees radioactives ayant pour origine les essais nucleaires atmospheriques (octobre 1961-janvier 1962). Des mesures de la radioactivite ont ete effectuees chaque jour sur des prelevements d'eau du lac Leman a des profondeurs de 0 m, 10 m, 20 m et sur un collecteur de retombees atmospheriques seches et humides. Malgre la complexite du regime des apports en fonction du temps, l'interpretation des diagrammes obtenus peut contribuer a resoudre le probleme du devenir des produits radioactifs dans les conditions de diffusion et de courants rencontrees. L'utilisation de la diffusion de produits radioactifs en tres faibles quantites et des differentes techniques de detection nucleaires a haute sensibilite actuellement disponibles peut conduire a une meilleure connaissance de la diffusion in situ et du mouvement des masses d'eaux naturelles. (author) [Spanish] En una primera etapa, los autores ha i provecado la difusion in situ de un emisor radiactivo, el sodio-22 en forma de Na{sup +}, de actividad muy baja (inferior al milicurie). La aplicacion de las leyes de la difusion a este caso facilita el calculo de la velocidad de difusion de la ''nube radiactiva''. Por consiguiente, el registro en funcion del tiempo de las actividades medidas con dos detectores gamma dispuestos de modo conveniente permite asignar un coeficiente de difusion ai emisor empleado y, eventualmente, evaluar la velocidad de la corriente en el punto en que se efectua la medicion (en el caso descrito, el lago Leman). En una segunda etapa, en relacion con un estudio geofisico del problema general de las precipitaciones radiactivas, los autores utilizaron la aportacion de las

  5. Radioactive tracer system to indicate drill bit wear or failure

    International Nuclear Information System (INIS)

    Fries, B.A.

    1975-01-01

    A radioactive tracer system for indicating drill bit wear or failure utilizing radioactive krypton 85 in clathrate form, in the form of water-soluble kryptonates, or dissolved grease, is described. Preferably the radioactive krypton is placed so that when drill bit wear or failure occurs, the radioactive krypton 85 is relased and effectively becomes diffused in the circulating drilling fluid. At the surface, the radioactive krypton 85 gas is separated from the circulating drilling fluid by gas-mud separating means and is transported as a gas to a counting chamber where an accurate radioactivity count of beta rays released from the krypton is obtained. (Patent Office Record)

  6. Electrodeless light source provided with radioactive material

    International Nuclear Information System (INIS)

    1979-01-01

    Radioactive materials are used to assist in starting a discharge in an electrodeless light source. The radioactive emissions predispose on the inner surface of the lamp envelope loosely bound charges which thereafter assist in initiating discharge. The radioactive material can be enclosed within the lamp envelope in gaseous or non-gaseous form. Preferred materials are krypton 85 and americium 241. In addition, the radioactive material can be dispersed in the lamp envelope material or can be a pellet imbedded in the envelope material. Finally, the radioactive material can be located in the termination fixture. Sources of alpha particles, beta particles, or gamma rays are suitable. Because charges accumulate with time on the inner surface of the lamp envelope, activity levels as low as 10 -8 curie are effective as starting aids. (Auth.)

  7. Radioactive waste processing method

    International Nuclear Information System (INIS)

    Ando, Ken-ichi; Kawamura, Hideki; Takeuchi, Kunifumi.

    1997-01-01

    Base rock is dug in a substantially cylindrical shape, bentonite blocks in an amount for a predetermined lift are disposed on the inner side of the dug wall surfaces. Concrete blocks constituting a structure of an underground silo are disposed at the inner side. Barrier blocks are disposed to the inner side thereof, and vessels incorporated with radioactive wastes are disposed to the inner side. The bentonite disposed to the inner side of the dug wall surfaces, the concrete structure of the underground silo and the barrier members are divided in the vertical direction into a plurality of blocks, and these blocks are stacked successively from the lowermost layer together with the containing vessels of the radioactive wastes, and after stacking them to a predetermined height, a filler is filled up to the circumference of the vessels. With such a constitution, the underground silo is not fallen down or vibrated even upon occurrence of an earthquake. In addition, bending stresses are scarcely caused thereby making reinforcement of iron reinforcing materials unnecessary. Accordingly, the sealing performance is improved, and processing cost is reduced. (T.M.)

  8. Apparatus for measuring radioactive emissions

    International Nuclear Information System (INIS)

    Bohme, R.C.; Lazerson, M.M.

    1984-01-01

    Apparatus for measuring radioactive emissions from moving radioactive material comprises at least one radiation detector in a housing serving as a first radiation shield and in which at least one groove is formed to expose at least a portion of a receptor surface of the detector. The groove extends transverse to the direction of movement of the material over the detector. A second radiation shield may be located between at least a portion of the first shield and the detector. The material of the second shield is inherently less contaminated and emits secondary excitation radiation of lower energy than the first material. (author)

  9. Radioactive gas solidification treatment device

    International Nuclear Information System (INIS)

    Igarashi, Ryokichi; Watanabe, Yu; Seki, Eiji.

    1992-01-01

    In a radioactive gas solidification treatment device by using sputtering, spiral pipelines are disposed with a gap therebetween for cooling an ion injection electrode by passing cooling water during operation of the solidification treatment. During the operation of the solidification treatment, cooling water is passed in the pipelines to cool the ion injection electrode. During storage, a solidification vessel is cooled by natural heat dissipation from an exposed portion at the surface of the solidification vessel. Accordingly, after-heat of radioactive gas solidified in a metal accumulation layer can be removed efficiently, safely and economically to improve the reliability. (N.H.)

  10. Low-level radioactive wastes

    International Nuclear Information System (INIS)

    Garbay, H.; Chapuis, A.M.

    1988-01-01

    During dismantling operations of nuclear facilities radioctive and non radioactive wastes are produced. The distinction between both kinds of wastes is not easy. In each dismantling operation special care and rules are defined for the separation of wastes. Each case must be separately studied. The volume and the surface activites are analyzed. Part of the wastes had been disposed in a public environment. The regulations, the international recommendations, thetheoretical and experimental investigations in this field are presented. A regulation principle and examples of radioactivity limits, on the basis of international recommendations, are provided. Those limits are calculated from individual radiation dose that may reach human beings [fr

  11. Disposal of radioactive wastes

    International Nuclear Information System (INIS)

    Blomeke, J.O.

    1979-01-01

    Radioactive waste management and disposal requirements options available are discussed. The possibility of beneficial utilization of radioactive wastes is covered. Methods of interim storage of transuranium wastes are listed. Methods of shipment of low-level and high-level radioactive wastes are presented. Various methods of radioactive waste disposal are discussed

  12. Transport of radioactive substances

    International Nuclear Information System (INIS)

    2014-12-01

    The report on the transport of radioactive substances covers the following topics: facts on radioactive materials transport, safety of the transport of radioactive substances, legal regulations and guidelines: a multiform but consistent system, transport of nuclear fuels, safety during the transport of nuclear fuel, future transport of spent fuel elements and high-level radioactive wastes in Germany.

  13. A simulation of the transport and fate of radon-222 derived from thorium-230 low-level waste in the near-surface zone of the Radioactive Waste Management Site in Area 5 of the Nevada Test Site

    International Nuclear Information System (INIS)

    Lindstrom, F.T.; Cawlfield, D.E.; Donahue, M.E.; Emer, D.F.; Shott, G.J.

    1993-12-01

    US Department of Energy (DOE) Order 5820.2A (DOE, 1988) requires performance assessments on all new and existing low-level radioactive waste (LLW) disposal sites. An integral part of performance assessment is estimating the fluxes of radioactive gases such as radon-220 and radon-222. Data needs pointed out by mathematical models drive site characterization. They provide a logical means of performing the required flux estimations. Thorium-230 waste, consisting largely of thorium hydroxide and thorium oxides, has been approved for disposal in shallow trenches and pits at the LLW Radioactive Waste Management Site in Area 5 of the Nevada Test Site. A sophisticated gas transport model, CASCADR8 (Lindstrom et al., 1992b), was used to simulate the transport and fate of radon-222 from its source of origin, nine feet below a closure cap of native soil, through the dry alluvial earth, to its point of release into the atmosphere. CASCADR8 is an M-chain gas-phase radionuclide transport and fate model. It has been tailored to the site-specific needs of the dry desert environment of southern Nevada. It is based on the mass balance principle for each radionuclide and uses gas-phase diffusion as well as barometric pressure-induced advection as its main modes of transport. CASCADR8 uses both reversible and irreversible sorption kinetic rules as well as the usual classical Bateman (1910) M-chain decay rules for its kinetic processes. Worst case radon-222 gas-phase concentrations, as well as surface fluxes, were estimated over 40 days. The maximum flux was then used in an exposure assessment model to estimate the total annual dose equivalent received by a person residing in a standard 2500-square-foot house with 10-foot walls. Results are described

  14. Removal of radioactive cesium from surface soils solidified using polyion complex. Rapid communication for decontamination test at Iitate-mura in Fukushima Prefecture

    International Nuclear Information System (INIS)

    Naganawa, Hirochika; Yanase, Nobuyuki; Mitamura, Hisayoshi; Nagano, Tetsushi; Yoshida, Zenko; Kumazawa, Noriyuki; Saitoh, Hiroshi; Kashima, Kaoru; Fukuda, Tatsuya; Tanaka, Shun-ichi

    2011-01-01

    We tried the decontamination of surface soils for three types of agricultural land at Nagadoro district of Iitate-mura (village) in Fukushima Prefecture, which is highly contaminated by deposits of radionuclides from the plume released from the Fukushima Daiichi nuclear power plant. The decontamination method consisted of the peeling of surface soils solidified using a polyion complex, which was formed from a salt solution of polycations and polyanions. Two types of polyion complex solution were applied to an upland field in a plastic greenhouse, a pasture, and a paddy field. The decontamination efficiency of the surface soils reached 90%, and dust release was effectively suppressed during the removal of surface soils. (author)

  15. Radioactive waste management

    International Nuclear Information System (INIS)

    Kawakami, Yutaka

    2008-01-01

    Radioactive waste generated from utilization of radioisotopes and each step of the nuclear fuel cycle and decommissioning of nuclear facilities are presented. On the safe management of radioactive waste management, international safety standards are established such as ''The Principles of Radioactive Waste Management (IAEA)'' and T he Joint Convention on the Safety of Radioactive Waste Management . Basic steps of radioactive waste management consist of treatment, conditioning and disposal. Disposal is the final step of radioactive waste management and its safety is confirmed by safety assessment in the licensing process. Safety assessment means evaluation of radiation dose rate caused by radioactive materials contained in disposed radioactive waste. The results of the safety assessment are compared with dose limits. The key issues of radioactive waste disposal are establishment of long term national strategies and regulations for safe management of radioactive waste, siting of repository, continuity of management activities and financial bases for long term, and security of human resources. (Author)

  16. Character and levels of radioactive contamination of underground waters at Semipalatinsk test site

    Energy Technology Data Exchange (ETDEWEB)

    Subbotin, S.; Lukashenko, S.; Turchenko, Y. [Institute of radiation safety and ecology (Kazakhstan)

    2014-07-01

    According to the data of RK government commission, 470 explosions have been set off at the Semipalatinsk Test Site (STS), inclusive of 26 surface, 90 in the air and 354 underground nuclear explosions (UNE), 103 of those have been conducted in tunnels and 251 - in boreholes. Underground nuclear explosions have been conducted at STS in horizontal mines, called - 'tunnels' ('Degelen' test site) and vertical mines called 'boreholes' ('Balapan' and 'Sary-Uzen' test sites). Gopher cavities of boreholes and tunnels are in different geotechnical conditions, that eventually specify migration of radioactive products with underground waters. Central cavities of UNE in holes are located significantly below the level of distribution of underground water. High temperature remains for a long time due to presence of overlying rock mass. High temperatures contribute to formation of thermal convection. When reaching the cavity, the water heat up, dissolve chemical elements and radionuclides and return with them to the water bearing formation. In the major part of 'Balapan' site for underground water of regional basin is characterized by low concentrations of radionuclides. High concentrations of {sup 137}Cs in underground water have been found only in immediate vicinity to 'warfare' boreholes. Formation of radiation situation in the 'Balapan' test site area is also affected by local area of underground water discharge. It is located in the valley of Shagan creek, where the concentration of {sup 3}H reaches 700 kBq/l. Enter of underground water contaminated with tritium into surface water well continue. In this case it is expected that tritium concentration in discharge zone can significantly change, because this migration process depends on hydro geological factors and the amount of atmospheric precipitation. Central cavities of nuclear explosions, made in tunnels, are above the level of underground

  17. Impact of surface water recharge on the design of a groundwater monitoring system for the Radioactive Waste Management Complex, Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Wood, T.R.

    1990-01-01

    Recent hydrogeologic studies have been initiated to characterize the hydrogeologic conditions at the Radioactive Waste Management Complex (RWMC) at the Idaho National Engineering Laboratory (INEL). Measured water levels in wells penetrating the Snake River Plain aquifer near the RWMC and the corresponding direction of flow show change over time. This change is related to water table mounding caused by recharge from excess water diverted from the Big Lost River for flood protection during high flows. Water levels in most wells near the RWMC rise on the order of 10 ft (3 m) in response to recharge, with water in one well rising over 60 ft (18 m). Recharge changes the normal south-southwest direction of flow to the east. Design of the proposed groundwater monitoring network for the RWMC must account for the variable directions of groundwater flow. 11 refs., 9 figs., 2 tabs

  18. Radioactivity in surface and coastal waters of the British Isles, 1976. Part 2. Areas other than the Irish Sea and its environs

    International Nuclear Information System (INIS)

    Mitchell, N.T.

    1978-01-01

    The establishments from which discharges are made are listed: they comprise sites of the United Kingdom Atomic Energy Authority, the Radiochemical Centre and the Ministry of Defence, as well as nuclear power stations operated by the Central Electricity Generating Board and the South of Scotland Electricity Board. Much of the environmental data in this report is the direct result of the Fisheries Radiobiological Laboratory's (FRL) control monitoring activities in relation to these discharges - that is monitoring to show whether public radiation exposure from them remains within the prescribed limits laid down within national policy. As such it is independent of the often similar environmental monitoring done by the operators as a condition of their authorizations. It is supplemented by some of the results of the Laboratory's extensive programme of environmental research where summaries of those results can be useful in providing a more comprehensive account of the situations being described. Tables are presented showing the radioactivity in environmental materials around each site. (author)

  19. Natural Radioactivity of U-238, Th-232 and K-40 in Surface Soil of Baghdad, Nahrain and Al-Mustansiriyah University in Iraq

    International Nuclear Information System (INIS)

    Ridha, A.A.; Mutter, M.M.; Salim, M.D.

    2015-01-01

    The study of natural radioactivity in public universities soil is very important because of containing a large numbers of students and personnel in small areas and for long periodic times, especially the centers and gathering students areas. So it was chosen the most important universities in Baghdad city according with the students density, which is Baghdad and Nahrain University in Al-Jadriyah region in addition to Al-Mustansiriyah University in Palestine street region. Thirteen soil samples collected from these regions to estimate the radiological impact to the dweller, the concentrations of 238 U, 232 Th and 40 K present in the soil samples were analyzed using HPGe as Gamma-spectrometry. The results showed that the average radioactivity of 238 U is 26.262±4.52 Bq/ kg, for 232 Th is equal to 24.860±4.03 Bq/ kg and for 40 K is 293.706±16.62 Bq/ kg. Thus, the values of specific activity of 238 U, 232 Th and 40 K for all soil samples are in acceptable values of the worldwide average. The maximum value for Ra eq is 119.727±10.94 Bq/ kg recorded in sample (Bag2), with an average value of 76.938±8.44 Bq/ kg. All soil samples have Ra eq value below the 247 Bq/ kg (Iraqi permissibility limit). In addition to radium equivalent, the absorbed gamma dose rate (D), outdoor annual effective dose and hazard indices are calculated in this work and show low values compared with permissible limits. (author)

  20. Radioactive pollution

    International Nuclear Information System (INIS)

    Pohl, R.O.

    1976-01-01

    The widely published claims that the public health effects resulting from routine emissions are between 0.01 and 0.1 serious health effects per gigawattyear, and hence are at least a thousand times smaller than those resulting from air pollution by the burning of coal, cannot be true, for two reasons. The authors of these claims have ignored at least two of the more important isotopes, radon-222 and carbon-14, which are presently released to the environment, and thus contribute greatly to the health impact of nuclear energy. The health effects calculated in the earlier work cover only those which occur during the year in which the energy is generated. This means, figuratively speaking, that the authors have confused an annual installment payment with the full cost. This is unacceptable. The contribution to the health impact of nuclear energy arising from the single isotopic species radon-222 emanating from the mill tailings is estimated to 400 lung cancer deaths/GW(e)y, larger even than the most pessimistic estimates of the health impact of energy from coal through atmospheric pollution. We have no assurance that other long-lived isotopes do not contribute comparable amounts to the health impact of nuclear energy. The discussion of the health impact of radon-222 raises the fundamental moral question--how far into the future our responsibility extends. If such a long-termresponsibility is rejected, then we must at least try to predict the environmental buildup of radioactive pollutants, in order to avoid unacceptable and irreversible levels of radiation dose rate. The potential health consequences from long-lived radioisotopes seem to have been largely ignored so far, and should be explored in detail

  1. Nucléation, ascension et éclatement d'une bulle de champagne

    Science.gov (United States)

    Liger-Belair, G.

    2006-03-01

    People have long been fascinated by bubbles and foams dynamics, and since the pioneering work of Leonardo da Vinci in the early 16th century, this subject has generated a huge bibliography. However, only quite recently, much interest was devoted to bubbles in Champagne wines and carbonated beverages. Since the time of the benedictine monk dom Pierre Perignon (1638-1715), champagne is the wine of celebration. This fame is largely linked to the elegance of its effervescence and foaming properties. In this book, the latest results about the chemical physics behind the bubbling properties of Champagne and sparkling wines are collected and fully illustrated. The first chapter is devoted to the history of champagne and to a presentation of the tools of the physical chemistry of interfaces needed for a whole comprehension of the book. Then, the three main steps of a fleeting champagne bubble's life are presented in chronological order, that is, the bubble nucleation on the glass wall (Chap.2), the bubble ascent and growth through the liquid matrix (Chap.3), and the bursting of bubbles at the liquid surface (Chap.4), which constitutes the most intriguing, functional, and visually appealing step. L'objectif général de ce travail consacré à l'étude des processus physicochimiques liés à l'effervescence des vins de Champagne était de décortiquer les différentes étapes de la vie d'une bulle de champagne en conditions réelles de consommation, dans une flûte. Nous résumons ci-après les principaux résultats obtenus pour chacune des étapes de la vie de la bulle, depuis sa naissance sur les parois d'une flûte, jusqu'à son éclatement en surface. Nucléation À l'aide d'une caméra rapide munie d'un objectif de microscope, nous avons pu mettre à mal une idée largement répandue. Ce ne sont pas les anfractuosités de la surface du verre ou de la flûte qui sont responsable de la nucléation hétérogène des bulles, mais des particules adsorbées sur les parois du

  2. Underground radioactive waste disposal concept

    International Nuclear Information System (INIS)

    Frgic, L.; Tor, K.; Hudec, M.

    2002-01-01

    The paper presents some solutions for radioactive waste disposal. An underground disposal of radioactive waste is proposed in deep boreholes of greater diameter, fitted with containers. In northern part of Croatia, the geological data are available on numerous boreholes. The boreholes were drilled during investigations and prospecting of petroleum and gas fields. The available data may prove useful in defining safe deep layers suitable for waste repositories. The paper describes a Russian disposal design, execution and verification procedure. The aim of the paper is to discuss some earlier proposed solutions, and present a solution that has not yet been considered - lowering of containers with high level radioactive waste (HLW) to at least 500 m under the ground surface.(author)

  3. Old radioactive waste storage sites

    International Nuclear Information System (INIS)

    2008-01-01

    After a recall of the regulatory context for the management of old sites used for the storage of radioactive wastes with respect with their activity, the concerned products, the disposal or storage type, this document describes AREVA's involvement in the radioactive waste management process in France. Then, for the different kinds of sites (currently operated sites having radioactive waste storage, storage sites for uranium mineral processing residues), it indicates their location and name, their regulatory status and their control authority, the reference documents. It briefly presents the investigation on the long term impact of uranium mineral processing residues on health and environment, evokes some aspects of public information transparency, and presents the activities of an expertise group on old uranium mines. The examples of the sites of Bellezane (uranium mineral processing residues) and COMURHEX Malvesi (assessment of underground and surface water quality at the vicinity of this installation) are given in appendix

  4. Envenimation mortelle par morsure de serpent chez une femme ...

    African Journals Online (AJOL)

    Les auteurs rapportent un cas de morsure de serpent au niveau de la face chez une femme enceinte, dont l'évolution a été marquée par l'installation d'un oedème cervico-facial nécessitant une trachéotomie en urgence, et une mort foetale in utero avec troubles de l'hémostase responsable du décès maternel dans un ...

  5. Surveillance of the environmental radioactivity

    International Nuclear Information System (INIS)

    Schneider, Th.; Gitzinger, C.; Jaunet, P.; Eberbach, F.; Clavel, B.; Hemidy, P.Y.; Perrier, G.; Kiper, Ch.; Peres, J.M.; Josset, M.; Calvez, M.; Leclerc, M.; Leclerc, E.; Aubert, C.; Levelut, M.N.; Debayle, Ch.; Mayer, St.; Renaud, Ph.; Leprieur, F.; Petitfrere, M.; Catelinois, O.; Monfort, M.; Baron, Y.; Target, A.

    2008-01-01

    The objective of these days was to present the organisation of the surveillance of the environmental radioactivity and to allow an experience sharing and a dialog on this subject between the different actors of the radiation protection in france. The different presentations were as follow: evolution and stakes of the surveillance of radioactivity in environment; the part of the European commission, regulatory aspects; the implementation of the surveillance: the case of Germany; Strategy and logic of environmental surveillance around the EDF national centers of energy production; environmental surveillance: F.B.F.C. site of Romans on Isere; steps of the implementation 'analysis for release decree at the F.B.F.C./C.E.R.C.A. laboratory of Romans; I.R.S.N. and the environmental surveillance: situation and perspectives; the part of a non institutional actor, the citizenship surveillance done by A.C.R.O.; harmonization of sampling methods: the results of inter operators G.T. sampling; sustainable observatory of environment: data traceability and samples conservation; inter laboratories tests of radioactivity measurements; national network of environmental radioactivity measurement: laboratories agreements; the networks of environmental radioactivity telemetry: modernization positioning; programme of observation and surveillance of surface environment and installations of the H.A.-M.A.V.L. project (high activity and long life medium activity); Evolution of radionuclides concentration in environment and adaptation of measurements techniques to the surveillance needs; the national network of radioactivity measurement in environment; modes of data restoration of surveillance: the results of the Loire environment pilot action; method of sanitary impacts estimation in the area of ionizing radiations; the radiological impact of atmospheric nuclear tests in French Polynesia; validation of models by the measure; network of measurement and alert management of the atmospheric

  6. An international peer review of the programme for evaluating sites for near surface disposal of radioactive waste in Lithuania. Report of the IAEA International Review Team

    International Nuclear Information System (INIS)

    2006-12-01

    Lithuania's national Radioactive Waste Management Agency (RATA) is mandated by national legislation to find a disposal solution for radioactive waste arising mainly from the operation and decommissioning of the Ignalina nuclear power plant. A key step in the process of obtaining a disposal solution is to identify potential sites for detailed consideration. The RATA has completed this first step and is now directing a programme for detailed investigation of these sites. In this context, the RATA requested that the IAEA, on the basis of its statutory mandate to establish safety standards and provide for their application, conduct a peer review of the safety of the proposed disposal concept. The objective of the peer review, carried out in December 2005, was to provide an independent assessment of the safety related aspects of the sites under consideration on the basis of international safety standards and applicable national standards. The review also considered the feasibility of the proposed reference design and its suitability for the local conditions. The peer review provides an independent opinion as to whether the RATA's siting and site characterization programme is consistent with international standards and agrees with good practice in other national disposal programmes. Peer reviews are increasingly being acknowledged as an important component in building broader stakeholder confidence in the safety of facilities. For this reason, an increase in their number and frequency is anticipated. The coming into force of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management has also focused attention on the demonstration of the safety of waste management facilities. This report presents the consensus view of the international group of experts convened by the IAEA to carry out the review. The findings and recommendations of the Review Team were grouped under six topics considered to be of fundamental importance

  7. Scintillation detector for dosing unknown {beta} emitters deposited on large-surface filters (1963); Detecteur a scintillation pour la dosimetrie d'emetteurs beta inconnus deposes sur filtre de grande surface (1963)

    Energy Technology Data Exchange (ETDEWEB)

    Soudain, G; Cercy, J; Geoffre, B [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1963-07-01

    The apparatus described has been specially studied for direct counting, using a plastic scintillator, of unknown emitters occurring in atmospheric samples collected on large-surface filters (10 cm diameter). In view of the fairly large contribution of low-energy fission products to the overall {beta}-activity of radio-active fallout, the adjustments have been chosen so as to obtain the best yield in an energy range as wide as possible. This has led to the acceptance of a certain background noise which is later reduced by the anti-coincidence method. The quality of the apparatus depends largely on the uniformity of the photocathode in the photomultiplier used. The counter which was built had a counting efficiency for a 10 cm diameter source of 30 per cent for S-35, 88 per cent for P-32, 45 per cent for unknown emitters and a background noise of 56 cpm. (authors) [French] L'appareil decrit a ete specialement etudie pour le comptage direct, a l'aide d'un scintillateur plastique d'emetteurs inconnus recueillis dans les prelevements atmospheriques sur des filtres de grande surface (10 cm de diametre). Etant donne la participation assez importante des produits de fission de faible energie a l'activite globale {beta} des retombees radioactives, les reglages ont ete choisis de maniere a obtenir le meilleur rendement dans une gamme d'energie aussi etendue que possible. Cela a conduit a admettre un certain bruit de fond que l'on reduit ensuite par la methode d'anticoincidence. La qualite de l'appareil depend en grande partie de l'uniformite de la photocathode du photomultiplicateur utilise. Le compteur que l'on a construit possede une efficacite de comptage pour une source de 10 cm de diametre de 30 pour cent pour {sup 35}S, 88 pour cent pour {sup 32}P, 45 pour des emetteurs {beta} inconnus et un bruit de fond de 56 cpm. (auteurs)

  8. Quand la biopsie cutanee peut etiqueter une epilepsie

    Directory of Open Access Journals (Sweden)

    Taoufiq Harmouch

    2011-10-01

    Full Text Available La maladie de Lafora (ML represente une forme rare et grave d�epilepsie myoclonique progressive. C�est une affection a transmission autosomique recessive, heterogene sur le plan genetique. Nous rapportons le cas d�une adolescente de 16 ans, issue de parents consanguins de premier degre, qui presente depuis l�age de 14 ans des crises d�epilepsie et des myoclonies. L'examen neurologique a montre un syndrome cerebelleux et une deterioration intellectuelle. La biopsie cutanee etait indispensable pour orienter le diagnostic. La ML a un pronostic constamment fatal. L�etude histologique confirme le diagnostic et l�etude moleculaire peut aider a etablir un conseil genetique.

  9. Echographie devant une metrorragie du premier trimestre de ...

    African Journals Online (AJOL)

    Echographie devant une metrorragie du premier trimestre de grossesse sur uterus bicorne a issue favorable. Vaginal bleeding in a pregnant woman with a bicornuate uterus, ultrasound finding and favourable outcome.

  10. Une histoire de la physique moderne

    CERN Document Server

    Guillaud, Jean-Paul

    2010-01-01

    Vous étiez noyé dans les théorèmes et perdu dans vos cours de physique ? Et pourtant les informations sur les grands laboratoires de recherche explorant la matière vous intéressent et vous souhaiteriez en comprendre les enjeux ? Alors cet ouvrage de vulgarisation scientifique est pour vous. Ce livre dresse le plus simplement possible un panorama de la physique moderne en abordant : la relativité restreinte, la relativité générale, la physique quantique. Vous verrez : cette science n'est pas si hermétique et la profession de physicien est passionnante. La physique est au cœur de l'actualité avec la mise en service du nouvel accélérateur du CERN, le LHC, qui a fait la une de tous les médias. Ce livre prépare le lecteur à apprécier comme il se doit les découvertes à venir.

  11. L'univers des particules une introduction

    CERN Document Server

    Diu, Bernard

    2017-01-01

    Au début du XXe siècle, les scientifiques imaginaient que l'ensemble du monde était construit à partir de trois "particules élémentaires" (électron, proton, photon). Depuis, nous avons appris que notre univers contient un nombre considérable de particules - soit des corps individualisés d'extension réduite - de natures et de caractéristiques très diverses, qu'il serait illusoire de chercher à énumérer de manière formelle et systématique. C'est pourquoi le propos de ce livre suit une stratégie fondamentalement différente. Il s'organise autour de certaines propriétés générales que laissent apparaître l'observation et l'étude des particules dans leur existence et leur conduite primaire. Aussi, chacune des parties de cet ouvrage rassemble plusieurs chapitres de thèmes voisins, mais un sujet donné peut également être traité en divers endroits et, de ce fait, être abordé sous différents angles de manière complémentaire. De telles compositions et décompositions d'éléments proche...

  12. Vers une narratologie naturelle de la musique

    Directory of Open Access Journals (Sweden)

    Nicolas Marty

    2011-12-01

    Full Text Available Grâce à l’étude du modèle de la narratologie « naturelle » de Monika Fludernik, nous souhaitons montrer qu’il est possible d’envisager une narratologie « naturelle » de la musique, prenant en compte tous les phénomènes sémiotiques, sémantiques et narratifs présents dans l’écoute de la musique. Nous ouvrons de plus la question de la différence observable entre les « narrativisations » opérées par les musiciens experts et celles opérées par les non-experts.Following Monika Fludernik’s frame for a “natural” narratology, we wish to demonstrate that it is in fact possible to think of “natural” narratology for music, which would consider every semiotic, semantic and narrative phenomenon found in the listening of music. We then open the question of the apparent difference between music experts’ and non-experts’ “narrativizations”.

  13. Methods for studying the radioactive contamination of plants (1963); Methodes d'etude de la contamination radioactive des vegetaux (1963)

    Energy Technology Data Exchange (ETDEWEB)

    Coulon, R; Jeanmaire, L; Michon, G [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1963-07-01

    The authors first define the doctrine which led to the devising of a method for studying the radioactive pollution of plants, based on the use of simple techniques, having the possibility of being adapted for routine work, and so devised that each stage is proceeded with only if the preceding one justifies it. For each stage a study is effected comparing the results obtained by the use of more exact techniques. The second part describes in detail the techniques used. (authors) [French] Dans une premiere partie lea auteurs definissent la doctrine qui leur a permis d'elaborer une methode d'etude de la pollution radioactive des vegetaux, basee sur l'utilisation de techniques simples, se pretant au travail de serie et concues de telle maniere que chaque etape n'est abordee que si la precedente le justifie. Chaque etape fait l'objet d'une etude qui compare les resultats a ceux obtenue par des techniques plus precises. La deuxieme partie decrit dans le detail les techniques utilisees. (auteurs)

  14. Management of radioactive wastes

    International Nuclear Information System (INIS)

    2005-01-01

    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.)

  15. Radioactive wastes management

    International Nuclear Information System (INIS)

    Albert, Ph.

    1999-01-01

    This article presents the French way to deal with nuclear wastes. 4 categories of radioactive wastes have been defined: 1) very low-level wastes (TFA), 2) low or medium-wastes with short or medium half-life (A), 3) low or medium-level wastes with long half-life (B), and 4) high-level wastes with long half-life (C). ANDRA (national agency for the management of radioactive wastes) manages 2 sites of definitive surface storage (La-Manche and Aube centers) for TFA-wastes. The Aube center allows the storage of A-wastes whose half-life is less than 30 years. This site will receive waste packages for 50 years and will require a regular monitoring for 300 years after its decommissioning. No definitive solutions have been taken for B and C wastes, they are temporarily stored at La Hague processing plant. Concerning these wastes the French parliament will have to take a decision by 2006. At this date and within the framework of the Bataille law (1991), scientific studies concerning the definitive or retrievable storage, the processing techniques (like transmutation) will have been achieved and solutions will be proposed. These studies are numerous, long and complex, they involve fresh knowledge in geology, chemistry, physics,.. and they have implied the setting of underground facilities in order to test and validate solutions in situ. This article presents also the transmutation technique. (A.C.)

  16. Radioactive waste disposal

    International Nuclear Information System (INIS)

    Cluchet, J.; Roger, B.

    1975-10-01

    After mentioning the importance of the problem of the disposal of wastes produced in the electro-nuclear industry, a short reminder on a few laws of radioactivity (nature and energy of radiations, half-life) and on some basic dosimetry is given. The conditioning and storage procedures are then indicated for solid wastes. The more active fractions of liquid wastes are incorporated into blocks of glass, whereas the less active are first concentrated by chemical treatments or by evaporation. The concentrates are then embedded into concrete, asphalt or resins. Storage is done according to the nature of each type of wastes: on a hard-surfaced area or inside concrete-lined trenches for the lowest radioactivity, in pits for the others. Transuranium elements with very long half-lives are buried in very deep natural cavities which can shelter them for centuries. From the investigations conducted so far and from the experience already gained, it can be concluded that safe solutions are within our reach [fr

  17. Radioactive waste management

    International Nuclear Information System (INIS)

    Alfredson, P.G.; Levins, D.M.

    1975-08-01

    Present and future methods of managing radioactive wastes in the nuclear industry are reviewed. In the stages from uranium mining to fuel fabrication, the main purpose of waste management is to limit and control dispersal into the environment of uranium and its decay products, particularly radium and radon. Nuclear reactors produce large amounts of radioactivity but release rates from commercial power reactors have been low and well within legal limits. The principal waste from reprocessing is a high activity liquid containing essentially all the fission products along with the transuranium elements. Most high activity wastes are currently stored as liquids in tanks but there is agreement that future wastes must be converted into solids. Processes to solidify wastes have been demonstrated in pilot plant facilities in the United States and Europe. After solidification, wastes may be stored for some time in man-made structures at or near the Earth's surface. The best method for ultimate disposal appears to be placing solid wastes in a suitable geological formation on land. (author)

  18. Geohydrology of the near-surface unsaturated zone adjacent to the disposal site for low-level radioactive waste near Beatty, Nevada: A section in Safe disposal of radionuclides in low-level radioactive-waste repository sites; Low-level radioactive-waste disposal workshop, U.S. Geological Survey, July 11-16, 1987, Big Bear Lake, Calif., Proceedings (Circular 1036)

    Science.gov (United States)

    Fisher, Jeffrey M.; Bedinger, Marion S.; Stevens, Peter R.

    1990-01-01

    Shallow-land burial in arid areas is considered the best method for isolating low-level radioactive waste from the environment (Nichols and Goode, this report; Mercer and others, 1983). A major threat to waste isolation in shallow trenches is ground-water percolation. Repository sites in arid areas are believed to minimize the risk of ground-water contamination because such sites receive minimal precipitation and are underlain by thick unsaturated zones. Unfortunately, few data are available on rates of water percolation in an arid environment.

  19. TUMEUR ORBITAIRE: MANIFESTATION INITIALE D'UNE MALADIE ...

    African Journals Online (AJOL)

    L'hétérogénéité et la rareté des formes multicentriques de la maladie de Castleman font que leurs traitements soient très disparates. La maladie de Castleman doit être considérée comme un diagnostic possible d'une adénopathie cervicale particulièrement chez les patients souffrant d'une maladie inflammatoire chronique.

  20. TERATOME MATURE DE LA PAROTIDE : A PROPOS D'UNE ...

    African Journals Online (AJOL)

    Le tératome de la parotide est une malformation tumorale vestigiale rare contenant des dérivés plus ou moins différenciés, des trois feuillets embryonnaires. A la lumière d'une nouvelle observation et des données de la littérature, on se propose de mettre l'accent sur les aspects cliniques, histologiques et thérapeutiques de ...

  1. Case Report - Une tumeur exceptionnelle du doigt: la tumeur ...

    African Journals Online (AJOL)

    ... mous rend le diagnostic de ces tumeurs mésenchymateuses difficile et tardif. Dans 20à 30 % des cas le comportement de la TFS est celui d'une tumeur maligne localement agressive et récidivante, avec des métastases rares et tardives. Ce comportement impose une surveillance prolongée après exérèse chirurgicale.

  2. Natural atmospheric radioactivity

    International Nuclear Information System (INIS)

    Renoux, A.

    1986-01-01

    After having summed up the different old or new units, used in radioactivity and radioprotection, the origins of atmospheric radioactivity are reported. Next the authors deal with the air content in radon, thoron and their radioactive descendants, insisting on the variations of the radon air content and on the radioactive balance between radon and its descendants. Then a few notions concerning the natural radioactive aerosol are developed: electric charge state, granulometric distribution. The possible effects of natural atmospheric radioactivity on man are studied with a distinction between inner irradiation and outer irradiation, an average assessment is shown. Finally the important problem of radon in inhabitations is approached [fr

  3. Performance of engineered barrier materials in near surface disposal facilities for radioactive waste. Results of a co-ordinated research project

    International Nuclear Information System (INIS)

    2001-11-01

    The primary objectives of the CRP were to: promote the sharing of experiences of the Member States in their application of engineered barrier materials for near surface disposal facilities; help enhance their use of engineered barriers by improving techniques and methods for selecting, planning and testing performance of various types of barrier materials for near surface disposal facilities. The objective of this publication is to provide and overview of technical issues related to the engineered barrier systems and a summary of the major findings of each individual research project that was carried out within the framework of the CRP. This publication deals with a general overview of engineered barriers in near surface disposal facilities, key technical information obtained within the CRP and overall conclusions and recommendations for future research and development activities. Appendices presenting individual research accomplishments are also provided. Each of the 13 appendices was indexed separately

  4. Radioactive thickness gauge (1962); Jauge d'epaisseur radioactive (1962)

    Energy Technology Data Exchange (ETDEWEB)

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

    1962-07-01

    The author describes a thickness gauge in which the scintillating crystal detector alternately 'sees' a radioactive source through the material which is to be measured and then a control source of the same material; the radiations are separated in time by an absorbing valve whose sections are alternately full and hollow. The currents corresponding to the two sources are separated beyond the photomultiplier tube by a detector synchronized with the rotation of the valve. The quotient of these two currents is then obtained with a standard recording potentiometer. It is found that the average value of the response which is in the form G = f(I{sub 1}/I{sub 2}) is not affected by decay of the radioactive sources, and that it is little influenced by variations of high tension, temperature, or properties of the air in the source detector interval. The performance of the gauge is given. (author) [French] L'auteur decrit une jauge d'epaisseur dans laquelle le cristal scintillant detecteur 'voit' alternativement une source radioactive a travers le materiau a mesurer, puis une source de reference de meme nature; la separation des rayonnements est faite dans le temps a l'aide d'un volet absorbeur a secteurs alternativement pleins et creux. Les courants correspondants aux deux sources sont separes apres le tube photomultiplicateur par un detecteur synchrone avec la rotation du volet. On fait ensuite le quotient de ces deux courants a l'aide d'un potientometre enregistreur classique. il resulte de cette disposition que la valeur moyenne de la reponse, qui est de la forme G = f(I{sub 1}/I{sub 2}) n'est pas affectee par la decroissance des sources radioactives, et qu'elle est peu sensible aux variations de haute tension, de temperature ou des proprietes de l'air dans l'intervalle source-detecteur. On donne les performances de cette jauge. (auteur)

  5. Autostéréogramme d'une montagne gaussienne -utilisant une structure paradoxale périodique comme texture de camouflage-

    OpenAIRE

    Colonna , Jean-François

    2011-01-01

    Autostereogram -using a periodical paradoxal structure as a desguise texture- with an hidden gaussian mountain (Autostéréogramme d'une montagne gaussienne -utilisant une structure paradoxale périodique comme texture de camouflage-)

  6. Migration d'une broche dans le canal médullaire cervical après une ...

    African Journals Online (AJOL)

    Migration d'une broche dans le canal médullaire cervical après une ostéosynthèse de l'articulation acromio-claviculaire. Bah Aliou, El Alaoui Adil. Abstract. We report the case of a 49 year-old right-handed chef with left shoulder trauma occurred during a football game. The diagnosis was fracture of the distal quarter of ...

  7. Spatial distribution and risk assessment of radioactivity and heavy metal levels of sediment, surface water and fish samples from Lake Van, Turkey

    International Nuclear Information System (INIS)

    Sema Erenturk; Zeyneb Camtakan

    2014-01-01

    In this study, radioactivity levels of 228 lake water samples, 63 upper and depth sediment samples and 12 fish samples from Lake Van were investigated from 2005 to 2008 and the distribution patterns of the radionuclides were presented. Analysis included gross alpha-beta and total radium isotopes activities and uranium concentrations of the water, and gross alpha and gross beta activities and relevant 238 U, 232 Th and 40 K activity of the sediment and fish samples of the lake. Mean gross alpha, gross beta and radium isotopes activities of lake water were found 0.74 ± 0.46, 0.02 ± 0.01 and 0.06 ± 0.04 Bq/L, respectively. Mean gross alpha and beta activities in upper and depth sediments were found to be 41 ± 6 and 1,514 ± 74 Bq/kg; 77 ± 5 and 394 ± 24 Bq/kg at a 95 % confidence level, respectively. Mean activities of 238 U, 232 Th and 40 K activity concentrations in upper and depth sediments were determined to be 225 ± 22, 70 ± 7 and 486 ± 39 Bq/kg; 174 ± 4, 63 ± 3 and 263 ± 25 Bq/kg, respectively. The mean gross alpha and beta, 238 U, 232 Th and 40 K activities in fish samples were established as 47 ± 18, 470 ± 12, 0.57 ± 0.220, 0.022 ± 0.006, 319 ± 11 Bq/kg, respectively. The transfer factor from lake water to fish tissues, annual intake by humans consuming fish, and annual committed effective doses were estimated and evaluated. (author)

  8. Radioactivity and geophysics

    International Nuclear Information System (INIS)

    Radvanyi, P.

    1992-01-01

    The paper recalls a few steps of the introduction of radioactivity in geophysics and astrophysics: contribution of radioelements to energy balance of the Earth, age of the Earth based on radioactive disintegration and the discovery of cosmic radiations

  9. Radioactive Waste Management Strategy

    International Nuclear Information System (INIS)

    2002-01-01

    This strategy defines methods and means how collect, transport and bury radioactive waste safely. It includes low level radiation waste and high level radiation waste. In the strategy are foreseen main principles and ways of storage radioactive waste

  10. Radioactivity in consumer products

    Energy Technology Data Exchange (ETDEWEB)

    Moghissi, A.A.; Paras, P.; Carter, M.W.; Barker, R.F. (eds.)

    1978-08-01

    Papers presented at the conference dealt with regulations and standards; general and biological risks; radioluminous materials; mining, agricultural, and construction materials containing radioactivity; and various products containing radioactive sources.

  11. Radioactivity of bone cement

    International Nuclear Information System (INIS)

    Scherer, M.A.; Winkler, R.; Ascherl, R.; Lenz, E.

    1993-01-01

    A total of 14 samples of different types of bone cement from five different manufacturers were examined for their radioactivity. Each of the investigated bone cements showed a low radioactivity level, i.e. between [de

  12. Immersed radioactive wastes

    International Nuclear Information System (INIS)

    2017-03-01

    This document presents a brief overview of immersed radioactive wastes worldwide: historical aspects, geographical localization, type of wastes (liquid, solid), radiological activity of immersed radioactive wastes in the NE Atlantic Ocean, immersion sites and monitoring

  13. Natural Radioactivity in Surface Soil and Its Radiation Risk Implications in The Vicinity of Lynas Rare-Earth Plant at Gebeng, Kuantan

    International Nuclear Information System (INIS)

    Wo, Y.M.; Zal Uyun Wan Mahmood; Abdul Kadir Ishak; Mohd Abdul Wahab Yusof; Faizal Azrin Abdul Razalim

    2015-01-01

    Natural radionuclides (NORM) concentration (Bq/ kg) in surface soil at Lynas plant in Kuantan, Pahang were measured. To evaluate radiation hazard risk to human, radium equivalent activity (R aeq ), external hazard index (H ex ), representative level index(Iγr) and dose rate in air from the terrestrial natural gamma radiation (nGy/ h) were calculated. (author)

  14. Storage containers for radioactive material

    International Nuclear Information System (INIS)

    Cassidy, D.A.; Dates, L.R.; Groh, E.F.

    1981-01-01

    A radioactive material storage system is disclosed for use in the laboratory. This system is composed of the following: a flat base plate with a groove in one surface thereof and a hollow pedestal extending perpendicularly away from the other surface thereof; a sealing gasket in the groove, a cover having a filter therein and an outwardly extending flange which fits over the plate; the groove and the gasket, and a clamp for maintaining the cover and the plate are sealed together, whereby the plate and the cover and the clamp cooperate to provide a storage area for radioactive material readily accessible for use or inventory. Wall mounts are provided to prevent accidental formation of critical masses during storage

  15. Une pratique intertextuelle d'Aragon

    Directory of Open Access Journals (Sweden)

    Hervé Bismuth

    1999-09-01

    Full Text Available L'écriture du poème implique un « Je » susceptible d'impliquer à son tour un « tu » qui n'est pas seulement le lecteur. C'est dans cette particularité énonciative que s'inscrit la pratique du poème-hommage, qui, dans la poésie moderne, est prétexte à des jeux intertextuels. Dans le poème Les Poètes, Aragon complique la pratique coutumière de ce dialogue intertextuel, en plaçant le lecteur dans la perspective d'une intertextualité infinie, stratégie qui peut se décrire par l'étude de trois pratiques nouvelles alors chez Aragon : la mise en icône, le jeu de piste et ce que j'appellerai l'intertextualité tierce. Dans ce poème dont le scripteur ne cesse de parler à la première personne, s'impose à travers ces trois pratiques, qui coexistent avec d'autres, bien plus traditionnelles, la perspective d'une intertextualité abyssale.Writing a poem implies the existence of the « I », who is likely to involve another « you » who is not only the reader. Within the framework of this particular enunciation lies the use of the homage-poem which provides modern poetry with a pretext for intertextual play. In the poem Les poètes, Aragon heightens the complexity of the usual intertextual dialogue, putting the reader in the perspective of infinite intertextuality. This strategy can be described by the study of three new practices in Aragon's work – icon-making, track games, and what I would call the third intertextuality. In this first-person poem, the perspective of abysmal intertextuality prevails through these three practices coexisting with other more traditional ones.La escritura del poema implica un « yo » susceptible de implicar a su vez un « tú » que no es únicamente el lector. Es dentro de esta particularidad enunciativa donde se sitúa la práctica del poema-homenaje, que, en la poesia moderna, sirve de pretexto a varios juegos intertextuales. En el poema Les Poètes, Aragon complica la pr

  16. Une terreur par l’image

    Directory of Open Access Journals (Sweden)

    Annie DULONG

    2011-09-01

    Full Text Available Si d’autres événements — Hiroshima, la découverte des camps de concentration, la chute du mur de Berlin — ont, au cours du XXe siècle, marqué suffisamment l’imaginaire pour trouver leur réponse dans des œuvres d’art, le 11 septembre 2001 pose la question de la fictionnalisation autrement : il ne s’agit plus tant de combler les manques de la représentation, liés à l’absence d’images ou au délai dans leur dévoilement, mais bien de composer avec l’omniprésence d’une représentation martelée à la télévision et sur Internet. Que cette représentation soit partielle, tronquée et qu’il lui manque la présence des corps, ces grands absents des photographies et des images tournées par les journalistes, ne change rien au fait que c’est avec le trop-plein que les artistes doivent maintenant négocier.Cet article s’intéresse aux romans qui traitent l’événement de front au lieu de l’aborder sur un mode mineur, et a pour objectif de tracer un portrait de la représentation des médias dans les romans du 11 septembre 2001. Ces romans, outre le fait qu’ils traitent des événements de New York, ont comme point commun un personnage, ou décor : les médias, représentés par la télévision, l’Internet, les photographies de presse, interviennent dans les récits d’une manière significative et témoignent de la force brute des images. À travers une étude de certains des mécanismes à l’œuvre dans The Writing on the Wall (Lynne Sharon Schwartz, Extremely Loud and Incredibly Close (Jonathan Safran Foer, Falling Man (Don DeLillo et A Disorder Peculiar to the Country (Ken Kalfus, il s’agira de proposer des réponses à ces quelques questions : quel rôle les médias jouent-ils, et comment participent-ils au récit ? Quelle pression les images exercent-elles sur les personnages ? Que révèlent les personnages enfants dans leur rapport aux médias ? Quelle critique, finalement, les romans

  17. Transport of radioactive wastes

    International Nuclear Information System (INIS)

    Stuller, C.

    2003-01-01

    In this article author describes the system of transport and processing of radioactive wastes from nuclear power of Slovenske elektrarne, plc. It is realized the assurance of transport of liquid and solid radioactive wastes to processing links from places of their formation, or of preliminary storage and consistent transports of treated radioactive wastes fixed in cement matrix of fibre-concrete container into Rebublic storage of radioactive wastes in Mochovce

  18. Polarized secondary radioactive beams

    International Nuclear Information System (INIS)

    Zaika, N.I.

    1992-01-01

    Three methods of polarized radioactive nuclei beam production: a) a method nuclear interaction of the non-polarized or polarized charged projectiles with target nuclei; b) a method of polarization of stopped reaction radioactive products in a special polarized ion source with than following acceleration; c) a polarization of radioactive nuclei circulating in a storage ring are considered. Possible life times of the radioactive ions for these methods are determined. General schemes of the polarization method realizations and depolarization problems are discussed

  19. Management of radioactive waste

    International Nuclear Information System (INIS)

    Neerdael, B.; Marivoet, J.; Put, M.; Van Iseghem, P.; Volckaert, G.; Wacquier, W.

    1998-09-01

    The document gives an overview of of different aspects of radioactive waste management in Belgium. The document discusses the radioactive waste inventory in Belgium, the treatment and conditioning of radioactive waste as well as activities related to the characterisation of different waste forms. A separate chapter is dedicated to research and development regarding deep geological disposal of radioactive waste. In the Belgian waste management programme, particular emphasis is on studies for disposal in clay. Main results of these studies are highlighted and discussed

  20. Focus on radioactivity

    Energy Technology Data Exchange (ETDEWEB)

    Lambert, M

    1989-01-01

    Written for children, this book looks at the nature of radioactive materials, how they were discovered, what they are used for and how they affect the environment around us. The emphasis is on the benefits of radioactive materials, particularly in nuclear power stations, in medical diagnostics and radiotherapy, in industry and in agriculture. Nuclear fission and fusion are explained, how radioactive materials are handled and naturally occurring radioactivity are included. (UK).

  1. Radioactive waste management

    International Nuclear Information System (INIS)

    Balek, V.

    1994-01-01

    This booklet is a publication by International Atomic Energy Agency for general awareness of citizens and policy-makers to clarify their concept of nuclear wastes. In a very simple way it tells what is radioactivity, radiations and radioactive wastes. It further hints on various medial and industrial uses of radiations. It discusses about different types of radioactive wastes and radioactive waste management. Status of nuclear power plants in Central and Eastern European countries are also discussed

  2. Radioactive consumer products

    International Nuclear Information System (INIS)

    Sato, Otomaru

    1981-01-01

    Present situation of utilizing the radioactive consumer products and exposure dose were reviewed with published data. Practically, consumer products are divided into three categories, (1) radioactive nuclides intentionally incorporated into radioluminous dye, ionization chambers for smoke detector, eliminator of static electricity, and glow lamp (2) natural radioactive nuclides contained in false teeth, porcelain, glass, and gas mantle (3) natural radioactive nuclides accumulated as industrial waste at the consumption of coal, petroleum, and natural gas or in fertilizer and materials for construction. (Nakanishi, T.)

  3. Aspects of radioactive waste management

    International Nuclear Information System (INIS)

    Cutoiu, Dan

    2003-01-01

    The origin and types of radioactive waste, the objective and the fundamental principles of radioactive waste management and the classification of radioactive waste are presented. Problems of the radioactive waste management are analyzed. (authors)

  4. Method of solidifying radioactive waste by plastics

    International Nuclear Information System (INIS)

    Yasumura, Keijiro; Tomita, Toshihide.

    1976-01-01

    Purpose: To prevent leakage of radioactivity by providing corrosion-resistant layer on the inner surface of a waste container for radioactive waste. Constitution: The inner periphery and bottom of a drum can is lined with an non-flammable cloth of such material as asbestos. This drum is filled with a radioactive waste in the form of powder or pellets. Then, a mixture of a liquid plastic monomer and a polymerization starting agent is poured at a normal temperature, and the surface is covered with a non-flammable cloth. The plastic monomer and radioactive waste are permitted to impregnate the non-flammable cloth and are solidified there. Thus, even if the drum can is corroded at the sea bottom after disposal it in the ocean, it is possible to prevent the waste from permeating into the outer sea water because of the presence of the plastic layer on the inside. Styrene is used as the monomer. (Aizawa, K.)

  5. Understanding radioactive waste

    International Nuclear Information System (INIS)

    Murray, R.L.

    1989-01-01

    This book discusses the sources and health effects of radioactive wastes. It reveals the techniques to concentrate and immobilize radioactivity and examines the merits of various disposal ideas. The book, which is designed for the lay reader, explains the basic science of atoms,nuclear particles,radioactivity, radiation and health effects

  6. Transport of radioactive materials

    International Nuclear Information System (INIS)

    2013-01-01

    This ninth chapter presents de CNEN-NE--5.01 norm 'Transport of radioactive material'; the specifications of the radioactive materials for transport; the tests of the packages; the requests for controlling the transport and the responsibilities during the transport of radioactive material

  7. Radioactivity in the environment

    International Nuclear Information System (INIS)

    2011-01-01

    Illustrated by drawings, this publication briefly describes radioactive exposure modalities (external or internal irradiation), the ways they are measured and assessed (doses, units), the different natural radioactivity origins, the different radioactivity origins related to human activity, the share of each origin in population exposures

  8. Antiprotonic Radioactive Atom for Nuclear Structure Studies

    International Nuclear Information System (INIS)

    Wada, M.; Yamazaki, Y.

    2005-01-01

    A future experiment to synthesize antiprotonic radioactive nuclear ions is proposed for nuclear structure studies. Antiprotonic radioactive nuclear atom can be synthesized in a nested Penning trap where a cloud of antiprotons is prestored and slow radioactive nuclear ions are bunch-injected into the trap. By observing of the ratio of π+ and π- produced in the annihilation process, we can deduce the different abundance of protons and neutrons at the surface of the nuclei. The proposed method would provide a unique probe for investigating the nuclear structure of unstable nuclei

  9. The use of ligneous plants for controlling the radioactive contamination of a soil; Utilisation des vegetaux ligneux au controle de la pollution radioactive d'un sol

    Energy Technology Data Exchange (ETDEWEB)

    Gagnaire, J; Heuze, C; Aubert, M T [Commissariat a l' Energie Atomique, Grenoble (France).Centre d' Etudes Nucleaires

    1961-07-01

    A method for checking on the possible radioactive pollution of CEN-G. soil, by taking samples of tissue of ligneous plants cultivated on the land in question, is proposed and investigated during the vegetation period. A preliminary study on the retention capacity of the CEN-G. soil for solutions containing {sup 32}P and chemical composition is given. (author) [French] Une methode de controle de la pollution radioactive eventuelle du sol du CEN-G., a l'aide de prelevements de tissus de vegetaux ligneux, cultives sur ce terrain est proposee et etudiee pendant la periode vegetative. Une etude preliminaire du pouvoir de retention du sol du CEN-G, vis-a-vis de solutions contenant du {sup 32}P et de composition chimique, est exposee. (auteur)

  10. French hospital response to an emergency radioactive situation; Reponse des hopitaux francais a une dissemination radionucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Telion, C.; Carli, P. [SAMU de Paris, Dept. Anesthesie et Reanimation Hopital Necker Enfants Madades, 75 - Paris (France)

    2006-07-15

    Anticipating exceptional risks and training to deal with serious and violent events which are given massive media coverage is a very real challenge for hospital staff, and one that AP-HP decided to face. The R*53 exercise involved dealing with radiation contaminated victims requiring organisation of a specific, protected care circuit within the hospital. It was designed as a pedagogical exercise as part of a collective learning process with the aim of providing data which could be used as the basis for subsequent training. (authors)

  11. Hydro-mechanical improvement of the cap cover of a surface landfill for low and intermediate level radioactive waste short life time

    International Nuclear Information System (INIS)

    Verstaevel, Matthieu

    2015-01-01

    This study related to the Manche storage center (CSM), one of the first landfill in the world dedicated to low and intermediate radioactive waste short-live time. The researches considered in this thesis supported by industrial companies, focus on the hydraulic study of cap cover materials of the site, and their hydro-mechanical improvement. The aim is to improve their impermeability in order to be substituted to the geo-membrane as cap cover liner. A specification imposed by Andra was to consider a solution of the re-use of the in situ material by adding of additive. The initial material is a sandy silt, a material with a significant proportion of fines. In the literature there are many studies on the mechanical improvement of fine materials (applications to road infrastructure) and the treatment of sandy materials by adding a fine fraction (constitution of waterproof barriers). On the other hand there are very few studies on the impermeability improvement of fine soils. A physical tests campaign on treated materials with bentonite was carried out at various treatment rates. The results showed that the addition of additive induces a decrease in optimum dry unit weight for a normal Proctor compaction energy and increases their optimum water content. In addition, the susceptibility to erosion, internal or external, observed during oedo-permeameter test was assessed from various stability criteria available in the literature. Unlike the treatment of soil for road embankments, the increase of the material stiffness is not wanted and flexibility is preferred what is observed with the treatment tested. The comparative hydraulic conductivity of the untreated and treated materials were measured. In this study different devices (oedo-permeameter, permeameters, triaxial device) were used. The influence of the treatment rate of the material on the decrease of the hydraulic conductivity was observed. Four large scale experimentations were designed; they should be monitored

  12. Conception et réalisation d'une pince acoustique pour la manipulation de cellules

    OpenAIRE

    Toru , Sylvain

    2013-01-01

    "Prix scientifique" JCGE'2013 (3 prix attribués pour 80 présentations); International audience; Parmi les techniques de manipulation sans contact de micro-objets comme des cellules vivantes, l'acoustophorèse présente l'avantage de permettre leur manipulation dans leur milieu de culture sans aucun marquage préalable. Un substrat piézoélectrique sur lequel sont déposées des électrodes interdigitées (IDTs) permet de générer une onde acoustique de surface stationnaire. Celle-ci se transmet au flu...

  13. A method of sub-critical experimentation, 'the neutrostat'; Une methode d'experimentation sous critique 'le neutrostat'

    Energy Technology Data Exchange (ETDEWEB)

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

    1958-07-01

    The method proposed is designed for the study of neutronic properties of a sample (its material buckling, for example) and consists in submitting the sample to uniform surface density irradiation, its surface being a sphere or a cylinder which is supposed, temporarily, to be infinite. Neutron density in the sample will thus be uniform if its laplacian is nil: any curve in the distribution clearly indicating its absorbent or multiplying properties. In the case of a sample with multiplying power, density is identical to that in an active core, thus measurement of buckling will be free from considerable systematic error causes. The thermic equivalent of this type of irradiation would be a thermostat with an external heat source distributed uniformly over its surface: its temperature would be uniform. It is this analogy that has led us to baptize it the 'Neutrostat'. (author)Fren. [French] En vue d'etudier les proprietes neutroniques d'un milieu (son laplacien 'matiere' par exemple), la methode proposee consiste a le soumettre a des conditions d'irradiation uniforme sur sa surface, celle-ci ayant la forme d'une sphere ou d'un cylindre que nous supposons provisoirement infini. Les neutrons s'y trouvent alors repartis avec une densite uniforme si le milieu est un diffuseur pur. Toute courbure de cette repartition sera un indice sensible de ses proprietes absorbantes ou multiplicatrices. Dans le cas d'un milieu multiplicateur, la repartition est identique a celle qui regne au milieu d'une pile critique et nous verrons que la mesure du laplacien est alors exempte de causes d'erreurs systematiques importantes. L'equivalent thermique d'un tel mode d'irradiation serait un dispositif thermostatique dont la source de chaleur externe serait repartie uniformement sur la surface: il y regnerait une temperature uniforme. C'est cette analogie qui nous a guides dans le choix du vocable propose dans le titre: 'Neutrostat'. (auteur)

  14. Surface passivation: a new way to reduce self-output in LiMn{sub 2}O{sub 4}/Li lithium ion rechargeable batteries; Passivation de surface: une nouvelle voie pour reduire l`autodecharge dans les batteries rechargeables a ions lithium LiMn{sub 2}O{sub 4}/Li

    Energy Technology Data Exchange (ETDEWEB)

    Sigala, C.; Blyr, A.; Tarascon, J.M. [Amiens Univ., 80 (France). Laboratoire de Reactivite et de Chimie des Solides; Amatucci, G. [Bellcore, (United States); Alphonse, P. [Toulouse-3 Univ., 31 (France). Laboratoire de Chimie des Materiaux Inorganiques

    1996-12-31

    The new generation of performing rechargeable lithium-ion batteries (``rocking-chair``-type) are penalized by important self-output phenomena linked with the use of highly oxidizing positive electrodes. In order to limit this problem in LiMn{sub 2}O{sub 4}/C batteries, two different passivation techniques were used in order to limit the surface contact between the positive electrode and the electrolyte. Thanks to these treatments, a significant reduction of the percentage of irreversible capacity losses is effectively observed. (J.S.) 3 refs.

  15. Surface passivation: a new way to reduce self-output in LiMn{sub 2}O{sub 4}/Li lithium ion rechargeable batteries; Passivation de surface: une nouvelle voie pour reduire l`autodecharge dans les batteries rechargeables a ions lithium LiMn{sub 2}O{sub 4}/Li

    Energy Technology Data Exchange (ETDEWEB)

    Sigala, C; Blyr, A; Tarascon, J M [Amiens Univ., 80 (France). Laboratoire de Reactivite et de Chimie des Solides; Amatucci, G [Bellcore, (United States); Alphonse, P [Toulouse-3 Univ., 31 (France). Laboratoire de Chimie des Materiaux Inorganiques

    1997-12-31

    The new generation of performing rechargeable lithium-ion batteries (``rocking-chair``-type) are penalized by important self-output phenomena linked with the use of highly oxidizing positive electrodes. In order to limit this problem in LiMn{sub 2}O{sub 4}/C batteries, two different passivation techniques were used in order to limit the surface contact between the positive electrode and the electrolyte. Thanks to these treatments, a significant reduction of the percentage of irreversible capacity losses is effectively observed. (J.S.) 3 refs.

  16. Radioactive sources in chemical laboratories

    International Nuclear Information System (INIS)

    Janzekovic, H.; Krizman, M.

    2007-01-01

    Radioactive sources including all radioactive materials exceeding exemption levels have to be registered in national databases according to international standards based on the recommendations ICRP 60 and a proper licensing should take place as described for example in the 96/29/EURATOM. In spite of that, unregistered sources could be found, usually due to the fact that the owner is not aware of radiation characteristics of sources. The material inventories of chemical laboratories are typical and most frequent example where radioactive sources could be found. Five different types of sources could be identified. The most frequent type are chemicals, namely thorium and uranium compounds. They are used not due to their radioactivity but due to their chemical properties. As for all other sources a stringent control is necessary in order to assure their safe use. Around hundred of stored radioactive chemical items were found during inspections of such laboratories performed by the Slovenian Nuclear Safety Administration or qualified experts in a period December 2006 - July 2007. Users of such chemicals are usually not aware that thorium and uranium chemicals are radioactive and, as unsealed sources, they could be easily spilled out and produce contamination of persons, surfaces, equipment etc. The external exposure as well as the internal exposure including exposure due to inhalation could be present. No knowledge about special precautions is usually present in laboratories and leads to underestimating of a potential risk and unintentional exposure of the laboratory personnel, students etc. Due to the long decay times in decay series of Th -232, U-238 and U- 235 the materials are also radioactive today. Even more, in case of thorium chemicals the radioactivity increased substantially from the time of their production. The implementation of safety measures has been under way and includes a survey of the qualified experts, establishment of organizational structure in a

  17. Treating radioactive effluent

    International Nuclear Information System (INIS)

    Kirkham, I.A.

    1981-01-01

    In the treatment of radioactive effluent it is known to produce a floc being a suspension of precipitates carrying radioactive species in a mother liquor containing dissolved non-radioactive salts. It is also known and accepted practice to encapsulate the floc in a solid matrix by treatment with bitumen, cement and the like. In the present invention the floc is washed with water prior to encapsulation in the solid matrix whereby to displace the mother liquor containing the dissolved non-radioactive salts. This serves to reduce the final amount of solidified radioactive waste with consequent advantages in the storage and disposal thereof. (author)

  18. Report on radioactive waste disposal

    International Nuclear Information System (INIS)

    1993-01-01

    The safe management of radioactive wastes constitutes an essential part of the IAEA programme. A large number of reports and conference proceedings covering various aspects of the subject have been issued. The Technical Review Committee on Underground Disposal (February 1988) recommended that the Secretariat issue a report on the state of the art of underground disposal of radioactive wastes. The Committee recommended the need for a report that provided an overview of the present knowledge in the field. This report covers the basic principles associated with the state of the art of near surface and deep geological radioactive waste disposal, including examples of prudent practice, and basic information on performance assessment methods. It does not include a comprehensive description of the waste management programmes in different countries nor provide a textbook on waste disposal. Such books are available elsewhere. Reviewing all the concepts and practices of safe radioactive waste disposal in a document of reasonable size is not possible; therefore, the scope of this report has been limited to cover essential parts of the subject. Exotic disposal techniques and techniques for disposing of uranium mill tailings are not covered, and only brief coverage is provided for disposal at sea and in the sea-bed. The present report provides a list of references to more specialized reports on disposal published by the IAEA as well as by other bodies, which may be consulted if additional information is sought. 108 refs, 22 figs, 2 tabs

  19. ISAM news. International programme on implementation of safety assessment methodologies for near surface disposal facilities for radioactive waste (ISAM 1997-1999)

    International Nuclear Information System (INIS)

    Torres, Carlos

    1996-01-01

    The scope of the programme will be the scientific and technical aspects related to the long term safety assessment of near disposal facilities. The primary focus of ISAM will be on the methodological aspects of safety assessment with emphasis on the practical application of these methodologies. Furthermore, practical application is necessary for for a thorough understanding of safety assessment methodologies. The programme will address important methodological issues associated with long term safety assessment of near surface disposal systems. At least three important areas will be covered: (1) scenario generation and justification; (2) modelling, data and tools; and (3) analysis of results and confidence building

  20. Dry containment of radioactive materials

    International Nuclear Information System (INIS)

    Williams, C.E.

    1980-01-01

    A cask for the dry containment of radioactive fuel elements is described. The cask has a cover which contains valved drain and purge passageways. These passageways are sealed by after purge cover seals which are clamped over them and to the outer surface of the cover. The cover seals are tested by providing them with a pair of concentric ring seal elements squeezed between the cover seal and the outer surface of the cover and by forcing a gas under pressure into the annular region between the seal element

  1. Une restauration « spectaculaire »

    Directory of Open Access Journals (Sweden)

    Muriel Verbeeck-Boutin

    2010-04-01

    Full Text Available Cet article replace dans le contexte d’une époque la restauration d’une Vierge à l’enfant par Joseph Van der Veken. Documentée par le commanditaire, l’intervention ne répondit pas à son attente et déboucha sur une dérestauration. Ce fait, loin d’être anecdotique, témoigne d’une mutation des mentalités et des sensibilités dans la première moitié du vingtième siècle, et de l’émergence d’une nouvelle conception de la restauration.This article replaces the restoration of a Madonna and Child by Joseph Van der Vecken within the context of a period.Documented by the patron, the intervention did not meet his expectations and resulted in a de-restoration. This fact, far from being anecdotic, is proof of the change in mentalities and sensitivities in the first half of the twentieth century and of the emergence of a new concept of restoration

  2. Restauration et traduction : une question de philosophie

    Directory of Open Access Journals (Sweden)

    Pierre Leveau

    2011-05-01

    Full Text Available On peut faire de la restauration une mission de service public, ou une entreprise privée soumise à la loi du marché. Quel sens donner à cette activité ? Philosophiquement, la méthodologie est à réinventer. L’auteur propose pour cela de définir la restauration comme une traduction, c’est-à-dire une transmission en même temps qu’une transaction. Il formule cette hypothèse en engageant un dialogue entre le réalisme et le constructionnalisme.The conservation can be viewed as a public service and also as an economical activity. How to understand such a pratice ? From a philosophical standpoint, this question is methologically challenging. The author claims that conservation can be defined as a translation, i.e. as a transmission and a transaction. He tests this hypothesis through a confrontation between realism and constructionism.

  3. Reference levels of natural radioactivity and (137)Cs in and around the surface soils of Kestanbol pluton in Ezine region of Çanakkale province, Turkey.

    Science.gov (United States)

    Öztürk, Buket Canbaz; Çam, N Füsun; Yaprak, Günseli

    2013-01-01

    The aim of the study was to conduct a systematic investigation on the natural gamma emitting radionuclides ((226)Ra, (232)Th and (40)K) as well as (137)Cs in the surface soils from Kestanbol/Ezine plutonic area in Çanakkale province as part of the environmental monitoring program on radiologic impact of the granitoid areas in Western Anatolia. The activity measurements of the gamma emitters in the surface soil samples collected from 52 sites distributed all over the region has been carried out, by means of HPGe gamma-ray spectrometry system. The activity concentrations of the relevant radionuclides in the soil samples appeared in the ranges as follows: (226)Ra was 20-521 Bq kg(-1); (232)Th, 11-499 Bq kg(-1)and; (40)K, 126-3181 Bq kg(-1), yet the (137)Cs was much lower than 20 Bq kg(-1)at most. Furthermore, based on the available data, the radiation hazard parameters associated with the surveyed soils were calculated. The present data also allowed evaluation of some correlations that may exist in the investigated natural radionuclides of the soil samples from the plutonic area in Çanakkale province. It is concluded from the above that the concerned region did not lead to any significant radiological exposure to the environment.

  4. Radioactivity levels of 238U and 232Th, the α and β activities and associated dose rates from surface soil in Ulu Tiram, Malaysia

    International Nuclear Information System (INIS)

    Abdul Rahman, A.T.; Ramli, A.T.

    2007-01-01

    A survey was carried out to determine terrestrial gamma radiation dose rates, the concentration level of 238 U and 232 Th and α and β activities for the surface soil in Ulu Tiram, Malaysia. A 125 measurements were performed using a NaI(Tl) gamma-ray detector with crystal size of 1' x 1' on 15 soil samples collected from the site area about 102 km 2 . 238 U and 232 Th concentrations were determined in soils by using hyper pure germanium (HPGe) gamma-ray spectrometry. The activity of α and β from the surface soil was counted by using alpha beta counting system. The average value of 238 U and 232 Th concentrations in soil samples collected are 3.63±0.39 ppm within the range of 1.74±0.20 to 4.58±0.48 and 43.00±2.31 ppm within the range of 10.68±0.76 to 82.10±4.01 ppm, respectively. The average estimate of α and β activity in soil samples collected are 0.65±0.09 Bq x g -1 and 0.68±0.08 Bq x g -1 , respectively. The average of terrestrial gamma-radiation dose rates measured in Ulu Tiram was found to be 200 nGy x h -1 , within the range of 96 to 409 nGy x h -1 . The population weighted outdoor annual effective dose was 1.2 mSv. (author)

  5. Ostéo arthrite tuberculeuse de la cheville et spondylodiscite: une ...

    African Journals Online (AJOL)

    La TDM et l'IRM rachidienne (A, B, C, D) ont montré: une collection épidurale en regard de D3D4D5D6, une destruction vertébrale de D4 avec recul du mur postérieur responsable d'une déformation dorsale avec compression médullaire, une atteinte D8D9D10D11D12 avec présence d'une collection intra-osseuse, une ...

  6. La syphilis congenitale revelee par une fracture spontanee

    Directory of Open Access Journals (Sweden)

    Mounia Lakhdar Idrissi

    2011-11-01

    Full Text Available Alors qu�elle est actuellement oubliee dans les pays developpes, la syphilis congenitale se voit encore chez nous faute du depistage antenatal. Ses formes cliniques sont polymorphes et orientent a tord vers d�autres pathologies surtout en periode neonatale. Le diagnostic n�est donc pas toujours facile. La revelation d�une syphilis congenitale par une fracture spontanee est exceptionnellement decrite. Nous rapportons dans ce travail le cas d�un nourrisson de 2 mois ramene en consultation pour limitation douloureuse des mouvements du bras droit. Le diagnostic est evoque sur les donnees radiologiques et confirme par la serologie syphilitique. Le traitement a repose essentiellement sur l�administration de la penicilline G avec une bonne evolution clinique.

  7. 1. Le Soleil, une étoile dans notre Galaxie

    OpenAIRE

    Vial, Jean-Claude

    2017-01-01

    Par une belle nuit sans Lune (et sans nuages), levons les yeux vers le ciel. L’œil est immédiatement attiré par le cortège d’étoiles brillantes qui a donné son nom à la Voie lactée. Il s’agit en fait d’une galaxie de près de 200 milliards d’étoiles qui abrite notre Soleil et ses planètes, c’est notre galaxie, « la » Galaxie, comme une île dans le vaste cosmos. La Galaxie : ses 150 à 200 milliards d’étoiles sont réparties selon des bras spiraux autour d’un noyau central et pour la plupart conf...

  8. In-situ IR reflexion spectroscopy characterization of the passivation layer developed on the surface of lithium electrodes in organic medium; Passivation de surface: une nouvelle voie pour reduire l`autodecharge dans les batteries rechargeables a ions lithium LiMn{sub 2}O{sub 4}/Li

    Energy Technology Data Exchange (ETDEWEB)

    Barusseau, S. [Alcatel Alsthom Recherche, 91 - Marcoussis (France); Perton, F. [SAFT, Advanced and Industrial Battery Group, 86 - Poitiers (France); Rakotondrainibe, A.; Lamy, C. [Poitiers Univ., 86 (France). Laboratoire de Chimie 1, ``Electrochimie et Interactions``

    1996-12-31

    the development of lithium metal batteries is hindered by the bad reversibility of the Li{sup +}/Li pair, due to dendrites formation which limits the amount of active matter and can generate short-circuits. The chemical and electrochemical phenomena which take place at the electrode/organic electrolyte interface lead to the formation of a complex passivation film which is of prime importance for the functioning of this type of batteries. The in-situ infrared reflection spectroscopy is well adapted to the chemical study of the passivation layer. Two different techniques were used: the substraction normalized interfacial transform infrared spectroscopy (SNIFTIRS) and the electro-chemically modulated infrared reflectance spectroscopy. These methods have shown that the passivation layer that develops on the surface of the lithium electrode in contact with organic solutions (propylene carbonate, ethylene carbonate and dimethoxyethane) is mainly made of lithium alkyl carbonates (ROCO{sub 2}Li) and lithium carbonates (Li{sub 2}CO{sub 3}). (J.S.) 14 refs.

  9. The multi-task barge: a floating deep-sea production, storage and unloading unit, with surface production heads and drilling installations; La barge multifonctions: une unite flottante de production, de stockage et dechargement en eau profonde, avec tetes de production en surface et installations de forage

    Energy Technology Data Exchange (ETDEWEB)

    Valenchon, C; Rossig, J H [Bouygues Offshore (France); Pouget, G [Sedco-Forex (France); Biolley, F [Institut Francais du Petrole, 92 - Rueil-Malmaison (France)

    1998-05-01

    The multi-task barge is devoted to the exploitation of deep-sea fields in rather good conditions. It has been designed to bring together within a single installation, a production, storage and unloading unit and the necessary means for the drilling, the connecting and the work-over of wells. Thus submarine well-heads and well-head platforms are no longer needed. When the field configuration or the use of oriented drillings allows to group several wells together, the multi-task platform allows to use more economical surface production heads installed on steel rigid risers. This concept requires less investments thanks to less expensive drilling operations and restricted submarine installations, and to easier well operations and lower exploitation costs. Crude oil storage is ensured to up to about 2 millions of barrels. This paper presents the design aspects and the dynamical analysis of risers with the methods used. The tensioning and mooring system is examined and the advantages of the cylindrical float system is underlined and compared to the classical hydro-pneumatic systems. (J.S.) 11 refs.

  10. In-situ IR reflexion spectroscopy characterization of the passivation layer developed on the surface of lithium electrodes in organic medium; Passivation de surface: une nouvelle voie pour reduire l`autodecharge dans les batteries rechargeables a ions lithium LiMn{sub 2}O{sub 4}/Li

    Energy Technology Data Exchange (ETDEWEB)

    Barusseau, S [Alcatel Alsthom Recherche, 91 - Marcoussis (France); Perton, F [SAFT, Advanced and Industrial Battery Group, 86 - Poitiers (France); Rakotondrainibe, A; Lamy, C [Poitiers Univ., 86 (France). Laboratoire de Chimie 1, ` ` Electrochimie et Interactions` `

    1997-12-31

    the development of lithium metal batteries is hindered by the bad reversibility of the Li{sup +}/Li pair, due to dendrites formation which limits the amount of active matter and can generate short-circuits. The chemical and electrochemical phenomena which take place at the electrode/organic electrolyte interface lead to the formation of a complex passivation film which is of prime importance for the functioning of this type of batteries. The in-situ infrared reflection spectroscopy is well adapted to the chemical study of the passivation layer. Two different techniques were used: the substraction normalized interfacial transform infrared spectroscopy (SNIFTIRS) and the electro-chemically modulated infrared reflectance spectroscopy. These methods have shown that the passivation layer that develops on the surface of the lithium electrode in contact with organic solutions (propylene carbonate, ethylene carbonate and dimethoxyethane) is mainly made of lithium alkyl carbonates (ROCO{sub 2}Li) and lithium carbonates (Li{sub 2}CO{sub 3}). (J.S.) 14 refs.

  11. Henri Lopès : d’Une Quête Incessante à une identité plurielle

    Directory of Open Access Journals (Sweden)

    Vincent Simédoh

    2006-04-01

    Full Text Available Dans plusieurs oeuvres d’Henri Lopès, les personnages sont constamment en quête d’une identité. Une quête qu’ils entament comme un parcours puisque désormais ils vivent au confluent de plusieurs cultures et ils se sentent comme en exil. Ce n’est pas forcément un exil extérieur parce qu’ils ont quitté leur pays d’origine mais c’est plutôt un exil intérieur. Ainsi les personnages se sentent incapables de se situer par rapport à eux-mêmes et à autrui. Dès lors surgit une tentation, celle de se réfugier dans le souvenir qui n’existe même plus. La mémoire s’estompe. L’histoire elle-même fuit et disparaît. Ce qui fait naître chez les personnages un vide qui conduit à un malaise identitaire, d’où déchirement. En face de cet écartèlement, surgit une multitude de pistes. Et c’est dans cette perspective qu’Henri Lopès propose une identité plurielle.

  12. Method and device of decontaminating radioactive solid wastes

    International Nuclear Information System (INIS)

    Hasegawa, Hiroshi; Tamada, Masami.

    1983-01-01

    Purpose: To surely enable grinding for the inner surface of hollow radioactive solid wastes such as pipeways or valves, as well as enable to decontaminate these solid wastes to such a level as being capable of processing in the same manner for the ordinary wastes. Method: A grinding piece abutting resiliently against the inner surface of a hollow radioactive solid wastes to be contaminated is attached at the top end of a flexible shaft, and the inner surface of the radioactive solid wastes is ground while rotating and slightly reciprocating, as well as axially moving the flexible shaft. Consequently, since the grinding piece is always abutted against the inner surface of the radioactive solid wastes just following after the profile of the inner surface, and the flexible shaft is resiliently flexed corresponding to the profile of the inner surface of the radioactive solid wastes, even an inner surface of radioactive solid wastes with a complicated configuration can surely be ground entirely. This surely enables to remove radioactive claddings and contaminated layers deposited on the surface. (Yoshihara, H.)

  13. Radioactive waste management solutions

    International Nuclear Information System (INIS)

    Siemann, Michael

    2015-01-01

    One of the more frequent questions that arise when discussing nuclear energy's potential contribution to mitigating climate change concerns that of how to manage radioactive waste. Radioactive waste is produced through nuclear power generation, but also - although to a significantly lesser extent - in a variety of other sectors including medicine, agriculture, research, industry and education. The amount, type and physical form of radioactive waste varies considerably. Some forms of radioactive waste, for example, need only be stored for a relatively short period while their radioactivity naturally decays to safe levels. Others remain radioactive for hundreds or even hundreds of thousands of years. Public concerns surrounding radioactive waste are largely related to long-lived high-level radioactive waste. Countries around the world with existing nuclear programmes are developing longer-term plans for final disposal of such waste, with an international consensus developing that the geological disposal of high-level waste (HLW) is the most technically feasible and safe solution. This article provides a brief overview of the different forms of radioactive waste, examines storage and disposal solutions, and briefly explores fuel recycling and stakeholder involvement in radioactive waste management decision making

  14. Etude aerodynamique d'un jet turbulent impactant une paroi concave

    Science.gov (United States)

    LeBlanc, Benoit

    Etant donne la demande croissante de temperatures elevees dans des chambres de combustion de systemes de propulsions en aerospatiale (turbomoteurs, moteur a reaction, etc.), l'interet dans le refroidissement par jets impactant s'est vu croitre. Le refroidissement des aubes de turbine permet une augmentation de temperature de combustion, ce qui se traduit en une augmentation de l'efficacite de combustion et donc une meilleure economie de carburant. Le transfert de chaleur dans les au bages est influence par les aspects aerodynamiques du refroidissement a jet, particulierement dans le cas d'ecoulements turbulents. Un manque de comprehension de l'aerodynamique a l'interieur de ces espaces confinees peut mener a des changements de transfert thermique qui sont inattendus, ce qui augmente le risque de fluage. Il est donc d'interet pour l'industrie aerospatiale et l'academie de poursuivre la recherche dans l'aerodynamique des jets turbulents impactant les parois courbes. Les jets impactant les surfaces courbes ont deja fait l'objet de nombreuses etudes. Par contre des conditions oscillatoires observees en laboratoire se sont averees difficiles a reproduire en numerique, puisque les structures d'ecoulements impactants des parois concaves sont fortement dependantes de la turbulence et des effets instationnaires. Une etude experimentale fut realisee a l'institut PPRIME a l'Universite de Poitiers afin d'observer le phenomene d'oscillation dans le jet. Une serie d'essais ont verifie les conditions d'ecoulement laminaires et turbulentes, toutefois le cout des essais experimentaux a seulement permis d'avoir un apercu du phenomene global. Une deuxieme serie d'essais fut realisee numeriquement a l'Universite de Moncton avec l'outil OpenFOAM pour des conditions d'ecoulement laminaire et bidimensionnel. Cette etude a donc comme but de poursuivre l'enquete de l'aerodynamique oscillatoire des jets impactant des parois courbes, mais pour un regime d'ecoulement transitoire, turbulent

  15. Radioactive waste management and disposal in Australia

    International Nuclear Information System (INIS)

    Harries, J.R.

    1997-01-01

    A national near-surface repository at a remote and arid location is proposed for the disposal of solid low-level and short-lived intermediate-level radioactive wastes in Australia. The repository will be designed to isolate the radioactive waste from the human environment under controlled conditions and for a period long enough for the radioactivity to decay to low levels. Compared to countries that have nuclear power programs, the amount of waste in Australia is relatively small. Nevertheless, the need for a national disposal facility for solid low-level radioactive and short-lived intermediate-level radioactive wastes is widely recognised and the Federal Government is in the process of selecting a site for a national near-surface disposal facility for low and short-lived intermediate level wastes. Some near surface disposal facilities already exist in Australia, including tailings dams at uranium mines and the Mt Walton East Intractable Waste Disposal Facility in Western Australia which includes a near surface repository for low level wastes originating in Western Australia. 7 refs, 1 fig., 2 tabs

  16. Method of decontaminating radioactive metal wastes

    International Nuclear Information System (INIS)

    Miyaji, Nobuyoshi.

    1985-01-01

    Purpose: To completely prevent the surface contamination of an equipment and decrease the amount of radioactive wastes to be resulted. Method: The surfaces of vessels, pipeways or the likes of nuclear reactor facilities to be contaminated with radioactive materials are appended with thin plates of metals identical or different from the constituents of the surfaces so as to be releasable after use. The material and the thickness of the plates and the method of appending then are determined depending on the state of use of the appended portions. Since only the stripped plates have to be processed as radioactive wastes, the amount of wastes can be decreased and, since the scrap materials can be reused, it is advantageous in view of the resource-saving. (Sekiya, K.)

  17. Prevalence de la cataracte senile dans une population rurale du ...

    African Journals Online (AJOL)

    But: Evaluer la prévalence de la cataracte sénile dans le canton de Kévé, préfecture de l'Avé au Togo. Méthodologie: Il s'agit d'une étude transversale dans trois villages et le centre ville de Kévé. Les patients étaient regroupés et examinés à la lumière du jour à l'aide d'une lampe torche et un ophtalmoscope direct à piles ...

  18. Une clinique possible avec les malades d’Alzheimer

    OpenAIRE

    Fontela, Cristina; Darnaud, Thierry

    2015-01-01

    Dans cet article les auteurs montrent qu’une psychothérapie d’inspiration psychanalytique est possible avec des sujets institutionnalisés présentant une démence du type Alzheimer. Elle se justifie d’autant plus que le sujet a subi des pertes relationnelles et d’objets libidinalement investis. Le clinicien tente de s’adapter à un psychisme en proie aux troubles cognitifs où les mouvements transféro-contretransférentiels sont massifs et ont un rôle particulier dans l’économie psychique du sujet...

  19. Shallow disposal of radioactive waste

    International Nuclear Information System (INIS)

    1985-02-01

    A review and evaluation of computer codes capable of simulating the various processes that are instrumental in determining the dose rate to individuals resulting from the shallow disposal of radioactive waste was conducted. Possible pathways of contamination, as well as the mechanisms controlling radionuclide movement along these pathways have been identified. Potential transport pathways include the unsaturated and saturated ground water systems, surface water bodies, atmospheric transport and movement (and accumulation) in the food chain. Contributions to dose may occur as a result of ingestion of contaminated water and food, inhalation of contaminated air and immersion in contaminated air/water. Specific recommendations were developed regarding the selection and modification of a model to meet the needs associated with the prediction of dose rates to individuals as a consequence of shallow radioactive waste disposal. Specific technical requirements with regards to risk, sensitivity and uncertainty analyses have been addressed

  20. Chemical decontamination method for radioactive metal waste

    International Nuclear Information System (INIS)

    Onuma, Tsutomu; Akimoto, Hidetoshi

    1991-01-01

    The invention relates to a decontamination method for radioactive metal waste products derived from equipment that handles radioactive materials whose surfaces have been contaminated; in particular it concerns a decontamination method that reduces the amount of radioactive waste by decontaminating radioactive waste substances to a level of radioactivity in line with normal waste products. In order to apply chemical decontamination to metal waste products whose surfaces are divided into carbon steel waste and stainless steel waste; the carbon steel waste is treated using only a primary process in which the waste is immersed in a sulfuric acid solution, while the stainless steel waste must be treated with both the primary process and then electrolytically reduces it for a specific length of time and a secondary process that uses a solution of sulfuric acid mixed with oxidizing metal salts. The method used to categorize metal waste into carbon steel waste and stainless steel waste involves determining the presence, or absence, of magnetism. Voltage is applied for a fixed duration; once that has stopped, electrolytic reduction repeats the operative cycle of applying, then stopping voltage until the potential of the radioactive metal waste is retained in the active region. 1 fig. 2 tabs

  1. Safety objectives and basic design for surface centres for long-term storage of solid radioactive waste with short or medium half-life and low or medium specific activity

    International Nuclear Information System (INIS)

    1984-06-01

    RFS or Regles Fondamentales de Surete (Basic Safety Rules) applicable to certain types of nuclear facilities lay down requirements with which compliance, for the type of facilities and within the scope of application covered by the RFS, is considered to be equivalent to compliance with technical French regulatory practice. The object of the RFS is to take advantage of standardization in the field of safety, while allowing for technical progress in that field. They are designed to enable the operating utility and contractors to know the rules pertaining to various subjects which are considered to be acceptable by the Service Central de Surete des Installations Nucleaires, or the SCSIN (Central Department for the Safety of Nuclear Facilities). These RFS should make safety analysis easier and lead to better understanding between experts and individuals concerned with the problems of nuclear safety. The SCSIN reserves the right to modify, when considered necessary, any RFS and specify, if need be, the terms under which a modification is deemed retroactive. The role of this RFS is to define the safety objectives and the basic design philosophy for surface centres for long-term storage of packages of radioactive waste with short or medium half-life and with low or medium specific activity

  2. Radioactivity and food

    International Nuclear Information System (INIS)

    Olszyna-Marzys, A.E.

    1990-01-01

    Two topics relating to radioactivity and food are discussed: food irradiation for preservation purposes, and food contamination from radioactive substances. Food irradiation involves the use of electromagnetic energy (x and gamma rays) emitted by radioactive substances or produced by machine in order to destroy the insects and microorganisms present and prevent germination. The sanitary and economic advantages of treating food in this way are discussed. Numerous studies have confirmed that under strictly controlled conditions no undesirable changes take place in food that has been irradiated nor is radioactivity induced. Reference is made to the accident at the Chernobyl nuclear power station, which aroused public concern about irradiated food. The events surrounding the accident are reviewed, and its consequences with regard to contamination of different foods with radioactive substances, particularly iodine-131 and cesium-137, are described. Also discussed are the steps that have been taken by different international organizations to set limits on acceptable radioactivity in food.15 references

  3. Radioactive air sampling methods

    CERN Document Server

    Maiello, Mark L

    2010-01-01

    Although the field of radioactive air sampling has matured and evolved over decades, it has lacked a single resource that assimilates technical and background information on its many facets. Edited by experts and with contributions from top practitioners and researchers, Radioactive Air Sampling Methods provides authoritative guidance on measuring airborne radioactivity from industrial, research, and nuclear power operations, as well as naturally occuring radioactivity in the environment. Designed for industrial hygienists, air quality experts, and heath physicists, the book delves into the applied research advancing and transforming practice with improvements to measurement equipment, human dose modeling of inhaled radioactivity, and radiation safety regulations. To present a wide picture of the field, it covers the international and national standards that guide the quality of air sampling measurements and equipment. It discusses emergency response issues, including radioactive fallout and the assets used ...

  4. ORNL radioactive waste operations

    International Nuclear Information System (INIS)

    Sease, J.D.; King, E.M.; Coobs, J.H.; Row, T.H.

    1982-01-01

    Since its beginning in 1943, ORNL has generated large amounts of solid, liquid, and gaseous radioactive waste material as a by-product of the basic research and development work carried out at the laboratory. The waste system at ORNL has been continually modified and updated to keep pace with the changing release requirements for radioactive wastes. Major upgrading projects are currently in progress. The operating record of ORNL waste operation has been excellent over many years. Recent surveillance of radioactivity in the Oak Ridge environs indicates that atmospheric concentrations of radioactivity were not significantly different from other areas in East Tennesseee. Concentrations of radioactivity in the Clinch River and in fish collected from the river were less than 4% of the permissible concentration and intake guides for individuals in the offsite environment. While some radioactivity was released to the environment from plant operations, the concentrations in all of the media sampled were well below established standards

  5. Radiological control in a mine with a naturally-occurring radioactive material -NORM: III assessment of removable surface contamination in a pilot plant

    Energy Technology Data Exchange (ETDEWEB)

    Pereira, W.S.; Py Junior, D.A.; Silva, A.C.A.; Garcia Filho, O., E-mail: pereiraws@gmail.com [Industrias Nucleares do Brasil (INB), Pocos de Caldas, MG (Brazil). Unidade de Tratamento de Minerio. Grupo Multidisciplinar de Radioprotecao; Kelecom, A., E-mail: akelecom@id.uff.br [Universidade Federal Fluminense (GETA/LARARA-PLS/UFF), Niteroi, RJ, (Brazil). Grupo de Estudos em Temas Ambientais. Lab. de Radiobiologia e Radiometria; Pereira, J.R.S., E-mail: pereirarsj@gmail.com [Universidade Federal de Alfenas (UNIFAL), Pocos de Caldas, MG (Brazil)

    2013-07-01

    Ore Treatment Unit (OUT) possesses a process laboratory. Considering the uranium ore processing, this laboratory works in close cooperation with the Radiation Protection Service of the Unit. In the year of 2009 a pilot plant for the development of solvent uranium extraction from the phosphate ore of the mine of Santa Quiteria city, in Ceara State, Brazil was developed. In this kind of plant the surface contamination may cause contamination for Occupational Exposed Individuals (OEI). In order to control this kind of contamination and offer a safety work's condition for OEIs, a monitoring program of transferable contamination using swab samples was developed. 162 swabs were made. For the alpha emitters the monitoring results varied from 0.001 Bq cm{sup -2} to 0.014 Bq cm{sup -2}, with average value of 0.002 Bq cm{sup -2}. For beta emitters the results varied from 0.010 Bq cm{sup -2} to 0.031 Bq cm{sup -2} with average equal to 0.011 Bq cm{sup -2}. For alpha emitters, 87.65 % of the results were below 0.004 Bq cm{sup -2}, values that are one order of magnitude smaller than the limit and the maximum value stayed in 35 % of the limit for an object to be considered contaminated. For beta emitters, 90 % of the results were below 0.010 Bq cm{sup -2} that corresponds to 25 % of the limit and 100 % were below 0.031 Bq cm{sup -2} below the limit for an object to be considered contaminated. In both cases any object monitored during the operation, was not considered contaminated, proving the good practices employed in the laboratory, resultant of the good planning of the Radiation Protection Service for the operations' process. (author)

  6. Radiological control in a mine with a naturally-occurring radioactive material -NORM: III assessment of removable surface contamination in a pilot plant

    International Nuclear Information System (INIS)

    Pereira, W.S.; Py Junior, D.A.; Silva, A.C.A.; Garcia Filho, O.

    2013-01-01

    Ore Treatment Unit (OUT) possesses a process laboratory. Considering the uranium ore processing, this laboratory works in close cooperation with the Radiation Protection Service of the Unit. In the year of 2009 a pilot plant for the development of solvent uranium extraction from the phosphate ore of the mine of Santa Quiteria city, in Ceara State, Brazil was developed. In this kind of plant the surface contamination may cause contamination for Occupational Exposed Individuals (OEI). In order to control this kind of contamination and offer a safety work's condition for OEIs, a monitoring program of transferable contamination using swab samples was developed. 162 swabs were made. For the alpha emitters the monitoring results varied from 0.001 Bq cm -2 to 0.014 Bq cm -2 , with average value of 0.002 Bq cm -2 . For beta emitters the results varied from 0.010 Bq cm -2 to 0.031 Bq cm -2 with average equal to 0.011 Bq cm -2 . For alpha emitters, 87.65 % of the results were below 0.004 Bq cm -2 , values that are one order of magnitude smaller than the limit and the maximum value stayed in 35 % of the limit for an object to be considered contaminated. For beta emitters, 90 % of the results were below 0.010 Bq cm -2 that corresponds to 25 % of the limit and 100 % were below 0.031 Bq cm -2 below the limit for an object to be considered contaminated. In both cases any object monitored during the operation, was not considered contaminated, proving the good practices employed in the laboratory, resultant of the good planning of the Radiation Protection Service for the operations' process. (author)

  7. Vertical and Horizontal Mixing Rates of Radioactive Material in the Ocean; Taux de Melange Vertical et Horizontal des Matieres Radioactives Contenues dans l'Ocean; 0421 041a 041e 0420 041e 0421 0422 0414 ; Velocidades de Mezcla Vertical y Horizontal de Sustancias Radiactivas en las Aguas del Oceano

    Energy Technology Data Exchange (ETDEWEB)

    Miyake, Y.; Saruhashi, K. [Geochemical Laboratory, Meteorological Research Institute, Tokyo (Japan)

    1960-07-01

    Observations on the vertical distribution of radioactivity in the Pacific Ocean showed that presence of activity was mostly limited to the mixed layer above the thermocline in June 1954 (Miyake, Sugiura and Kameda, 1954). In March 1955, however, the activity extended down to about 600 m below the surface, the thermocline being present at the depth of 75 m (operation Troll, USAEC, 1956). If there is any biological transport of radioactive material in a vertical direction in sea-water, migration of plankton might be more effective than decomposition of organic debris in transporting radioactive material, although it would be only 10-20% of the physical mixing rate. When radioactive material diffuses out from a source point, the horizontal eddy diffusion coefficient may be obtained from the time change of the distribution of the activity. (author) [French] Il ressort des observations sur la repartition verticale de la radioactivite dans l'ocean Pacifique que l'activite, en juin 1954, etait presque entierement limitee a la couche mixte situee au-dessus du gradient thermique. Cependant, en mars 1955, l'activite s'etendait jusqu'aux environs de 600 m au-dessous de la surface, le gradient thermique se situant a une profondeur de 75 m (operation Troll, USAEC 1956). Si donc il y a un transport biologique quelconque de matieres radioactives dans le sens vertical, la migration de planctons pourrait etre plus efficace que la decomposition des debris organiques pour le transport de matieres radioactives alors qu'elle ne representerait que 10 a 20 pour cent du taux de melange physique. Lorsqu'une matiere est diffusee a partir d'une source, le coefficient de diffusion horizontale des remous peut etre calcule d'apres la modification du temps de repartition de l'activite. (author) [Spanish] Los estudios realizados sobre la distribucion vertical de la radiactividad en el oceano Pacifico pusieron de manifiesto que, en junio de 1954, dicha actividad se circunscribia principalmente a

  8. Radioactivity and its measurement

    CERN Document Server

    Mann, W B; Garfinkel, S B

    1980-01-01

    Begins with a description of the discovery of radioactivity and the historic research of such pioneers as the Curies and Rutherford. After a discussion of the interactions of &agr;, &bgr; and &ggr; rays with matter, the energetics of the different modes of nuclear disintegration are considered in relation to the Einstein mass-energy relationship as applied to radioactive transformations. Radiation detectors and radioactivity measurements are also discussed

  9. Radioactive wastes and discharges

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-07-01

    The guide sets out the radiation safety requirements and limits for the treatment of radioactive waste. They shall be observed when discharging radioactive substances into the atmosphere or sewer system, or when delivering solid, low-activity waste to a landfill site without a separate waste treatment plan. The guide does not apply to the radioactive waste resulting from the utilisation of nuclear energy or natural resources.

  10. Learning more about radioactivity

    International Nuclear Information System (INIS)

    2008-01-01

    This digest brochure explains what radioactivity is, where it comes from, how it is measured, what are its effects on the body and the way to protect it against these effects, the uses of radioactivity (In the medical field, In industry, In the food industry, and In the cultural world). It ends with some examples of irradiation levels, of natural radioactivity and with the distribution in France of various sources of exposure. (J.S.)

  11. Radioactive waste management

    International Nuclear Information System (INIS)

    2003-01-01

    Almost all IAEA Member States use radioactive sources in medicine, industry, agriculture and scientific research, and countries remain responsible for the safe handling and storage of all radioactively contaminated waste that result from such activities. In some cases, waste must be specially treated or conditioned before storage and/or disposal. The Department of Technical Co-operation is sponsoring a programme with the support of the Nuclear Energy Department aimed at establishing appropriate technologies and procedures for managing radioactive wastes. (IAEA)

  12. Handling of radioactive waste

    International Nuclear Information System (INIS)

    Sanhueza Mir, Azucena

    1998-01-01

    Based on characteristics and quantities of different types of radioactive waste produced in the country, achievements in infrastructure and the way to solve problems related with radioactive waste handling and management, are presented in this paper. Objectives of maintaining facilities and capacities for controlling, processing and storing radioactive waste in a conditioned form, are attained, within a great range of legal framework, so defined to contribute with safety to people and environment (au)

  13. Radioactive wastes and discharges

    International Nuclear Information System (INIS)

    2000-01-01

    The guide sets out the radiation safety requirements and limits for the treatment of radioactive waste. They shall be observed when discharging radioactive substances into the atmosphere or sewer system, or when delivering solid, low-activity waste to a landfill site without a separate waste treatment plan. The guide does not apply to the radioactive waste resulting from the utilisation of nuclear energy or natural resources

  14. Radiation surveys of radioactive material shipments

    International Nuclear Information System (INIS)

    Howell, W.P.

    1986-07-01

    Although contractors function under the guidance of the Department of Energy, there is often substantial variation in the methods and techniques utilized in making radiation measurements. When radioactive materials are shipped from one contractor to another, the measurements recorded on the shipping papers may vary significantly from those measured by the receiver and has been a frequent cause of controversy between contractors. Although significant variances occur in both measurements of radiation fields emanating from shipment containers and measurements of residual radioactivity on the surfaces of the containers, the latter have been the most troublesome. This report describes the measurement of contamination on the exterior surfaces of shipment containers

  15. Safety in the management of radioactive substances

    International Nuclear Information System (INIS)

    Balter, Henia; Rey, Ana; Leon, Alba; Jelen, Miguel

    1994-01-01

    A brief explanation of radiation protection,external irradiation,internal contamination,risk factors, active laboratory design,localization,ventilation,working surfaces,area distribution,classification of active laboratory.Radiopharmacy laboratory,shielding, area monitoring,personal dosimetry,rules for management of open sources,maximum admitted limits for radionuclides currently used in radiopharmacy.Decontamination of active areas and materials,surfaces,equipment s.Decontamination of hands.Waste disposal.Radioactive materials transportation.Reception of radioactive materials.Bibliography

  16. Radioactive Decontamination by Strippable Paint

    International Nuclear Information System (INIS)

    Chantaraparprachoom, N.; Mishima, K.

    1998-01-01

    The strippable paint, one of the adhesion method, is to decontaminate solid surface of materials or/and a large area. Two kinds of specimen planchet, SUS 304 stainless steel and polycarbonate plastic, contaminated with radioactive 137 Cs were studied under various conditions. It included surface bottom types, the flat and convex concentric circle type, normal condition at room temperature and overheat condition (∼80 degree celsius). This method used coating paints which contains some elements to have a reaction with radioactive materials selectively. ALARA-Decon clear, Rempack-X200 clear, JD-P5-Mrs.Coat and Pro-Blue-color guard were selected to use as the coating paints. The contaminated surface was coated by the strippable paint under the optimum time, followed by peeling the paint seal. The Rempack-X200 showed the best result, the highest decontamination efficiency which are about 99-100% for all conditions of specimens. The JD-P5 and ALARA-Decon showed good results, which are 98-99% decontamination efficiency for the normal condition set of specimens and about 94-97% for the overheat set of specimens. They can decontaminate polycarbonate specimens better than stainless steel specimens. The Pro-Blue-color guard showed the lowest decontamination efficiency of which 60% for polycarbonate specimens at normal condition and 40%, 30% for stainless steel specimens at normal and overheat conditions respectively. There was no effects of surface bottom types significantly

  17. Radioactive waste disposal process geological structure for the waste disposal

    International Nuclear Information System (INIS)

    Courtois, G.; Jaouen, C.

    1983-01-01

    The process described here consists to carry out the two phases of storage operation (intermediate and definitive) of radioactive wastes (especially the vitrified ones) in a geological dispositif (horizontal shafts) at an adequate deepness but suitable for a natural convection ventilation with fresh air from the land surface and moved only with the calorific heat released by the burried radioactive wastes when the radioactive decay has reached the adequate level, the shafts are totally and definitely occluded [fr

  18. Radioactive droplet moisture transfer from nuclear power plant spray pool

    International Nuclear Information System (INIS)

    Elokhin, A.P.

    1995-01-01

    Problem on transfer of radioactive droplet moisture with an account of its evaporation from the nuclear power plant spray pool (NPP coolant) is considered. Formulae enabling evaluation of droplet and radioactive water admixture lifetime as a whole, as well as the maximum distance (by wind), over which it can extend, are obtained. Recommendations for decrease in the droplet dispersed composition and reduction in scale of radioactive contamination of underlying surface are given. 10 refs.; 3 figs.; 1 tab

  19. Surface decontamination

    International Nuclear Information System (INIS)

    Silva, S. da; Teixeira, M.V.

    1986-06-01

    The general methods of surface decontamination used in laboratory and others nuclear installations areas, as well as the procedures for handling radioactive materials and surfaces of work are presented. Some methods for decontamination of body external parts are mentioned. The medical supervision and assistance are required for internal or external contamination involving or not lesion in persons. From this medical radiation protection decontamination procedures are determined. (M.C.K.) [pt

  20. Deposition of radioactive corrosion products on the internal surfaces of tube elements in gaseous phase of dissociating system N2O4 reversible 2NO2 reversible 2NO+O2

    International Nuclear Information System (INIS)

    Gol'tsev, V.P.; Dolgov, V.M.; Katanaev, A.O.

    1979-01-01

    Analysis of experimental data, obtained as a result of γ-scanning of tube element samples of loop assembling with dissociating coolant contacting with N 2 O 4 gaseous phase is presented. Radioactive depositions are differentiated on fixed and unfixed ones by the method of radiochemical analysis. The data obtained have made it possible to establish the analytical form of radioactive element distribution functions along the piping length. It is noted, that relative quantities of radioactive isotopes, existing in fixed and unfixed depositions vary with temperature. The fraction of soluble forms of corrosion radioactive products in unfixed depositions increases both with the decrease of temperature and after passing of radioactive impurity through the zone of liquid coolant