WorldWideScience

Sample records for des matieres radioactives

  1. The transport safety of radioactive matters; La surete des transports des matieres radioactives

    Energy Technology Data Exchange (ETDEWEB)

    Landier, D.; Louet, Ch.A.; Robert, Ch. [Autorite de Surete Nucleaire, 75 - Paris (France); Binet, J. [Commission europeenne, DG Energie et transports, Bruxelles (Belgium); Malesys, P. [TN International, 75 - Paris (France); Pourade, C. [Societe Dangexpress, 78 - St Remy l' Honore (France); Le Meur, A.; Robert, M. [Societe Nationale des Chemins de fer Francais, 75 - Paris (France); Turquet de Beauregard, G.Y.; Hello, E. [CIS bio, 91 - Gif sur Yvette (France); Laumond, A. [Electricite de France (EDF), 75 - Paris (France); Regnault, Ph.; Gourlay, M. [AREVA NC, 78 - Velizy Villacoublay (France); Bruhl, G. [CEA Fontenay-aux-Roses, Dir. de la Protection et de la Surete Nucleaire, 92 (France); Malvache, P.; Dumesnil, J. [CEA Saclay, Dir. de l' Energie Nucleaire (DEN), 91 - Gif sur Yvette (France); Cohen, B. [Agence Nationale pour la Gestion des Dechets Radioactifs (ANDRA), 92 - Chatenay Malabry (France); Sert, G. [Institut de Radioprotection et de Surete Nucleaire (IRSN), 92 - Clamart (France); Pain, M. [Ministere de l' Interieur, et de l' Amenagement du Territoire, Dir. de la Defense et la Securite Civiles, 75 - Paris (France); Green, L.; Hartenstein, M. [World Nuclear Transport Institute, London (United Kingdom); Stewart, J. [Ministere des Transport, Royaume Uni (United Kingdom); Cottens, E.; Liebens, M. [Agence Federale de Controle Nucleaire (Belgium); Marignac, Y. [Wise, 75 - Paris (France)

    2007-02-15

    Since the control of transport of radioactive materials was given to A.S.N. 10 years ago, A.S.N. has strengthened the radioactive material transport inspections, in particular of the designers, manufacturers, carriers and consignors. A.S.N. has implemented INES scale for incidents during transport. It has participated as much as possible to IAEA working groups in order to improve the international regulatory framework. And, supported by I.R.S.N., A.S.N. has performed a periodic safety review of existing package models and has approved new models incorporating innovative design features. Finally, A.S.N. has tested its emergency responses to procedures to an accident involving the transport of radioactive materials. All these actions taken together have led to improvement in and reinforcement of the safety culture among the transport operators; this has been acknowledged by a recent audit T.R.A.N.S.A.S. performed by IAEA. In spite of all these actions, there are not approved by the competent authority. As A.S.N. is in charge of every field in radioprotection, this should help to intensify the control. In addition, the different kinds of transport are also tackled as rail transport with S.N.C.F. radiological risk training, air transport through nuclear medicine. Some experience feedback are given such radioactive waste transport to the storage facilities in the Aube or how to protect the population after a nuclear transport incident with the O.R.S.E.C.-T.M.S. plans. (N.C.)

  2. Dossier: transport of radioactive materials; Dossier: le transport des matieres radioactives

    Energy Technology Data Exchange (ETDEWEB)

    Mignon, H. [CEA Centre d`Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Direction du Cycle du Combustible; Niel, J.Ch. [CEA Centre d`Etudes Nucleaires de Fontenay-aux-Roses, 92 (France). Inst. de Protection et de Surete Nucleaire; Canton, H. [CEA Cesta, 33 - Bordeaux (France); Brachet, Y. [Transnucleaire, 75 - Paris (France); Turquet de Beauregard, G.; Mauny, G. [CIS bio international, France (France); Robine, F.; Plantet, F. [Prefecture de la Moselle (France); Pestel Lefevre, O. [Ministere de l`Equipement, des transports et du logement, (France); Hennenhofer, G. [BMU, Ministere de l`environnement, de la protection de la nature et de la surete des reacteurs (Germany); Bonnemains, J. [Association Robin des Bois (France)

    1997-12-01

    This dossier is entirely devoted to the transportation of radioactive and fissile materials of civil use. It comprises 9 papers dealing with: the organization of the control of the radioactive materials transport safety (safety and security aspects, safety regulations, safety analysis and inspection, emergency plans, public information), the technical aspects of the regulation concerning the transport of radioactive materials (elaboration of regulations and IAEA recommendations, risk assessments, defense in depth philosophy and containers, future IAEA recommendations, expertise-research interaction), the qualification of containers (regulations, test facilities), the Transnucleaire company (presentation, activity, containers for spent fuels), the packages of radioactive sources for medical use (flux, qualification, safety and transport), an example of accident during radioactive materials transportation: the Apach train derailment (February 4, 1997), the sea transport of radioactive materials (international maritime organization (OMI), international maritime dangerous goods (IMDG) code, irradiated nuclear fuel (INF) safety rules), the transport of radioactive materials in Germany, and the point of view from an external observer. (J.S.)

  3. The safety of radioactive materials transport; La surete des transports de matieres radioactives

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    The rule of the radioactive materials transport contains two different objectives: the safety, or physical protection, consists in preventing the losses, the disappearances, the thefts and the diversions of the nuclear materials (useful materials for weapons); the high civil servant of defence near the Minister of Economy, Finance and Industry is the responsible authority; the safety consists in mastering the risks of irradiation, contamination and criticality presented by the radioactive and fissile materials transport, in order that man and environment do not undergo the nuisances. The control of the safety is within the competence of the Asn. (N.C.)

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

    Energy Technology Data Exchange (ETDEWEB)

    Dupuis, M.C

    2006-07-01

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

  5. Survey of radiation protection programmes for transport; Etude des programmes de radioprotection pour les transports de matieres radioactives

    Energy Technology Data Exchange (ETDEWEB)

    Lizot, M.T.; Perrin, M.L.; Sert, G. [CEA Fontenay-aux-Roses, Inst. de Protection et de Surete Nucleaire, Dept. de Protection et de Surete Nucleaire, 92 (France); Lange, F.; Schwarz, G.; Feet, H.J.; Christ, R. [Gesellschaft fur Anlagen-und Reaktorsicherheit, GRS, mbH, Cologne (Germany); Shaw, K.B.; Hughes, J.S.; Gelder, R. [National Radiological Protection Board (NRPB), Oxon, OX (United Kingdom)

    2001-07-01

    The survey of radiation protection programmes for transport has been jointly performed by three scientific organisations I.P.S.N. (France), G.R.S. ( Germany), and N.R.P.B. (United kingdom) on behalf of the European Commission and the pertaining documentation summarises the findings and conclusions of the work that was undertaken with the principal objectives to provide guidance on the establishment, implementation and application of radiation protection programmes for the transport of radioactive materials by operators and the assessment and evaluation of such programmes by the competent authority and to review currently existing radiation protection programmes for the transport of radioactive materials. (N.C.)

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-01-15

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

  8. Transport of radioactive materials of the C. A. E. [CEA (France)]. Le transport des matieres radioactives au C.E.A.

    Energy Technology Data Exchange (ETDEWEB)

    Labrousse, M.

    1974-03-15

    Since the publication, in 1967, of the two issues of the Bull. Inform. Sci. Tech. devoted to the transport of radioactive materials, an important evolution has taken place, bearing both on the nature of the transports--where natural uranium hexafluoride, irradiated fuel, and wastes are becoming comparatively more important than miscellaneous small packages--and the construction of packagings, which are becoming more and more elaborate. This evolution appears in the reports selected for the BIST that are briefly introduced. (8 fig.)

  9. Regulations for the Safe Transport of Radioactive Material. 2012 Edition. Specific Safety Requirements (French Edition); Reglement de transport des matieres radioactives. Edition de 2012

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-03-15

    The IAEA's Statute authorizes the Agency to ''establish or adopt standards of safety for protection of health and minimization of danger to life and property'' - standards that the IAEA must use in its own operations, and which States can apply by means of their regulatory provisions for nuclear and radiation safety. The IAEA does this in consultation with the competent organs of the United Nations and with the specialized agencies concerned. A comprehensive set of high quality standards under regular review is a key element of a stable and sustainable global safety regime, as is the IAEA's assistance in their application. The IAEA commenced its safety standards programme in 1958. The emphasis placed on quality, fitness for purpose and continuous improvement has led to the widespread use of the IAEA standards throughout the world. The Safety Standards Series now includes unified Fundamental Safety Principles, which represent an international consensus on what must constitute a high level of protection and safety. With the strong support of the Commission on Safety Standards, the IAEA is working to promote the global acceptance and use of its standards. Standards are only effective if they are properly applied in practice. The IAEA's safety services encompass design, siting and engineering safety, operational safety, radiation safety, safe transport of radioactive material and safe management of radioactive waste, as well as governmental organization, regulatory matters and safety culture in organizations. These safety services assist Member States in the application of the standards and enable valuable experience and insights to be shared. Regulating safety is a national responsibility, and many States have decided to adopt the IAEA's standards for use in their national regulations. For parties to the various international safety conventions, IAEA standards provide a consistent, reliable means of ensuring the effective fulfilment of obligations under the

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

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

  11. 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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-15

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

  13. 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.)

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-02-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-02-15

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

  18. Two Cases of Chronic Occupational Exposure to Radioactive Materials; Deux Cas d'Exposition Professionnelle Chronique a des Matieres Radioactives; 0414 0412 0414 ; Dos Casos de Exposicion Cronica Profesional a Sustancias Radiactivas

    Energy Technology Data Exchange (ETDEWEB)

    Rundo, J. [United Kingdom Atomic Energy Authority, Atomic Energy Research Establishment, Harwell, Berks. (United Kingdom)

    1964-11-15

    This paper describes the results and interpretation of measurements of radioactivity in the bodies and in the excreta of two subjects with a long (up to 16 yr) history of exposure to radium-226, strontium-90 and thorium-228. Measurements were made in 1957, 1959, 1960 and 1963. The radium content of subject A showed no perceptible decrease between 1957 (0.13 {mu}c) and 1963 (0.14 {mu}c), and it was more than 30% higher in 1959. The excretion rate observed in 1957 was consistent, on the power function retention model, with a chronic intake of about 2 nc/d for the previous 10 yr, while the much lower excretion rate in 1963 indicated that there had not been a recent intake. The radium content of subject B decreased from 1.19 {mu}c in 1959 to 1.07 {mu}c in 1963, at a rate corresponding to a biological half-life of about 25 yr, yet the excretion rate in 1963 suggested a much faster fall in body content. This suggested that there had been a small intake of radium not long before. The strontium-90 content of subject A decreased. from 5.0 {mu}c in 1957 to 3.0 {mu}c in 1963, corresponding to a biological half-life of about 9 yr. Consideration of a power function retention model for strontium in man showed that the findings were consistent with a chronic intake for four years up to 1957 and then no further large intake, although as the excretion rate observed in 1963 was at least five times greater than that calculated there may have been a small intake shortly before the measurements in 1963. The retention of strontium-90 by subject B indicated a biological half-life of about 6 yr, agreeing with that deduced from the excretion rate (4.5 - 8.0 yr). After an initial four-fold increase, the thorium-228 content of subject A decreased exponentially between 1959 and 1963 with an effective half-life of at least 1.4 yr. Subject B's content increased from 1959 to 1960, but the decrease from 1960 to 1963 was not significantly different from that due to radioactive decay with a half

  19. Taking into account the dissemination risk of radioactive materials in the French fuel cycle factories; La prise en compte du risque de dissemination des matieres radioactives dans les usines du cycle du combustible en France

    Energy Technology Data Exchange (ETDEWEB)

    Ruiz, J

    1994-12-31

    In this text the conception principles retained for treating the dissemination risk of radioactive matters in the French fuel cycle factories are presented. For taking into account this risk successives containment systems are used with respects to the ventilation regulations and fire protection.

  20. Guide relative to the regulatory requirements applicable to the radioactive materials transport in airport area; Guide relatif aux exigences reglementaires applicables au transport des matieres radioactives en zone aeroportuaire

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-02-15

    This guide makes an inventory of all the points necessary for the correct functioning of the transport of radioactive materials in airport zone. Stowage of the parcels, program of radiological protection (P.R.P.), operation of transport, quality assurance, radiation dose evaluation, radiation monitoring, dose optimization, storage management, are the principal points of this guide. (N.C.)

  1. 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)

  2. statut de la matiere organique des cambisols et des lixisols sous

    African Journals Online (AJOL)

    Administrateur

    L'étude vise à évaluer la matière organique des Cambisols et des Lixisols sous formations naturelles de longue durée en zone climatique nord-soudanienne et à établir, les relations entre ... sont supérieures à celles des sols des zones sahélienne et sud-soudanienne. ... globale a eu une corrélation positive avec le pH.

  3. The energy outlook in China-Minutes from the seminar organised by the Centre Geopolitique de l'Energie et des Matieres Premieres

    International Nuclear Information System (INIS)

    Keppler, J.H.; Meritet, S.

    2004-01-01

    As part of the seminars that are organised on a regular basis, the Centre de Geopolitique de l'Energie et des Matieres Premieres has devoted, on the 2. of June, a day to China, its energetics outlook and the resulting economic and geopolitical challenges. (authors)

  4. Presentation of the program law of the 28 June 2006 relative to the sustainable management of radioactive materials and wastes; Presentation de la loi de programme du 28 juin 2006 relative a la gestion durable des matieres et des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    The french law of 1991, decided to define management solutions in the radioactive wastes management policy, is now over. The results of researches led to the promulgation of a new planing act, the law of the 28 June 2006. This law concerns the sustainable management of radioactive materials and wastes. It takes also in account a public debate, organized in September 2005 by the National Commission for Public Debate. The Law project architecture can be described in three main points: the implementing of a national policy of radioactive materials and wastes, a better transparency and democratic control and the implementing of specific modalities for the organization and the financing of spent fuels and radioactive wastes management. The law sets 2015 as deadline to submit the statutory application in order to commission a deep geological repository for high-level and long-lived radioactive wastes. (A.L.B.)

  5. Applicant guide for the demands of expedition and agreement approval of the parcel or radioactive matter models for civil use transported on the public highway; Guide du requerant pour les demandes d'approbation d'expedition et d'agrement des modeles de colis ou de matieres radioactives a usage civil transportes sur la voie publique

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-03-15

    This guide applies to the models of parcels or radioactive materials for which an approval of the competent authorities is required by the regulations of the dangerous goods transportations. It is about models used for: radioactive materials under special shape, lowly dispersible radioactive materials, packages containing 0.1 kg or more of uranium hexafluoride, any package containing fissile materials, the B(U) type packages, and the B(M) type packages; the C type packages. (N.C.)

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

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

  7. 1. round table - Nuclear wastes and radioactive materials. 2. round table - risks linked with nuclear wastes and materials. 3. round table - the problem of long-term management of medium-high activity and long lived wastes. The process defined by the 1991 law; 1. table ronde - dechets nucleaires et matieres radioactives. 2. table ronde - Les risques des dechets et matieres nucleaires. 3. table ronde - Le probleme de la gestion a long terme des dechets a MA/HAVL. Le processus defini par la loi de 1991

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    The law from December 30, 1991, precisely defines 3 axes of researches for the management of high level and long-lived radioactive wastes: separation/transmutation, surface storage and underground disposal. A global evaluation report about these researches is to be supplied in 2006 by the French government to the Parliament. A first synthesis of the knowledge gained after 14 years of research has led the national commission of the public debate (CNDP) to organize a national debate about the general options of management of high-level and long-lived radioactive wastes before the 2006 date line. The debate comprises 4 public hearings (September 2005: Bar-le-Duc, Saint-Dizier, Pont-du-Gard, Cherbourg), 12 round-tables (October and November 2005: Paris, Joinville, Caen, Nancy, Marseille), a synthesis meeting (December 2005, Dunkerque) and a closing meeting (January 2006, Lyon). This document is the synthesis of the debates of the first round table of Paris about the problems raised by nuclear wastes in the case of the geologic disposal option. Four families of questions have been tackled: 1 - the exhaustiveness of ANDRA's inventory, the solutions foreseen for the different types of wastes; 2 - the high-medium activity wastes and their processing; 3 - the management of non-reprocessed spent MOX fuels; 4 - the safety and security standards used and their establishment. Four presentations are attached to these proceedings and deal with: the measured and estimated inventory of all radioactive wastes; the inventory and management of radioactive wastes and the place of citizens; the point of view of the nuclear safety authority; conditioning and storage. (J.S.)

  8. Declinaisons militaires francaises des directives europeennes en matiere d’hemovigilance (French European Military Haemovigilance Guidelines)

    Science.gov (United States)

    2010-11-03

    du groupe sanguin A B O D et d’un dépistage du VIH et du VHC. Sauf exception (donneur originaire de zones endémiques pour le VHB, non contrôlé avant...réalisées les sérologies VIH , VHC et VHB pré-transfusionnelles. Pour fiabiliser cette procédure assez complexe, le CTSA assure la formation...sont contrôlés pour le VIH avant le départ en mission. Enfin, sur le terrain, les aphé- rèses sont pratiquées sur des donneurs réguliers. A

  9. Professional Nuclear Materials Management; Gestion Industrielle des Matieres Nucleaires; Obrashchenie s yadernymi materialami na professional'nom urovne; Administracion Eficiente de Materiales Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Forcella, A. A.; O' Leary, W. J. [Allis-Chalmers Manufacturing Company, Bethesda, MD (United States)

    1966-02-15

    . (author) [French] Le memoire expose en quoi consiste la gestion des matieres nucleaires dans une centrale nucleaire type, aux Etats-Unis. Comme le reacteur en question est partiellement finance a l'aide de capitaux prives, l'une des principales obligations de l'exploitant est d'assurer la protection et la rentabilite des investissements. Etant donne que les matieres nucleaires sont d'une valeur intrinseque elevee, il faut constamment proceder a des controles appropries allant au-dela des mesures de securite et de la comptabilite interessant les matieresnucleaires proprement dites afin de reduire les pertes au minimum. Il faut faire preuve de clairvoyance et planifier judicieusement pour prevenir toute perte supplementaire de capital provenant de frais inutiles ou d'un manque a gagner dans divers secteurs de l'exploitation. C'est ainsi que le gestionnaire de matieres nucleaires doit prendre des dispositions pour garantir la bonne marche des operations et assurer le respect des plans d'execution par une liaison et un controle constants, dans les domaines suivants? a) acquisition du combustible et des elements combustibles, b) utilisation des elements combustibles dans le reacteur et c) recuperation, dans le combustible irradie, des produits et matieres presentant de l'interet. Pendant la periode qui precede l'utilisation du reacteur, il faut faire une place importante dans la planification et les travaux preparatoires aux considerations d'economie dans la conception des elements combustibles, en ce qui concerne leur fabrication, leur manutention, leur transport et leur remplacement. Les differentes etapes de la fabrication doivent etre planifiees de facon a reduire au minimum le manque a gagner du a des periodes improductives d'entreposage de matieres tres couteuses. Pendant la marche du reacteur, il faut assurer une combustion maximale de la matiere fissile par des redistributions appropriees du combustible dans le coeur du reacteur. Parallelement, les temps morts dus a

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

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

  11. Report realized on behalf of the economic affairs, the environment and the territory commission on the law project, after urgency declaration, of the program relative to the sustainable management of materials and radioactive wastes; Rapport fait au nom de la commission des affaires economiques, de l'environnement et du territoire sur le projet de loi, apres declaration d'urgence, de programme relatif a la gestion des matieres et des dechets radioactifs (n. 2977)

    Energy Technology Data Exchange (ETDEWEB)

    Birraux, C

    2006-03-15

    In 1991 the France decided to intensify its researches in the high activity radioactive wastes management domain. The law of the 30 December 1991 relative to the radioactive wastes management, decided that a period of 15 years would be devoted to the research of very long dated solutions. Taking into account these researches, a law project has been composed. After a recall of the today situation of radioactive materials and wastes in France and the knowledge since 1991, this document presents the law project. (A.L.B.)

  12. 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)

  13. Report realized by the commission of the economical Affairs on the law project, adopted by the National Assembly after urgency declaration, of the program relative to the sustainable management of the radioactive materials and wastes; Rapport fait au nom de la commission des Affaires economiques sur le projet de loi, adopte par l'Assemblee Nationale apres declaration d'urgence, de programme relatif a la gestion durable des matieres et des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Revol, H

    2006-07-01

    In the framework of a sustainable development and of the nuclear energy development, the France decided by the law of the 30 December 1991, to study three axis or researches: the radioactive wastes transmutation, their deep underground disposal and their storage during ten years. Today, after evaluation of the researches results a law project on the sustainable management of the radioactive materials and wastes, has been prepared. This document is the approval of the law project and presents some amendments. (A.L.B.)

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

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

  15. The main evolutions brought by the parliamentary examination to the program law relative to the sustainable management of radioactive materials and wastes; Les principales evolutions apportees par l'examen parlementaire a la loi de programme relative a la gestion durable des matieres et dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

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

  16. Non-destructive analysis of major components in plant materials by mean of 14-MeV neutrons; Analyse ''non destructrice'' des principaux constituants de la matiere vegetale apres irradiation aux neutrons de 14 MeV

    Energy Technology Data Exchange (ETDEWEB)

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

    1968-07-01

    (n,p) , (n,{alpha}) et (n,2n). Les recherches actuelles portent sur l'exploitation complete du spectre gamma de matiere vegetale activee. Le spectre est decompose en 7 spectres principaux suivant La methode des moindres carres, par une calculatrice. En premiere approximation, ce sont ceux que donnent des etalons d'aluminium, de calcium, de potassium, de magnesium, de phosphore, de silicium et de chlore, dans des conditions standard d'activation et de decroissance radioactive. L'avantage recherche par ce moyen d'analyse n'est pas l'extreme sensibilite, mais la rapidite et, par cela, il est particulierement bien adapte aux dosages rapides et simultanes d'elements interessant l'agronomie. (auteur)

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-09-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-01-15

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

  19. National assessment board for research and the studies into the management of radioactive waste and materials instituted by the law no.2006-739 of June 28, 2006 - Assessment report No. 5; Commission nationale d'evaluation des recherches et etudes relatives a la gestion des matieres et des dechets radioactifs instituee par la loi no. 2006-739 du 28 juin 2006 - Rapport d'evaluation No. 5

    Energy Technology Data Exchange (ETDEWEB)

    Duplessy, Jean-Claude; Baechler, Jean; Berest, Pierre; Brechet, Yves; Deconinck, Frank; Laurent, Maurice; Ledoux, Emmanuel; Leroy, Maurice; Percebois, Jacques; Roure, Francois; Thegerstroem, Claes; Kerboul, Claire; Tissot, Bernard; Jouvance, Chantal; Ledoux, Florence

    2011-11-15

    The law provides that long-term management of long-lived, high-level waste comprises two aspects, which are not mutually exclusive: the partitioning and transmutation of the actinides present in spent fuel from nuclear reactors, and the geological disposal of long-lived high- and intermediate-level waste. This report is organised to reflect the two complementary aspects of R and D on the management of radioactive waste and materials: partitioning and transmutation (chapter 1), and the storage and disposal of LLHL and LLIL waste (chapter 2). In 2011 the Board decided to go into detail on the subject of the potential impact of transmutation of actinides on the disposal of the waste produced in the future, in a set of reactors suitable for multi-recycling. This question is dealt with in two chapters of the report. The Board continues to observe the overall international situation (chapter 3), and this year devoted an entire hearing to the different visions of the nuclear cycle held throughout the world. This hearing took place a few weeks before the accident in Fukushima. Contents: Chapter 1 - Partitioning and transmutation: scientific and technical context; transmutation and multi-recycling (Three important actinides potentially concerned by transmutation: Plutonium, Americium, Curium; Transmutation rate); demonstration tools; scenarios; ASTRID prototype (Core, Cooling and conversion, Designs and materials for Astrid); Reprocessing and fabrication of fuel (Experience and lessons learned; Pilot reprocessing facility for Astrid); transmutation in ADS; transmutation and disposal (Radiotoxicity of the inventory; Residual thermal power in LLHL waste); other scenarios; conclusion; Chapter 2 - disposal and storage: introduction; inventory; ZIRA (Contributions of the new 3D geophysics campaign; Knowledge of lithostratigraphic variations in the Callovo-Oxfordian layer; Knowledge of regional and local hydrogeology; Hydrogeological modelling situation); ZIIS - Integration of

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-03-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-01-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-04-15

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

  4. The Management of Nuclear Materials in a Research Establishment; Gestion des Matieres Nucleaires dans un Centre de Recherche; Uchet yadernykh materialov v nauchno-issledovatel'skom uchrezhdenii; Administracion de Sustancias Nucleares en un Centro de Investigaciones

    Energy Technology Data Exchange (ETDEWEB)

    Wright, W. J.; Hocking, D. R. [Australian Atomic Energy Commission Research Establishment, Lucas Heights, NSW (Australia)

    1966-02-15

    The functions of a nuclear materials management scheme are reviewed in relation to the activities of research establishments. Since these activities are normally non-repetitive, there is little opportunity to establish statistical quality and quantity control. The risks of an error in the material accounts must therefore be established from relatively few analytical measurements and the implications of this are discussed. Similar arguments are applied to illustrate the difficulties of quality control on suppliers when a large variety of materials are being purchased in small quantities. (author) [French] Les auteurs examinent le role d'un systeme de gestion des matieres nucleaires applique aux activites des centres de recherche. Comme ces activites ne sont normalement pas appelees a se repeter, il n'est guere possible d'organiser un controle statistique quantitatif et qualitatif. Il faut donc determiner les possibilites d'erreurs dans la comptabilite matieres en s'appuyant sur un nombre relativement restreint de mesures analytiques et les auteurs examinent les conclusions a tirer de cette situation. Ils recourent a une argumentation analogue pour illustrer les difficultes inherentes au controle de la qualite des matieres livrees par les fournisseurs lorsqu'il doit porter sur une grande diversite de matieres en petites quantites. (author) [Spanish] Los autores examinan el funcionamiento de un sistema de administracion de materiales nucleares en relacion con las actividades de los centros de investigaciones. Como estas actividades son por lo comun muy diversas, hay pocas oportunidades de establecer un control estadistico de la calidad y la cantidad. Por ello es necesario determinar los riesgos de error en la contabilidad de los materiales partiendo de un numero relativamente reducido de mediciones analiticas; en la memoria se examinan las consecuencias de este hecho. Los autores aplican razonamientos analogos para poner de manifiesto las dificultades con que, en el

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

  7. Economic Criteria Applied to Nuclear Materials Management; Criteres Economiques Applicables a la Gestion des Matieres Nucleaires; Ehkonomicheskie kriterii, primenyaemye pri kontrole i uchete yadernykh materialov; Criterios Economicos Aplicados a la Administracion de Materiales Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Shelley, W. J.; Kuehn, M. N. [Mallinckrodt Chemical Works, St. Charles, MS (United States)

    1966-02-15

    placed upon such personnel to accept, understand and perform the work. Such personnel selected must be thoroughly and minutely trained in the importance of their activity. Those responsible for the management of nuclear materials must be continually alert to the smallest kind of aberration in the quality and performance of the personnel, the process, the systems, procedures and techniques. Only through such alertness and willingness to revise, so as to secure improvement, does one secure the optimum balance of costs and needs. (author) [French] La gestion des matieres nucleaires doit etre subordonnee aux objectifs principaux du traitement de ces matieres, c'est-a-dire la production d'energie ou la fabrication de produits finis. Les responsables de la gestion des matieres nucleaires doivent donc tenir constamment compte des besoins de la production principale et adapter les methodes de gestion aux operations de facon a pouvoir assurer cette gestion avec un minimum de depenses. Le systeme de gestion des matieres nucleaires doit soigneusement tenir compte des divers facteurs qui influent sur son prix de revient. Il vient en complement des operations et doit entrainer le minimum de frais de personnel et d'analyse et provoquer le moins d'interruptions possible dans les operations. U doit etre integre a ces dernieres, de facon que les renseignements d'ordre quantitatif qu'il permet d'obtenir puissent etre communiques rapidement aux responsables du controle des operations. Le systeme d'enregistrement et de preparation des rapports doit fournir une quantite maximale de donnees subsidiaires. Il doit etre compatible avec les systemes utilises par les fournisseurs et les consommateurs et assurer la diffusion, partout ou cela est possible, de renseignements supplementaires concernant les lots de matieres nucleaires. Les donnees a fournir pour le controle des matieres nucleaires doivent se limiter a celles qui sont necessaires pour s'assurer qu'il n'y a pas de pertes importantes, de

  8. Les ecarts de financement en matiere d'adaptation aux changements climatiques - avec la perspective des CPDN

    DEFF Research Database (Denmark)

    Olhoff, Anne; Bee, Skylar; Puig, Daniel

    En 2014, le Programme des Nations Unies pour l’Environnement (PNUE) a publié son premier rapport sur les écarts entre besoins et perspectives en matière d’adaptation (AGR 2014) (PNUE, 2014), lequel a permis de poser un cadre préliminaire pour évaluer ces écarts et d’établir une évaluation...... rapport sur les écarts financiers et les options permettant de les combler. Le rapport sera publié au printemps 2016. Cette mise à jour doit contribuer aux débats lors de la 21ème session de la Conférence des Parties (COP 21) à la Convention-Cadre des Nations Unies sur les Changements Climatiques (CCNUCC...... les besoins de financement présentes dans les composantes adaptation des Contributions Prévues Déterminées au niveau National (CPDN) (INDC) – soit les engagements post 2020 que les pays se proposent mettre en oeuvre dans le cadre d’un nouvel accord mondial sur les changements climatiques....

  9. Economic outlook for radiometric selection of ores; Possibilites ouvertes en matiere economique par selection radiometrique des minerais

    Energy Technology Data Exchange (ETDEWEB)

    Formery, P.; Ziegler, V. [Commissariat a l' Energie Atomique, Usine du Bouchet, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    The value of an ore can be increased by cutting off it's poor fractions. This selection may be realized at two stages: - part of the ore in situ is unable to cover it's extraction and treatment costs, this defines the 'underground cut-off grade'; - another portion of already extracted ore is unable to cover it's transport and treatment costs; this defines the 'surface cut off grade'. These selections are easily feasible owing to the property of uranium ores of emitting gamma radiations. A diagram makes possible a fast forecast on the effect of this selection upon the weight and metal yields. An attempt is made as well in order to provide the expected effect of the composition of underground cut off and surface cut off. This cut off however, being realized through an appreciation of the radiations, involves an alteration of the weight and metal yields which calls for a correction. A survey of the economic interest of the cut-off is done and an example of valorisation in a given deposit of a section at the limit of operability is proposed. (author) [French] On peut augmenter la valeur d'un minerai en retranchant des fractions pauvres de minerai. Cette selection peut etre realisee a deux stades: - eviter l'abattage d'un minerai incapable de supporter les frais d'extraction et de traitement. On definit ainsi une teneur de 'coupure fond'; - eviter de traiter chimiquement des fractions de minerai deja extraites mais dont la teneur ne justifie pas le transport et le traitement. On definit ainsi une teneur de coupure jour. La propriete des minerais d'uranium d'emettre des rayonnements gamma dont la densite est liee a la teneur permet de realiser tres aisement cette selection. On propose un diagramme permettant de prevoir rapidement l'incidence de cette selection sur les rendements poids et metal. On a tente de prevoir l'effet d'une composition des coupures fond et jour. Toutefois, la

  10. Economic outlook for radiometric selection of ores; Possibilites ouvertes en matiere economique par selection radiometrique des minerais

    Energy Technology Data Exchange (ETDEWEB)

    Formery, P; Ziegler, V [Commissariat a l' Energie Atomique, Usine du Bouchet, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    The value of an ore can be increased by cutting off it's poor fractions. This selection may be realized at two stages: - part of the ore in situ is unable to cover it's extraction and treatment costs, this defines the 'underground cut-off grade'; - another portion of already extracted ore is unable to cover it's transport and treatment costs; this defines the 'surface cut off grade'. These selections are easily feasible owing to the property of uranium ores of emitting gamma radiations. A diagram makes possible a fast forecast on the effect of this selection upon the weight and metal yields. An attempt is made as well in order to provide the expected effect of the composition of underground cut off and surface cut off. This cut off however, being realized through an appreciation of the radiations, involves an alteration of the weight and metal yields which calls for a correction. A survey of the economic interest of the cut-off is done and an example of valorisation in a given deposit of a section at the limit of operability is proposed. (author) [French] On peut augmenter la valeur d'un minerai en retranchant des fractions pauvres de minerai. Cette selection peut etre realisee a deux stades: - eviter l'abattage d'un minerai incapable de supporter les frais d'extraction et de traitement. On definit ainsi une teneur de 'coupure fond'; - eviter de traiter chimiquement des fractions de minerai deja extraites mais dont la teneur ne justifie pas le transport et le traitement. On definit ainsi une teneur de coupure jour. La propriete des minerais d'uranium d'emettre des rayonnements gamma dont la densite est liee a la teneur permet de realiser tres aisement cette selection. On propose un diagramme permettant de prevoir rapidement l'incidence de cette selection sur les rendements poids et metal. On a tente de prevoir l'effet d'une composition des coupures fond et jour. Toutefois, la coupure etant realisee par une appreciation des rayonnements, il s'introduit une certaine

  11. Guide relative to the modalities of statements and to the codification of criteria relative to the significant events involving the safety, the radiation protection or the environment applicable to the base nuclear installations and to the transport of radioactive matters; Guide relatif aux modalites de declaration et a la codification des criteres relatifs aux evenements significatifs impliquant la surete, la radioprotection ou l'environnement applicable aux installations nucleaires de base et au transport de matieres radioactives

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    It is necessary to analyze the events detected on an installation in order to be sure that an already occurred event does not be repeated, by taking into account the appropriate remedial measures, to avoid a worsen situation could occur by analyzing the potential consequences of precursory events of more serious ones, to promote the correct practices to improve the safety. The present guide has for vocation to define the arrangements enforceable to nuclear operators about the statements modalities of such events when these ones concern the safety of nuclear facilities, transport of radioactive matters, radiation protection or environmental protection. In any case it can substitute to the specific obligations coming from the work code, public health code and environment code, licensing decrees about releases. (N.C.)

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

    Energy Technology Data Exchange (ETDEWEB)

    Sandier, J.

    1958-01-15

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

  13. Transport of dangereous waste on the route to the pilot facility in Grenoble. Risk analysis. Final report; Trafic des matieres dangereuses sur l'itineraire pilote de l'agglomeration de Grenoble. Evaluation du risque. Rapport final

    Energy Technology Data Exchange (ETDEWEB)

    Brenot, J; Despres, A; Degrange, J P; Hubert, Ph; Pages, P

    1988-12-01

    validate on the whole a variety of impacts identified here. This last process rises the question of economic and political analysis more than mere physical modelling. (author) [French] Le document presente les resultats d'une etude reaIisee par le CEPN pour l'TNRETS a la demande de la Mission Matieres Dangereuses du Ministere des Transports et de la Direction Departementale de l'Equipement de l'Isere. Son objectif est l'analyse du risque associe a la circulation des matieres dangereuses sur une portion de la voirie du departement, connue comme 'Itineraire Pilote', et traversant la vile de la vallee de l'Isere a Pont de Claix. Dans un premier temps l'estimation des trafics a ete realisee a partir des comptages effectues sur la route anterieurement a cette etude et a partir des donnees sur l'activite economique de la region. Annuellement 30 a 50 000 vehicules de transport de matieres dangereuses empruntent cet itineraire. Contrairement a ce qui se passe d'habitude en France, les produits petroliers comptent pour moins de la moitie de ce trafic et les liquides toxiques et corrosifs pour la moitie. Les hydrocarbures liquides (70 veh/j), les autres produits inflammables (20 veh/j), les GPL (10 veh/j) et la soude (30veh/j) sont les plus transportes d'apres les estimations faites ici. Le trafic a aussi ete estime pour d'autres produits comme le chiore (0,5 veh/j), l'ammoniac (1 veh/j) ou l'acide chiorhydrique gazeux (1 veh/j), dont le transport est plus rare mais le danger plus important. Avant d'estimer les risques, il a ete necessaire d'identifier les impacts redoutes. Evidents quant II s'agit de sante humaine (morts et blessures), ceux-ci sont moms bien definis quand on considere les dommages a l'environnement ou les pertes economiques. Le niveau d'analyse a ensuite ete tres different suivant les cas: quantification poussee pour la mortalite, approche semi-quantifiee pour les effets de la pollution et identification sommaire pour les impacts economiques. Cette difference de

  14. Report realized on behalf of the economic affairs, the environment and the territory commission, on the law project modified by the Senate, after urgency declaration (n. 3121), of program relative to the sustainable management of the radioactive materials and wastes; Rapport fait au nom de la commission des affaires economiques, de l'environnement et du territoire sur le projet de loi, modifie par le Senat, apres declaration d'urgence (n. 3121), de programme relatif a la gestion durable des matieres et des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Birraux, C

    2006-06-15

    This report presents and discusses the modifications realized by the Senate on the law project relative to the sustainable management of the radioactive materials and wastes. It details then the different articles in three main chapters: the national policy for the sustainable radioactive materials and wastes, the organization and the financing of the sustainable management of radioactive materials and wastes, the control and the penalties. (A.L.B.)

  15. Accounting Systems for Heavy Water and Fissionable Materials; Comptabilite de l'Eau Lourde et des Matieres Fissiles; Sistema ucheta tyazheloj vody i delyashchikhsya materialov; Sistemas de Contabilidad para el Agua Pesada y los Materiales Fisionables

    Energy Technology Data Exchange (ETDEWEB)

    Fletcher, G. W.; Reid, H. B.; Jenkinson, W. G. [Atomic Energy of Canada Ltd., Chalk River, ON (Canada)

    1966-02-15

    ] Les aureurs du memoire decrivent les methodes de gestion comptable utilisees par l'Atomic Energy of Canada Ltd (AECL) pour assurer l'enregistrement et le controle des stocks d'eau lourde et de matieres fissiles; ils decrivent egalement les fonctions et les responsabilites de ceux qui sont charges d'administrer ce systeme. Ils determinent la valeur de ces methodes et etudient dans quelle mesure elles sont adaptables et applicables aux programmes de recherche et de production d'energie qui se developpent rapidement; ils examinent en particulier les avantages du systeme electronique de traitement des donnees. Un comite de gestion a la responsabilite d'assurer la bonne marche du systeme de comptabilite, d'etablissement des rapports et de controle des matieres fissiles. A la Division des operations du Laboratoire nucleaire de Chalk River, le service de planification et de controle de la production est responsable envers le comite de la tenue de tous les registres et du fonctionnement general du systeme. Les differentes taches que cela implique sont decrites en detail dans le memoire. Le systeme de comptabilite des matieres fissiles est divise en un certain nombre de sections comptables dont 15 sont du ressort des differents departements de l'AECL et les autres confiees a des industries canadiennes et a des organismes de recherche. Pour chaque section, le service de planification et de controle de la production tient un livre; ces sections ont toutefois la responsabilite de preparer des etats comptables detailles pour toutes les matieres soumises a leur controle. Les principales methodes comptables utilisees pour enregistrer les transferts de matieres d'une section a l'autre, les transformations subies par les matieres dans une meme section, le traitement des gains et les pertes de matieres, l'elimination des dechets, sont exposees dans le memoire. La transcription de ces donnees sur carte IBM, leur traitement final a l 'aided'une calculatrice IBM 1401 et la preparation des

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-07-01

    Besides the very high activity liquids containing fission products, the chemical treatment of irradiated fuels produces a large volume of aqueous effluents and solid waste of relatively low radioactivity. These weakly active products can be eliminated in the ground, in a hydrographic land system or in the sea. Techniques of evaporation, of resin concentration, and of coprecipitation give rise to inorganic sludges with a high water content. All these residues occupy a large volume and represent a far from negligible weight. In the case of the sludge, their relative fluidity necessitates a conditioning guaranteeing safe storage. The solution to the problem will consist in passing directly from a liquid or a suspension, to a solid whose structure is homogeneous and whose matter is inert with respect to the storage medium (soil, sea, etc. ). We have proposed to coat the radioactive products with bitumen. This article is designed to give a review of the studies undertaken on this method. It consists of a progress report rather than a final assessment. (authors) [French] En dehors des liquides de tres haute activite contenant des produits de fission, le traitement chimique des combustibles irradies produit un volume important d'effluents aqueux et de residus solides de radioactivite relativement faible. Ces produits, faiblement actifs, peuvent etre elimines dans le sol, dans un systeme hydrographique terrestre ou dans la mer. Les techniques d'evaporation, de concentration sur resine, de coprecipitation, permettent la decontamination prealable des liquides. La coprecipitation donne naissance a des boues minerales dont la teneur en eau est elevee. Tous ces residus occupent un volume important et representent un poids non negligeable. Dans le cas des boues, leur fluidite relative exige un conditionnement donnant toutes garanties de securite au stockage. La solution du probleme consistera a passer directement d'un liquide ou d'une suspension a un solide

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-07-01

    Besides the very high activity liquids containing fission products, the chemical treatment of irradiated fuels produces a large volume of aqueous effluents and solid waste of relatively low radioactivity. These weakly active products can be eliminated in the ground, in a hydrographic land system or in the sea. Techniques of evaporation, of resin concentration, and of coprecipitation give rise to inorganic sludges with a high water content. All these residues occupy a large volume and represent a far from negligible weight. In the case of the sludge, their relative fluidity necessitates a conditioning guaranteeing safe storage. The solution to the problem will consist in passing directly from a liquid or a suspension, to a solid whose structure is homogeneous and whose matter is inert with respect to the storage medium (soil, sea, etc. ). We have proposed to coat the radioactive products with bitumen. This article is designed to give a review of the studies undertaken on this method. It consists of a progress report rather than a final assessment. (authors) [French] En dehors des liquides de tres haute activite contenant des produits de fission, le traitement chimique des combustibles irradies produit un volume important d'effluents aqueux et de residus solides de radioactivite relativement faible. Ces produits, faiblement actifs, peuvent etre elimines dans le sol, dans un systeme hydrographique terrestre ou dans la mer. Les techniques d'evaporation, de concentration sur resine, de coprecipitation, permettent la decontamination prealable des liquides. La coprecipitation donne naissance a des boues minerales dont la teneur en eau est elevee. Tous ces residus occupent un volume important et representent un poids non negligeable. Dans le cas des boues, leur fluidite relative exige un conditionnement donnant toutes garanties de securite au stockage. La solution du probleme consistera a passer directement d'un liquide ou d'une suspension a un solide dont la structure

  18. Contribution to the studies on the mineral content of plant material through radioactivation analysis; Contribution a l'etude de la composition minerale des matieres vegetales au moyen de l'analyse par radioactivation

    Energy Technology Data Exchange (ETDEWEB)

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

    1968-03-15

    Radioactivation analysis is by its great sensibility or its rapidity quite helpful in plant biology and agronomy. Specific composition of plants and results to obtain in biological experimentation have needed a practical research on analytical methods for plant materials, using for radioactivation swimming-pool reactor neutrons and 14 MeV neutrons from a generator. Dosage process for 25 elements is exposed, taking account of the interest of the analysis for each element, the average amount occurring in plants and the result obtained. Many applications are developed, concerning nutrition physiology, genetics, parasitology, toxicology, control of manufactured agricultural and pharmaceutical products industrial and pesticides residues, ecology, radioecology and biochemistry. (author) [French] L'analyse par radioactivation, par sa grande sensibilite ou sa rapidite, est susceptible de rendre de nombreux services en biologie vegetale et en agronomie. La composition particuliere des plantes et les buts recherches dans l'experimentation ont exige une etude concrete des methodes d'analyse propres a la matiere vegetale en utilisant, pour la radioactivation, soit un reacteur de type piscine a eau legere, soit un accelerateur generateur de neutrons de 14 MeV. Le mode de dosage de 25 elements est expose en tenant compte de l'interet de l'analyse de chaque element, des teneurs moyennes rencontrees dans les plantes, et du resultat atteint. De nombreuses applications sont developpees qui touchent a la physiologie de la nutrition, la genetique, la parasitologie, la toxicologie, le controle des fabrications, les pollutions industrielles, l'ecologie, la radioecologie et la biochimie. (auteur)

  19. Contribution to the studies on the mineral content of plant material through radioactivation analysis; Contribution a l'etude de la composition minerale des matieres vegetales au moyen de l'analyse par radioactivation

    Energy Technology Data Exchange (ETDEWEB)

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

    1968-03-15

    Radioactivation analysis is by its great sensibility or its rapidity quite helpful in plant biology and agronomy. Specific composition of plants and results to obtain in biological experimentation have needed a practical research on analytical methods for plant materials, using for radioactivation swimming-pool reactor neutrons and 14 MeV neutrons from a generator. Dosage process for 25 elements is exposed, taking account of the interest of the analysis for each element, the average amount occurring in plants and the result obtained. Many applications are developed, concerning nutrition physiology, genetics, parasitology, toxicology, control of manufactured agricultural and pharmaceutical products industrial and pesticides residues, ecology, radioecology and biochemistry. (author) [French] L'analyse par radioactivation, par sa grande sensibilite ou sa rapidite, est susceptible de rendre de nombreux services en biologie vegetale et en agronomie. La composition particuliere des plantes et les buts recherches dans l'experimentation ont exige une etude concrete des methodes d'analyse propres a la matiere vegetale en utilisant, pour la radioactivation, soit un reacteur de type piscine a eau legere, soit un accelerateur generateur de neutrons de 14 MeV. Le mode de dosage de 25 elements est expose en tenant compte de l'interet de l'analyse de chaque element, des teneurs moyennes rencontrees dans les plantes, et du resultat atteint. De nombreuses applications sont developpees qui touchent a la physiologie de la nutrition, la genetique, la parasitologie, la toxicologie, le controle des fabrications, les pollutions industrielles, l'ecologie, la radioecologie et la biochimie. (auteur)

  20. The determination by irradiation with a pulsed neutron generator and delayed neutron counting of the amount of fissile material present in a sample; Determination de la quantite de matiere fissile presente dans un echantillon par irradiation au moyen d'une source pulsee de neutrons et comptage des neutrons retardes

    Energy Technology Data Exchange (ETDEWEB)

    Beliard, L; Janot, P [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1967-07-01

    A preliminary study was conducted to determine the amount of fissile material present in a sample. The method used consisted in irradiating the sample by means of a pulsed neutron generator and delayed neutron counting. Results show the validity of this method provided some experimental precautions are taken. Checking on the residual proportion of fissile material in leached hulls seems possible. (authors) [French] Ce rapport rend compte d'une etude preliminaire effectuee en vue de determiner la quantite de matiere fissile presente dans un echantillon. La methode utilisee consiste a irradier l'echantillon considere au moyen d'une source puisee de neutrons et a compter les neutrons retardes produits. Les resultats obtenus permettent de conclure a la validite de la methode moyennant certaines precautions. Un controle de la teneur residuelle en matiere fissile des gaines apres traitement semble possible. (auteurs)

  1. Case Study in Internal Audit of Nuclear Material; Etude d'un Systeme de Verification Comptable Interne des Matieres Nucleaires; Izuchenie primera organizatsii vnutrennego ucheta yadernykh materialov na predpriyatii; Estudio de la Fiscalizacion Interna de los Materiales Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Kops, S. [United States Atomic Energy Commission, Argonne, IL (United States)

    1966-02-15

    sont generalement les principaux facteurs a considerer lorsque l'on veut determiner s'il y a lieu d'etablir un systeme classique de verification comptable interne. L'auteur analyse les besoins et les caracteristiques d'un systeme de verification comptable interne dans le cas particulier d'une organisation qui manipule des matieres brutes ou des produits fissiles speciaux (matieres nucleaires), en les confrontant a ceux d'un systeme de verification classique. Il montre comment, etant donne le prix eleve et la valeur strategique des matieres, il est necessaire d'etablir un systeme special de verification comptable. Le memoire etudie en detail l'organisation du systeme de verification comptable interne dans une installation produisant des matieres nucleaires; il indique notamment comment fixer la date des controles et comment proceder a la verification des livres et inventaires. Il indique egalement la competence et les qualifications professionnelles que doit avoir le personnel charge de la verification comptable, ainsi que les considerations d'ordre statistique a appliquer pour determiner les donnees qui devront faire l'objet d'une verification. Le memoire decrit de facon detaillee la maniere dont ces dispositions sont appliquees dans la pratique de la verification comptable interne. Il indique les modifications qui peuvent etre apportees aux normes etablies ainsi que les differentes manieres d'envisager le probleme de la verification des comptes et montre que, s'il est possible dans le cas d'autres fabrications de proceder simplement a une verification comptable des stocks, il est necessaire dans l'industrie nucleaire de proceder effectivement a l'inventaire materiel du stock. Le memoire presente les divers moyens utilises pour communiquer les resultats de la verification interne. La presentation du rapport comptable et sa teneur sont determinees en fonction des besoins des differents services. Le memoire indique les diverses manieres dont le rapport comptable peut

  2. An Appraisal of Analytical Methods for Plutonium and their Applications to the Analysis of Nuclear Materials; Evaluation des Methodes Analytiques de Dosage du Plutonium et de Leur Application a l'Analyse des Matieres Nucleaires; Otsenka analiticheskikh metodov opredeleniya plutoniya i ikh primenenie dlya analiza yadernykh materialov; Metodos Analiticos de Determinacion del Plutonio y su Empleo en el Analisis de Materiales Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Milner, G. W.C.; Phillips, G. [Atomic Energy Research Establishment, Harwell, Berks. (United Kingdom)

    1966-02-15

    programmes for new nuclear fuels. (author) [French] Il existe plusieurs methodes de dosage de la teneur en plutonium des matieres nucleaires. Pour les quantites de l'ordre du milligramme, les methodes utilisables sont la spectro- photometiie differentielle fondee sur la couleur de Pu (III), la gravimetrie fondee sur PuO{sub 2}, le comptage gamma et les methodes de reduction/oxydation comprenant les titrages poientiometriques et amperemetriques et la coulombmetrie a potentiel constant. Pour les quantites de Tordre du microgramme, le comptage alpha, la dilution isotopique et les methodes polarigraphiques sont a utiliser. Certaines methodes conviennent mieux que d'autres a des types determines d'echantillons et l'analyste soucieux d'obtenir les meilleurs resultats se heurte a un choix difficile. Les auteurs exposent les avantages et les inconvenients des methodes citees tels qu'ils se sont degages de l'experience acquise au cours des annees a l'Atomic Energy Research Establishment, et ils discutent l'exactitude, la precision, la sensibilite de ces methodes, et d'autres caracteristiques presentant un interet particulier. Certaines methodes ne peuvent etre utilisees si l'on n'a, dans une certaine mesure, separe le plutonium des autres constituants de l'echantillon et le memoire commente l'experience acquise avec l'echange d'anions et les procedes de chromatographie a phase inversee utilises a cette fin, en insistant surtout sur la mesure dans laquelle cette methode convient aux echantillons radioactifs. Les auteurs etudient en outre les nombreux problemes qui se sont poses lors de l'application (d'ailleurs couronnee de succes) de ces methodes a l'analyse des alliages de plutonium, des ceramiques et des cermets dans differentes combinaisons contenant de l'uranium, du thorium, du fer, du chrome, du molybdene, du cerium et du cobalt. Us exposent les difficultes de la dissolution des echantillons et de la reduction du plutonium a l'etat de valence voulu, ainsi que les avantages

  3. Criteria for Special Nuclear Materials Inventory and Control Procedures; Criteres a Suivre Pour Proceder a l'Inventaire des Matieres Nucleaires Speciales et aux Mesures de Controle; Kriterii dlya inventarizatsii spetsial'nykh yadernykh materialov i metody ucheta; Criterios a Que Deben Ajustarse los Procedimientos de Inventario y Control de los Materiales Nucleares Especiales

    Energy Technology Data Exchange (ETDEWEB)

    Kinderman, E. M.; Tarrice, R. R. [Stanford Research Institute, Menlo Park, CA (United States)

    1966-02-15

    and the total inventory of these special nuclear materials. A matrix of solutions to the management and inventory control of special nuclear materials will be presented. The multiplicity and relative effectiveness of varied techniques at key stages of the materials supply, utilization and recovery are assessed. (author) [French] L'un des plus importants problemes qui, dans le domaine nucleaire et notamment dans l'exploitation commerciale de l'energie d'origine nucleaire, se posera aux societes d'investissement, aux directeursetaux exploitants est celui du controle efficace de l'inventaire des matieres nucleaires dont la valeur depassera, d'ici 1980, 5 milliards de dollars des Etats-Unis. Comparativement a la plupart des matieres utilisees commercialement, les matieres nucleaires speciales sont couteuses; aux Etats-Unis par exemple, l'uranium enrichi a 90%, l'uranium enrichi a 3% sous forme d'hexa- fluorure et l'eau lourde coutent respectivement 10808 dollars, 254 dollars et 61,60 dollars le kilo. En outre, ces matieres sont frequemment soumises, pour des raisons de protection sanitaire et de securite, a des controles gouvernementaux speciaux sans rapport direct avec leur valeur monetaire. En depit de leur prix eleve, ces matieres sont destinees a etre utilisees en grandes quantites; par exemple, on utilisera de 50 a 75 t de combustible enrichi a 3{sup o}{r_brace}o dans un reacteur de 500 MW modere a l'eau ordinaire et 200 a 300 reacteurs de cette puissance fonctionneront vraisemblablement dans le monde en 1980. L'experience acquise a permis la mise au point et l'application de methodes speciales pour le controle commercial de grandes quantites de matieres de faible valeur comme le charbon ou le minerai de fer ou de petites quantites de matieres de grande valeur comme les metaux precieux. Tout en ayant des prix comparables a ces derniers, les matieres nucleaires speciales sont de nature differente et seront utilisees en quantites beaucoup plus importantes que les

  4. Materials Control in the Fabrication of Enriched Uranium Fuels; Controle des Matieres au Cours de la Fabrication des Combustibles a Base d'Uranium Enrichi; Uchet materialov pri izgotovlenii topliva na obogashchennom urane; Control de Materiales en la Elaboracion de Combustibles de Uranio Enriquecido

    Energy Technology Data Exchange (ETDEWEB)

    Cardwell, Jr., R. G. [Oak Ridge National Laboratory, Oak Ridge, TN (United States)

    1966-02-15

    measurement were successfully used where alloy fuel content was critical. Scrap handling had an important effect on the materials balance, by which fuel content was confirmed and good accountability was assured. Records and handling procedures, including batching and physical marking methods, were formulated in a manner that assisted the fabricator in criticality control. (author) [French] Grace aux efforts intenses qui ont ete accomplis au cours des 15 dernieres annees dans le domaine de la technologie des elements de combustible par le Laboratoire national d'Oak Ridge, il a ete possible d'etablir des methodes rationnelles de fabrication et de controle des combustibles eraichis, qui trouvent une iaige application dans la fabrication industrielle des elements de combustible a l'heure actuelle. Des techniques eprouvees de manipulation du combustible enrichi en alliages, en dispersion et sous forme d'oxyde en vrac ont ete mises au point et appliquees a l'etude et a la' fabrication des prototypes d'elements combustibles utilises pour le demarrage du reacteur d'essai de materiaux, du reacteur a protection constituee par la masse du ra- lentisseur ou reacteur piscine, du reacteur de puissance transportable construit pat V, du reacteur protection en tour, du reacteur expose a la Conference de Geneve, du reacteur a haut flux pour la production de radioisotopes et du reacteur experimental refroidi par un gaz. L'experience acquise est la base du present memoire qui traite essentiellement des problemes de controle des matieres qui se posent au cours de la fabrication de differents types d'elements de combustible a base d'uranium enrichi et montre comment ils ont ete resolus. Les objectifs principaux d'un systeme rationnel de controle des matieres sont les suivants: 1. reduire le plus possible le nombre des postes matiere a controler; 2. etablir des releves distincts pour chacune des phases principales des operations et les coordonner de maniere a pouvoir relever les ecarts avec un

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

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

  6. Biological cycles of radioactive contaminants; Les cycles biologiques des pollutions radioactives

    Energy Technology Data Exchange (ETDEWEB)

    Michon, M. -G. [Commissariat a l' energie atomique et aux energies alternatives - CEA (France)

    1959-07-01

    Artificial radio-elements (synthesized for scientific or industrial purposes)having been released, may be absorbed by plants or animals, and may eventually involve a catenation of organisms as some feed on the others. All organisms living in a polluted river become more radioactive than the water, which was to be expected, in as much as organisms are hypertonic in respect to sweet water. Conversely, soil brings into play physico-chemical phenomena (absorption) such that plants can get only a small portion of contaminating radio-elements, land animal feeding on such plants are relatively less exposed to contamination, and carnivorous animals feeding on herbivorous are still less exposed. Man, notably is fairly well protected, whereas lower organisms, notably unicellular organisms may suffer (mutations..). Reprint of a paper published in 'Revue de Pathologie Generale et de Physiologie Clinique', n. 707, April 1959, p. 505-514 [French] L'utilisation a des fins pacifiques ou scientifiques conduit au rejet dans le milieu ambiant de radio-elements artificiels. Ces radio-elements seront plus ou moins absorbes par les plantes et les animaux. Cette pollution va gagner tous les etres vivants a travers les chaines alimentaires. Cependant, l'importance relative de ces absorptions varie avec chaque cas particulier. Par exemple, lors du rejet du radio-element dans un fleuve ou un etang, on constate que tous les etres vivants dans ce milieu presentent une radioactivite specifique superieure a celle du milieu. Ceci n'est pas a priori etonnant puisque tous les etres vivant en eaux douces sont hypertoniques vis-a-vis du milieu. Les facteurs de concentration varient avec la nourriture et des exemples precis sont fournis. A l'inverse, lorsqu'il s'agit de la contamination d'un sol, par suite de phenomenes physicochimiques d'absorption, les plantes ne prelevent qu'une faible partie des radio-elements presents. La nourriture etant moins fortement contaminee, les animaux terrestres le

  7. The United States Atomic Energy Commission Programme of Nuclear Materials Management; Le Programme de Gestion des Matieres Nucleaires Applique par L'USAEC; Programma komissii po atomnoj ehnergii ssha v oblasti obrashcheniya s yadernymi materialami; El Programa de Administracion de Materiales Nucleares de la Comision de Energia Atomica de los Estados Unidos

    Energy Technology Data Exchange (ETDEWEB)

    George, D. E. [United States Atomic Energy Commission, Washington, DC (United States)

    1966-02-15

    Nuclear materials management as conceived by the US Atomic Energy Commission is defined and its development traced from 1943 to the present time. The general programme is outlined and its principal features discussed. Emphasis is placed on administration of those portions of the USAEC programme which pertain to the development and maintenance of quantity data, the establishment of internal controls and the evaluation of performance. The current techniques whereby transfer data are recorded and processed within the USAEC are discussed in some detail, as are the techniques for presentation of material balance reports which periodically summarize the transactions and the results of operations. The techniques used by the USAEC to ascertain the effectiveness of the nuclear materials management programmes of its operating contractors are also discussed. In addition to material being held by contractors which operate USAEC-owned plants and laboratories, there are large quantities of special nuclear material held under a wide variety of financial and administrative arrangements, e.g. under lease, private ownership, under contract with the USAEC where the user is financially liable for losses, as well as those where the risk of losses is taken by the USAEC. This divergence of circumstances causes significant variation in the emphasis and approach used by the AEC and this variation is noted. A brief summary of unresolved problem areas concludes the presentation. (author) [French] L'auteur definit la gestion des matieres nucleaires telle qu'elle est concue par l'USAEC et decrit son evolution depuis 1943 jusqu'a nos jours. Il expose le programme general et discute ses principales caracteristiques. Le memoire souligne les aspects administratifs des parties du programme qui ont trait a la preparation et la tenue a jour des donnees relatives aux quantites, a l'application de controles internes et a l'evaluation de l'efficacite des mesures prises. L'auteur commente en detail la

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

    Energy Technology Data Exchange (ETDEWEB)

    Villepin, D. de; Breton, T

    2006-03-15

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

  9. Nuclear Materials Management in a Recovery Facility for Unirradiated Enriched Uranium; Gestion des Matieres Nucleaires dans une Installation de Recuperation d'Uranium Enrichi Non Irradie; Administrativno-khozyajstvennyj uchet yadernykh materialov na ustanovke po regeneratsii neobluchennogo obogashchennogo urana; Administracion de Materiales Nucleares en una Planta de Recuperacion para Uranio Enriquecido No Irradiado

    Energy Technology Data Exchange (ETDEWEB)

    Jasny, G. R. [Union Carbide Corporation, Oak Ridge, TN (United States)

    1966-02-15

    measurements. Statistical analysis is used extensively in connection with the control of measurements and to minimize the number of chemical analyses. However, the application of statistics to the evaluation of inventory discrepancies has not been successful. This paper will discuss the details of the material control techniques which have been listed and some of the problems associated with them. (author) [French] L'usine Y-12 exploitee par la Commission de l'energie atomique a Oak Ridge, Tennessee, procede depuis plus de 20 ans au traitement et a la recuperation d'uranium enrichi non irradie se presentant sous diverses formes. A l'heure actuelle, les installations de recuperation d'Y-12 executent une serie d'operations distinctes en chaine semi-continue, par exemple, dissolution, combustion, evaporation, extraction, denitrification et hydrofluoration. Les installations de traitement et de stockage ont une geometrie restreinte et leur capacite globale est de plusieurs centaines de kilogrammes d'uranium enrichi par mois. L'uranium entrant provient de l'usine elle-meme ainsi que d'autres installations de la Commission de l'energie atomique, situees aux Etats-Unis. Depuis sa creation, l'usine Y-12 a recu pratiquement toutes les sortes de dechets d'uranium enrichi non irradie. Le controle des operations est assure a l'aide des methodes suivantes: 1. Utilisation du materiel concu de maniere a faciliter le nettoyage et l'echantillonnage ainsi qu'a reduire au minimum le 'piegeage ' de matieres; 2. Controle permanent de tous les rebuts et dechets liquides, en particulier des effluents evacues a l'egout ou dans l'atmosphere et des dechets contamines; 3. Inventaires periodiques des stocks; 4. Echantillonnages et analyses de toutes les matieres entrantes et sortantes; 5. Controle strict de la qualite des mesures analytiques et de l'echantillonnage; 6. Attribution de la responsabilite du controle des matieres au personnel charge des operations plutot qu'a des comptables; 7. Formation

  10. 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)

  11. Data acquisition and analysis for the Edelweiss dark matter search experiment; Acquisition et analyse des donnees pour l'experience de recherche de matiere noire EDELWEISS

    Energy Technology Data Exchange (ETDEWEB)

    Fiorucci, S

    2005-09-01

    The EDELWEISS experiment aims to detect WIMPs, hypothetical and elusive particles which could possibly amount for all or part of the dark matter in the universe. For that purpose, it uses cryogenic germanium detectors able to record both the rise in temperature and the ionisation created by a WIMP interaction in the semi-conductor crystal bulk. This thesis work focuses on the last data taking campaign of phase I of the experiment. It is centered around three main points. In a first part, we present the elaboration of a new numerical acquisition system, based on a heat channel trigger, contrary to the previous system which was based on an ionisation channel trigger. In a second part, we expose the complete analysis of the data acquired with this new system, from the calibration of each measurement channel to the extraction of a result in terms of sensitivity to a WIMP signal. Lastly, we dedicate a whole chapter to a further analysis of the high energy data, as well as to the interpretation of the different radioactive backgrounds we observe, in order to prepare the next phase of the experiment due to begin at the end of 2005. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-31

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-12-31

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Lombard, J; Hubert, P; Pages, P

    1987-07-01

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

  15. Special Nuclear Material Control by the Power Reactor Operator; Controle des Matieres Nucleaires Speciales par l'Exploitant d'une Centrale Nucleaire; Spetsial'nyj kontrol' nalichiya yadernykh materialov operatorom ehnergeticheskogo reaktora; Control de Materiales Nucleares Especiales por Parte de Quienes Operan el Reactor de Potencia

    Energy Technology Data Exchange (ETDEWEB)

    Cordin, R. A. [Yankee Atomic Electric Company, Boston, MA (United States)

    1966-02-15

    insurance programme. (author) [French] L'uranium, combustible relativement nouveau et extremement interessant pour la production d'electricite, doit faire l'objet d'un controle tres strict depuis le moment ou l'exploitant de la centrale en devient financierement responsable jusqu'a celui oti, sous forme de combustible partiellement epuise, la matiere est transferee dans une autre installation et oti l'on recupere ce qui reste de sa valeur initiale. La plupart des exploitants de centrales nucleaires dirigeaient des centrales alimentees par des combustibles fossiles avant l'avenement de l'energie nucleaire et ils ont etabli depuis longtemps un controle etendu et efficace de ces combustibles fossiles. L'exploitant d'une centrale nucleaire doit exercer un controle non moins efficace sur les matieres nucleaires speciales utilisees dans son installation. La technique de l'exploitation des centrales nucleaires n'est pas ancienne et, au cours de, son existence relativement breve, les ingenieurs et hommes de science des Etats-Unis ont constamment ameliore les plans des centrales et les methodes d'exploitation afin de reduire les couts et de permettre aux centrales nucleaires de concurrencer les centrales classiques. La gestion des matieres nucleaires doit etre aussi moderne et efficace que possible pour assurer que les progres technologiques grace auxquels les prix on pu etre reduits ne soient pas mis en echec par des insuffisances dans la manipulation du combustible nucleaire et la tenue de la comptabilite des stocks. Pour assurer la gestion des matieres nucleaires, il faut que l'exploitant de la centrale etablisse et tienne a jour une comptabilite complete et detaillee, sans etre necessairement complexe pour autant; en fait, la simplicite est extremement souhaitable. Bien que le combustible nucleaire soit nouveau et qu'il n'ait rien de commun avec les combustibles classiques, aucun secret ne doit s'y attacher. Le controle des matieres nucleaires dans le cadre de la gestion des

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-12-31

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

  17. Nuclear Materials Management and its Relationship to Nuclear Safety and Criticality Control; La Gestion des Matieres Nucleaires et ses Rapports avec la Securite Nucleaire et le Controle de la Criticite; Obrashchenie s yadernymi materialami i ego svyaz' s yadernoj bezopasnost'yu i kontrolem nad kritichnost'yu; La Administracion de Materiales Nucleares y sus Relaciones con la Seguridad Nuclear y el Control de la Criticidad

    Energy Technology Data Exchange (ETDEWEB)

    Tingey, F. H. [Phillips Petroleum Company, Idaho Falls, ID (United States)

    1966-02-15

    dictated by the technical considerations and familiar with the operational limitations. The administrative problems are solved through procedural restrictions placed by the supervisor. The NMM office can be most valuable in further support to the supervisor in these activities. The primary responsibility of this office is to alert responsible supervision to potentially hazardous situations as indicated either from information made available through the routine processing of accountability data or from material balance calculations. Any information pertaining to criticality studies as requested from the NMM office must be accurate and precise. A vigorous inventory management policy must be pursued to lessen the problems presented by accumulation of fissile materials. Internal audit by the NMM staff of inventory holdings can also serve to verify adherence to safeguard procedures. A vigorous orientation programme can be implemented by the NMM staff in its dealing with those individuals handling nuclear materials to make them more aware of the hazards involved. The integration of the NMM group into the general criticality safeguard problems at the NRT and has provided an effective system for assisting the line supervision in discharging this very important responsibility. (author) [French] Il est essentiel pour tous ceux qui travaillent dans l'industrie nucleaire de savoir comment eviter que des matieres nucleaires ne se trouvent rassemblees en quantites, selon une geometrie ou dans un milieu tels qu'elles puissent donner lieu a une reaction neutronique en chaine. Ceci interesse tout particulierement ceux qui, dans l'exercice de leurs fonctions, sont responsables de la manipulation, du transfert et de l'entreposage des matieres fissiles. Ces memes personnes participent au systeme de gestion des matieres nucleaires. Elles ont au premier chef la responsabilite de fournir et de recevoir les donnees comptables par l'intermediaire du service de gestion des matieres nucleaires

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-01-01

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

  19. Radioactive contamination of foodstuffs: determination of permissible levels; Contamination radioactive des denrees alimentaires: determination des niveaux admissibles

    Energy Technology Data Exchange (ETDEWEB)

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

    1965-07-01

    In a latent air-soil contamination situation, the population would receive 80 per cent of its contamination through foodstuffs. The supervision of this food poses many problems: sampling, radionuclide dosages, etc. It is also necessary to estimate the maximum permissible concentration of radionuclides in foodstuffs, once the maximum exposure limit for the human body has been fixed. The passage of this level to the maximum concentrations is not simple since a) each radionuclide has its own particular effect on the body; b) their concentrations vary from one foodstuff to another, and c) the average amounts of foodstuffs vary from one population to another. Two methods are given here for estimating the maximum permissible concentrations in foodstuffs, together with the first diets likely to become critical when several of them are to be considered simultaneously. The results depend on the way in which the present situation can change to become critical. This evolutionary path can only be estimated approximately. Two methods are therefore given for studying the sensitivity of the results. As an example, a numerical application of these methods using data actually available is given. The data used is naturally incomplete and this will always be true. This application test indicates however two fields in which an improvement is absolutely necessary. 1 - The obtention of multiple observations (simultaneous dosage of at least 2 radionuclides in the same foodstuff, and simultaneous dosage of at least two foodstuffs for the same radionuclide); this assumes a combined effort by the various organisms; 2 - The reaching of an agreement on the dosage methods used by the various organisms since the results actually available are not comparable. (authors) [French] Dans une situation de contamination air-sol latente, la contamination des populations se ferait a 80 pour cent par l'alimentation. Surveiller cette alimentation pose des problemes complexes: echantillonnage, dosage des

  20. Presentation the national Plan of management of radioactive materials and wastes. Friday, the 4. of June 2010

    International Nuclear Information System (INIS)

    2010-01-01

    After a synthesis of the national plan of management of radioactive materials and wastes (PNGMDR for Plan national de gestion des matieres et des dechets radioactifs), this document contains the main conclusions of this plan for the period 2010-2012, a presentation of its elaboration modalities, a presentation of the basic principles regarding radioactive materials and wastes (definitions, origins, waste types and categories, waste management types), a presentation of the main actors of their management (agencies, ministries, authorities, research organizations, institutional bodies, associations). A glossary and other documents are provided, notably a presentation of the ASN (the French Nuclear Safety Authority), a report by the ANDRA agency giving an inventory of radioactive materials and wastes, and a chapter of a report on nuclear safety and radioprotection status in France in 2009

  1. Management of radioactive wastes; Gestion des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

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

  2. 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)

  3. Administrative Co-ordination of Fissile Material Management and Accounting in the U.K.A.E.A; Coordination Administrative de la Gestion et de la Comptabilite des Matieres Fissiles dans les Etabussements de l'Autorite de l'Energie Atomique du Royaume-Uni; Administrativnaya koordinatsiya kontrolya i ucheta delyashchikhsya materialov v upravlenii po atomnoj ehnergii soedinennogo korolevstva; Coordinacion Administrativa de la Gestion y la Contabilidad de Materiales Fisionables en la Comision de Energia Atomica del Reino Unido

    Energy Technology Data Exchange (ETDEWEB)

    Hood, St. C.C. [United Kingdom Atomic Energy Authority, London (United Kingdom)

    1966-02-15

    of fissile material within the Authority for civil purposes during the year ending 31.3.65. (author) [French] En tant que fournisseur, l'Autorite s'occupe de la production, de la distribution, du recyclage et du traitement chimique des matieres fissiles. En tant que consommateur, elle a besoin de matieres fissiles pour ses reacteurs de puissance, pour une serie de prototypes, pour ses reacteurs d'essai des materiaux, pour ses reacteurs de puissance zero et pour ses travaux de mise au point de combustibles; il lui en faut egalement, en petites quantites, pour ses experiences et ses recherches en laboratoire. L'Autorite confie a quatre groupes la direction de ces. activites. Elle a juge utile de faire suivre regulierement ces activites par des comites specialises intergroupes ayant un secretariat commun. Ces comites ont les attributions suivantes: a) etudier tous travaux ou projets de travaux qui necessitent l'utilisation de quantites importantes de matieres fissiles (plutonium et uranium enrichi a l'exclusion de l'uranium naturel ou de l'uranium appauvri en uranium-235), en tenant compte de tous les approvisionnements prevus pendant un certain nombre d'annees en provenance de toutes sources, y compris la production sur place, la recuperation des dechets et les importations; en tenant compte aussi de toutes les utilisations, y compris la combustion, les pertes et les exportations; b) recommander, compte tenu des autres besoins en matieres disponibles et des imperatifs economiques, la meilleure attribution possible de quantites determinees destinees a des fins agreees; c) enregistrer toutes les attributions approuvees de matieres et suivre leur utilisation, et etudier la nature, les quantites et la destination de tous les stocks existants en tenant compte des directives en vigueur et des objectifs poursuivis; d) enregistrer et etudier toutes les pertes de matieres fissiles en cours de fabrication ou de traitement ainsi que les mesures prises pour les reduire; e) aider a

  4. 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)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1954-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1954-07-01

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

  8. A critical summary of microscopic fast-neutron interactions with reactor structural, fissile and fertile materials; Apercu critique des interactions microscopiques des neutrons rapides avec les materiaux de construction et les matieres fissiles et fertiles utilisees dans les reacteurs; Kriticheskij obzor mikroskopicheskog o vzaimodejstviya bystrykh nejtronov s konstruktsionnymi, rasshcheplyayushchimis ya i vosproizvodyashchim i reaktornymi materialami; Resumen critico de las interacciones microscopicas de los neutrones rapidos con los materiales estructurales fisionables y fertiles utilizados en los reactores

    Energy Technology Data Exchange (ETDEWEB)

    Smith, A B [Argonne National Laboratory, Argonne, IL (United States)

    1962-03-15

    Prevailing knowledge of fast-neutron-induced reactions utilized in the nuclear design of reactor systems is reviewed. Principal emphasis is placed upon microscopic experimental methods, results and precisions. Fast-neutron scattering is considered in detail, including the results of experimental determinations of scattering from oxygen, iron, zirconium, niobium, tungsten, thorium and uranium. Representative results of experimental studies of fast-neutron capture and fast-neutron-induced fission are given. The measurements discussed not only provide results of considerable applied usefulness but axe also examples of the application of advanced experimental nuclear techniques. Areas of limited, conflicting or non-existent experimental information are outlined. A prognosis of future knowledge of fast-neutron reactions is made, with emphasis on the fulfillment of reactor requirements for basic nuclear data. (author) [French] L'auteur fait le point des connaissances sur les reactions provoquees par les neutrons rapides sur lesquelles on tend a fonder les projets de reacteurs. Il met en relief les methodes, les resultats et la precision de mesures experimentales a l'echelle microscopique. Il etudie en detail la diffusion des neutrons rapides, et donne les resultats de mesures experimentales de diffusion dans l'oxygene, le fer, le zirconium, le niobium, le tungstene, le thorium et l'uranium. Il donne les resultats les plus significatifs d'etudes experimentales sur la capture des neutrons rapides et sur la fission provoquee par des neutrons rapides. Les mesures etudiees, non seulement fournissent des renseignements d'une utilite pratique considerable, mais aussi constituent des exemples de l'application de techniques experimentales nucleaires a la pointe du progres. L'auteur indique les domaines ou les donnees experimentales sont limitees, contradictoires ou inexistantes. Il se livre a des pronostics sur le developpement des connaissances experimentales en matiere de

  9. 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)

  10. Viewpoint held by the -Robin des bois- environment protection association regarding radioactive waste

    International Nuclear Information System (INIS)

    Bonnemains, J.

    2011-01-01

    For twenty years, the 'Robin des Bois' association has held the belief that every country must manage the hazardous waste, including radioactive waste, that it produces. The vehemence of German anti-nuclear activists in rejecting the return of waste produced by recycling irradiated fuel from German nuclear power plants runs counter to the principles of responsibility and proximity to which ecologists claim to adhere. There are more reasonable means available than refusing to manage end-of-cycle nuclear waste, such as blockading power plants or the uranium enrichment plant in Gronau which supplies the nuclear power industry worldwide. In Lower Saxony, the La Hague plant located on this West European headland is therefore thought of as the ideal hideaway for this waste. It is true that the list of radioactive scrap, hospital waste, asbestos from the steamer, the Norway, and WEEE exported by Germany is long. Robin des Bois is against recycling irradiated fuel as it facilitates the proliferation and dispersion of plutonium and other radionuclides into the environment. The association has revealed many scandals and lies related to recycling in areas other than the nuclear industry, which have been concealed behind the false good ecological and systematically positive image of recycling. (author)

  11. Some Possibilities of Radiation Polymerization from the Gaseous Phase on Solid Bases; Possibilites de polymerisation radiochimique en phase gazeuse sur des lits de matiere solide; O nekotorykh vozmozhnostyakh radiatsionnoj polimerizatsii iz gazovoj fazy na tverdykh podlozhkakh; Perspectivas de la radiopolimerizacion en fase gaseosa sobre lechos de sustancias solidas

    Energy Technology Data Exchange (ETDEWEB)

    Tsetlin, B. L.

    1963-11-15

    The unusual feature of graft polymer synthesis by solid ''bed'' irradiation in the presence of monomer vapours is that the activation centres initiating polymerization are in practice generated only on the bed; transmission of the kinetic chain to the monomer is impeded and new polymer chains grow only under the influence of the solid bed molecular forces. These features of gas phase processes enlarge the scope of the graft polymer technique, making it applicable to inorganic beds and usable in the synthesis of mineral organic products. If stretched synthetic fibres are used as a bed, on the other hand, their orientated macromolecules control the growth of new polymer chains and the graft polymer is formed directly as an orientated structure. Two-component combined fibres are formed as a result and the fibre-bed and ''grafted'' fibre may in appropriate circumstances each display their own particular complex of mechanical properties. (author) [French] La synthese des polymeres greffes par irradiation de ''lits'' de matiere solide en presence de vapeur de monomeres en voie de polymerisation presente les particularites suivantes: les centres actifs qui amorcent la polymerisation ne se forment pratiquement qu'a la surface du ''lit''; le transfertau monomere de la chaine en mouvement est rendu plus difficile; les nouvelles chafnes du polymere se developpent sous l'action unilaterale des forces moleculaires de la surface solide. Ces particularites du processus en phase gazeuse elargissent les possibilites qu'offre la methode de la polymerisation par greffage. La methode peut alors etre egalement appliquee aux lits non organiques et servir a la synthese de composes organomineraux. En revanche, lorsqu'on utilise comme lits des fibres synthetiques allongees, les macromolecules orientees de ces dernieres dirigent la croissance des nouvelles chaines du polymere de sorte que le polymere greffe se forme directement a l'etat oriente. On obtient ainsi des fibres cominees a deux

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

    Numerous physical, chemical and biological processes influence the distribution of radioactive materials and their return to man. These include vertical and horizontal advection, turbulent diffusion, precipitation and sedimentation, uptake concentration, and transport by organisms, and transfer to man through his food from the sea. Research is urgently needed on the flushing characteristics of typical harbours, estuaries and open coastal waters, on diffusion and sedimentation processes in inshore waters, and on the passage of radioactive elements through the food web in this portion of the sea. Research is needed to delineate present and potential fishing areas, and non-fishing areas, by basic studies of biological productivity and other means. Studies are also required to determine rates of transfer of radioactive materials between areas by horizontal advection and turbulent diffusion, rates of dilution by diffusion, sedimentation, and vertical transport, and rates of uptake and transfer by the biota. Research is required on efficient means of monitoring waste disposal areas. The ability of certain organisms selectively to concentrate particular elements offers a possible economical basis of monitoring radioactive wastes in the sea at very low concentrations. Specific research proposals have been recently developed by several groups of oceanographers in the United States. These are summarized, together with cost estimates. (author) [French] De nombreux processus physiques, chimiques et biologiques influent sur la repartition des matieres radioactives et sur leur retour a l'homme. Parmi ces processus, il y a notamment l'amenee verticale et horizontale, la diffusion turbulente, la precipitation et la sedimentation, l'entrainement, la concentration et le transport par des organismes, et leur transfert a l'homme par les aliments qu'il retire de la mer. Des recherches s'imposent d'urgence sur les caracteristiques de curage des eaux dans les ports, estuaires et rades

  13. The System for Controlling Source and Special Nuclear Material at the Eurochemic Reprocessing Plant; Systeme de Controle des Matieres Nucleaires Brutes et Speciales a l'Usine de Traitement D'Eurochemic; Sistema kontrolya nad iskhodnym i spetsial'nym yadernym materialom na zavode evrokhimicheskoj kompanii po regeneratsii yadernogo topliva; Control de Materiales Nucleares Basicos y de Materiales Fisionables Especiales en la Planta de Regeneracion de la Eurochemic

    Energy Technology Data Exchange (ETDEWEB)

    Frenzel, W.; Schueller, W. [EUROCHEMIC, MOL (Belgium)

    1966-02-15

    Eurochemic is constructing a reprocessing plant near Mol (Belgium). The main characteristics of the plant and the different process steps are summarized. To maintain proper control of source and special nuclear material, the facilities of the company are divided into material balance areas. All transfers into and out of these areas are determined. Depending on their significance for the overall material balance, different precision requirements have been established according to a scale of significance which is briefly discussed. To adjust the book balance, physical inventories are periodically performed. The corresponding inventory procedures are outlined. The books used for nuclear materials accounting and the principles of the accounting system are summarized. (author) [French] La societe Eurochemic fait actuellement construire une usine de traitement chimique pres de Mol (Belgique). L'auteur indique succinctement les principales caracteristiques de l'usine et les differentes etapes du traitement. Pour assurer un controle correct des matieres nucleaires brutes et speciales, les installations d'Eurochemic sont divisees en secteurs de mesures. Tous les transferts entre ces secteurs de mesure sont determines quantitativement. Les mesures sont faites avec des degres de precision differents qui ont ete fixes en fonction de leur importance pour le bilan matieres general; les auteurs examinent brievement les criteres appliques a cette fin. Pour verifier le bilan, on procede periodiquement a des inventaires materiels. La facon dont sont menes ces inventaires est exposee dans ses grandes lignes. Les auteurs indiquent les livres utilises pour la comptabilite des matieres nucleaires et resument les principes du systeme comptable. (author) [Spanish] La compania Eurochemic esta construyendo una planta de regeneracion en Mol (Belgica). Los autores resumen las principales caracteristicas de la instalacion, y las distintas fases del proceso industrial. Para mantener un control

  14. Various possible ways to express the toxicity of radioactive substances in relation with the involved practical problems; Diverses expressions possibles de la toxicite des substances radioactives en fonction des problemes pratiques poses

    Energy Technology Data Exchange (ETDEWEB)

    Jammet, H; Vacca, G [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1959-07-01

    Radioelements have at the same time physico-chemical and radioactive properties. It is then possible to establish two types of toxicological classifications: one in function of the weight of the radioelement, another in function of its activity. More often, the maximum permissible amounts (MPA) in the human body and the maximum permissible concentrations (MPC) in air and water are expressed in microcuries by millilitre ({mu}c/ml), less frequently in micrograms by millilitre ({mu}g/ml). The comparison of these tables of MPA and MPC shows important differences in the classification of radioactive substances by order of decreasing toxicity. Plutonium and radium, being among the most toxic products when the activity is considered are far from being the most dangerous when the weight is considered. On the other hand, {sup 131}I and {sup 56}Mn, for instance appear to be among the most hazardous substances in this eventuality. This twofold consideration corresponds to two aspects of the problems of the toxicity of radioisotopes. The classification by activity is almost exclusively utilised because the toxicological measurements are based on the radioactive properties of the radioisotopes. In general, only these measurements allow to detect the very small amounts of substance usually involved. On the other hand, the toxicity related to internal contamination by radioisotopes depends mostly from their metabolism which is exclusively a function of their physico-chemical properties. Therefore the classification by weight gives the best representation of the hazards encountered when radioactive substances are inhaled or ingested. As a result, the relative toxicity of radioisotopes cannot be based on the classification by activity only. The present division of radioisotopes into different classes: very hazardous, moderately hazardous, slightly hazardous must be revised. (author) [French] Les radioelements presentent a la fois des proprietes physico-chimiques banales et des

  15. Nuclear Materials Management in Relation to Safety and Criticality Control: A Study of Non-Inherently Safe Systems; La Gestion des Matieres Nucleaires dans ses Rapports avec la Securite et le Controle de la Criticite; Etude des Systemes a Securite Non Inherente; Obrashchenie s yadernymi materialami s uchetom bezopasnosti i kontrolya za kritichnost'yu. izuchenie sistem dopolnitel'noj avarijnoj zashchity; La Administracion de Materiales Nucleares y sus Relaciones con la Seguridad y el Control de la Criticidad; Estudio de los Sistemas de Seguridad No Inherente

    Energy Technology Data Exchange (ETDEWEB)

    Fruchard, Y. [Commissariat a l' Energie Atomique, Marcoule (France)

    1966-02-15

    concentrated solutions and wet precipitates are treated. This is the realm of safe geometry. Materials management is of less direct interest here but is still an important factor as far as safety is concerned (where special action, cleaning of equipment, etc. is necessary). In the third section, for the treatment of dry products, control by mass is required and materials management presents no particular difficulty. An additional field which, although less, obvious, is nevertheless of paramount importance from the point of view of safety is that of recycling and waste processing. A look at the list of criticality accidents in the United States of America is sufficient to show that five out of six accidents were connected more or less directly with waste processing. If we examine these accidents in greater detail, we can observe that in most cases one of the contributory causes to a criticality accident was faulty management of fissionable materials. The ''over-all'' importance of the relation between safety and nuclear materials management should also be stressed. Although this management may not always form the basis of ''primary'' criticality control, it is still indispensable throughout any process since what is done in this respect in one section of a plant is of significance with regard to the safety of neighbouring sections, especially that concerned with waste processing. (author) [French] La production, la mise en oeuvre et la manutention de certaines matieres fissiles comportent un type de danger particulier qui est le risque de criticite. L'art de l'ingenieur est d'eviter ce risque, au moindre prix, sans trop gener le travail de production ou de transformation. Pour ecarter ce risque, il existe, en premiere approximation, trois methodes preventives; une limitation de la concentration des solutions, une limitation de la masse, un choix judicieux des geometries. La tendance est d'employer au maximum la troisieme methode, autrement: dit de fonctionner avec des systemes

  16. Instructions for use of radioactive sources; Notices d'utilisation des sources radioactives

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-01-15

    In the industrial and research domain, article L.1333-4, R.1333-26 and R.1333-27 of the public health code submit to authorization of the minister of health the 'nuclear following activities ': the manufacturing of radionuclides; the manufacturing of products or devices by containing; the import, the export of radionuclides, products or devices that contain some; the distribution of radionuclides, of products or devices that contain some; the use of devices emitting X-rays or radioactive sources and the use of accelerators others than electron microscopes; the irradiation of products whatever nature it is, including food products. The activity bringing to plan the manufacturing or the use of radionuclides (in the form of sealed or not sealed sources) there is, in the terms of the public health code (C.S.P.) and except in the cases of exemption which are mentioned there, the obligation to obtain an authorization to hold and to make or to use these radionuclides. The regulations in radioprotection being in full evolution, one will find in these notices the main evolutions relative to the regime of authorizations. (N.C.)

  17. Monte-Carlo method for studying the slowing down of neutrons in a thin plate of hydrogenated matter; Methode de Monte-Carlo pour l'etude du ralentissement des neutrons dans une plaque mince de matiere hydrogenee

    Energy Technology Data Exchange (ETDEWEB)

    Ribon, P; Michaudon, A [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1965-07-01

    The studies of interaction of slow neutrons with atomic nuclei by means of the time of flight methods are made with a pulsed neutron source with a broad energy spectrum. The measurement accuracy needs a high intensity and an output time as short as possible and well defined. If the neutrons source is a target bombarded by the beam of a pulsed accelerator, it is usually required to slow down the neutrons to obtain a sufficient intensity at low energies. The purpose of the Monte-Carlo method which is described in this paper is to study the slowing down properties, mainly the intensity and the output time distribution of the slowed-down neutrons. The choice of the method and parameters studied is explained as well as the principles, some calculations and the program organization. A few results given as examples were obtained in the line of this program, the limits of which are principally due to simplifying physical hypotheses. (author) [French] l'etude de l'interaction des neutrons lents avec les noyaux atomiques par la methode du temps de vol s'effectue avec une source pulsee de neutrons dont le spectre en energie est assez etendu. La precision des mesures demande que la source soit intense et que la duree d'emission des neutrons soit breve et bien definie. Si la source est une cible bombardee par le faisceau de particules d'un accelerateur pulse, il est generalement indispensable de ralentir les neutrons pour avoir une intensite suffisante a basse energie. Nous presentons ici une methode de Monte-Carlo pour l'etude detaillee de ce ralentissement, notamment l'intensite et la distribution des temps de sortie des neutrons ralentis. Cette presentation comprend: la justification du choix de la methode de Monte-Carlo, les principes generaux, les differentes etapes du calcul et du programme ecrit pour le calculateur electronique IBM 7090. Nous indiquons aussi les restrictions qui sont apportees au domaine d'application de ce programme et qui proviennent surtout des

  18. Influence of the Previous History of the Raw Material on Sintering of UO{sub 2}; Influence des antecedents de la matiere premiere sur le frittage de UO{sub 2}; Vliyanie obrabotki iskhodnogo veshchestva na spekanie UO{sub 2}; Influencia de la historia previa de la materia prima sobre la sinterizacion del UO{sub 2}

    Energy Technology Data Exchange (ETDEWEB)

    Aparicio, E.; Alonso, J. A.; Pedregal, J. D. [Junta de Energia Nuclear Madrid (Spain)

    1963-11-15

    An account is given of the experimental principles underlying the production process of a UO{sub 2} pellet plant. In this process, advance determination of the particle-size distribution characteristics of the raw material is secured not by means of controlled precipitation but by the crushing and grading of powders. The uranium oxides tested in this work are conventional materials, representing types of fabrication which differ by origin and method used. A study of the pellets obtained shows the potentialities and limitations of each type of oxide in the process adopted. A description is given of the characteristics of the powders as regards specific area, particlesize distribution, differential and thermogravimetric thermal analyses, and stoichiometry, and of the density, contraction, structure and stoichiometry of the pellets. (author) [French] Les auteurs decrivent les experiences qui ont servi de base aux operations d'une installation de fabrication de pastilles d'UO{sub 2}. Selon la methode employee, pour fixer a l'avance les caracteristiques granulometriques de la matiere premiere, on ne procede pas a une precipitation controlee, mais a un broyage et a un criblage des poudres. Les uranes qui ont fait l'objet de ce travail sont des produits classiques provenant de fabrications qui different par l'origine et le procede de transformation. De l'etude des pastilles obtenues, on deduit les possibilites et les limites de chaque type d'urane par rapport au procede adopte. On controle les caracteristiques suivantes: pour les poudres, la surface specifique, la granulometrie; les proprietes thermiques differentielles et thermogravimetrique et la stoechiometrie; pour les pastilles, la densite, la contraction, la structure et la stoechiometrie des pastilles. (author) [Spanish] Se exponen los fundamentos experimentales sobre los que se basa el proceso de una planta de fabricacion de pastillas de UO{sub 2} . En este proceso no se emplea la precipitacion controlada como

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

    1946 a 1957 inclusivement, on a immerge, au large de la cote de Californie, un total de 16.288 bidons de 230 litres environ, remplis de dechets a faible radioactivite. Au cours de ces operations d'evacuation dans les eaux des Etats-Unis, on s'est efforce d'observer deux criteres principaux: 1) assurer la securite des manipulations entre la source des dechets et le lieu d'evacuation et 2) d'engloutir de facon appropriee les dechets dans la mer. Aucune condition n'a ete fixee au sujet de l'integrite du recipient ou du contenu, une fois parvenus dans les profondeurs de la mer. Le memoire expose d'autres methodes pour renfermer des dechets radioactifs qui ont ete utilisees ou suggerees precedemment: mise en recipients metalliques, adsorption sur de l'argile et integration dans du verre. Afin de rendre les dechets radioactifs inoffensifs pour les poissons et autres organismes aquatiques, il faut 1) soit les isoler du milieu environnant, 2) soit les disperser afin d'abaisser leur radioactivite a, la concentration autorisee. Il a ete propose, pour isoler les dechets du milieu environnant, de les placer dans un recipient spherique construit selon un plan approprie, scelle hermetiquement et capable de resister a de hautes pressions; il servirait pour l'elimination des dechets solides a radioactivite faible ou moyenne. Les poissons peuvent etre affectes par les dechets radioactifs de plusieurs manieres : 1) par rayonnement direct des matieres radioactives eliminees; ' 2) par ingestion d'organismes alimentaires contenant des radioisotopes concentres ; 3) par irradiation de l'eau contenant des ions ou particules radioactifs et 4) par contamination, au contact de matieres riches en radioisotopes precipitees en profondeur. L'auteur pense qu'il est bon de poursuivre les recherches avant d'autoriser l'elimination en grand des dechets radioactifs dans la mer. (author) [Spanish] Los desechos de baja radiactividad suelen ser, por lo general, basuras de laboratorio contaminadas, piezas de

  1. A remark on the effect f organic materials on the migration of {sup 90}Sr in the soil; Une remarque sur l'effet des matieres organiques dans la migration du {sup 90}Sr dans le sol

    Energy Technology Data Exchange (ETDEWEB)

    Gailledreau, C.

    1960-05-05

    After having presented different characteristics of the migration of iron in soils submitted to an intense leaching, and noticed that a similar process could be at the origin of the quick displacement of a radioactive contamination due to wastewater releases or fallouts, the author reports an experimental study performed by using one of the most hazardous radio-element, strontium 90, placed at the top of an earth column in which an anaerobic fermentation occurs. The strontium migration is compared with that in a similar column but without fermentation. Calcium migration and pH are measured. The migration behaviour of strontium appears to be very similar to that of calcium.

  2. Status of Research and Developmental Studies on Radiation Pasteurization of Fish and Shellfish in the United States; Etat des Etudes et des Realisations en Matiere de Radiopasteurisation des Poissons, Crustaces et Mollusques aux Etats-Unis; Sostoyanie nauchno-issledovatel'skikh rabot po radiatsionnoj pasterizatsii ryby i krabov v soedinennykh shtatakh; Estado de las Investigaciones y Estudios Experimentales Sobre la Radiopasteurizacion de Pescados y Mariscos en los Estados Unidos

    Energy Technology Data Exchange (ETDEWEB)

    Slavin, J. W.; Ronsivalli, L. J.; Connors, T. J. [United States Bureau of Commercial Fisheries Technological Laboratory, Gloucester, MA (United States)

    1966-11-15

    . In co-operation with private and governmental organizations, irradiated sea foods have been shipped across the United States in commercial carriers and evaluated for quality., Results are very encouraging and indicate that the process would be extremely valuable to industry. Irradiation of fish at sea shows promise as a means of increasing the landings of fresh fish. Preliminary findings indicate that it may be feasible to irradiate eviscerated groundfish at sea with levels less than 100 000 rad and then re-irradiate the fish ashore after filleting and packaging. (author) [French] Le memoire donne un apercu des recherches sur la radiopasteurisation des poissons, crustaces et mollusques aux Etats-Unis et expose les plans de commercialisation de ce procede. Les auteurs examinent: a) les etudes de laboratoire dans les universites et les instituts de recherche de l'Etat sur la qualite et les aspects microbiologiques des produits marins irradies; b) les essais d'irradiation des poissons a terre et en mer; c) l'autorisation officielle, aux Etats-Unis, de la vente des produits de la mer radiopasteurises et de l'utilisation de ce procede par l'industrie de la peche. Les etudes sur la qualite des produits indiquent que l'irradiation avec du cobalt-60 a des doses de 150 000 a 450 000 rad permet au moins de doubler la duree de conservation sous refrigeration de 16 especes de poissons et de crustaces ou mollusques, dont les principales especes vendues aux Etats-Unis a l'etat frais ou congele. La temperature d'emmagasinage, la qualite de la matiere premiere et la dose influent considerablement sur la qualite du produit et la duree de conservation; remballage presente une importance moindre. Les effets synergetiques obtenus par remploi de sels bactericides ou de la chaleur en combinaison avec les rayonnements detruisent efficacement les bacteries et permettront sans aucun doute de reduire les doses de rayonnements et d'assurer une conservation plus longue qu'apres un traitement

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

  4. The radioactivity of the Hercynian Vosges; La radioactivite des Vosges hercyniennes

    Energy Technology Data Exchange (ETDEWEB)

    Rothe, J.P. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires; Institut de Physique du Globe de Strasbourg, 67 (France)

    1957-07-01

    On november 22, 1950, in the course of the formal beginning of term ceremony, the University of Strasbourg was pleased to confer on Professor VENING-MEINESZ the degree of Doctor Honoris Causa. In his speech of acknowledgement, Professor VENING-MEINESZ paid tribute to the fact that his colleague, Edmond ROTHE, had created at Strasbourg a centre of radio-geological research and during his visit to the Institute of Terrestrial Physics, the scholar whom we are honouring today expressed an interest in the new measurements that I was able to show him. I am happy to offer to him in homage some results of a systematic study of radioactivity of the Hercynian Vosges. (author) [French] Le 22 novembre 1950, au cours de sa seance solennelle de rentree, l'Universite de Strasbourg avait la joie de decerner au professeur VENING-MEINESZ le grade de Docteur Honoris Causa. Dans son allocution de remerciements, le professeur VENING-MEINESZ voulait bien rappeler que son collegue Edmond ROTHE avait cree a Strasbourg un centre de recherches de radiogeologie; et vistant l'Institut de Physique du Globe, le savant que nous honorons aujourd'hui acceptait de s'interesser aux mesures nouvelles que je pus alors lui presenter. Je suis heureux de lui offrir en hommage quelques resultats d'une etude systematique de radioactivite des Vosges hercyniennes. (auteur)

  5. The radioactivity of the Hercynian Vosges; La radioactivite des Vosges hercyniennes

    Energy Technology Data Exchange (ETDEWEB)

    Rothe, J P [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires; Institut de Physique du Globe de Strasbourg, 67 (France)

    1957-07-01

    On november 22, 1950, in the course of the formal beginning of term ceremony, the University of Strasbourg was pleased to confer on Professor VENING-MEINESZ the degree of Doctor Honoris Causa. In his speech of acknowledgement, Professor VENING-MEINESZ paid tribute to the fact that his colleague, Edmond ROTHE, had created at Strasbourg a centre of radio-geological research and during his visit to the Institute of Terrestrial Physics, the scholar whom we are honouring today expressed an interest in the new measurements that I was able to show him. I am happy to offer to him in homage some results of a systematic study of radioactivity of the Hercynian Vosges. (author) [French] Le 22 novembre 1950, au cours de sa seance solennelle de rentree, l'Universite de Strasbourg avait la joie de decerner au professeur VENING-MEINESZ le grade de Docteur Honoris Causa. Dans son allocution de remerciements, le professeur VENING-MEINESZ voulait bien rappeler que son collegue Edmond ROTHE avait cree a Strasbourg un centre de recherches de radiogeologie; et vistant l'Institut de Physique du Globe, le savant que nous honorons aujourd'hui acceptait de s'interesser aux mesures nouvelles que je pus alors lui presenter. Je suis heureux de lui offrir en hommage quelques resultats d'une etude systematique de radioactivite des Vosges hercyniennes. (auteur)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

  7. Regulations concerning radiation protection and survey; Donnees de la surveillance et regles qui en resultent en matiere de protection contre les rayonnements

    Energy Technology Data Exchange (ETDEWEB)

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

    1958-07-01

    will only be considered with regard to recuperation of uranium after simple machining. (author) [French] 1. L'utilisation croissante de l'energie nucleaire sous toutes ses formes a des fins pacifiques pose des problemes de securite vis-a-vis des travailleurs, des populations et des sites en general. Une etude comparee des risques d'irradiation auxquels le personnel du Commissariat a l'Energie atomique (CEA) a ete expose au cours de l'annee 1957 et des resultats du controle des radiations par les moyens de detection collectifs ou individuels montre que les installations du CEA ont une influence negligeable sur la sante, en raison de la surveillance exercee. 2. Cependant, quelques incidents de contamination et d'irradiation - sommairement indiques ainsi que la maniere dont ils ont ete regles - rendent necessaire l'elaboration d'une reglementation precise definissant les responsabilites respectives, au sein d'un etablissement nucleaire, des services utilisateurs et du Service charge de la Protection contre les Radiations, en matiere de prevention de la contamination. 3. Un ensemble coherent de regles pratiques de prevention et de protection relatives a la detention, la manipulation, le transport et le stockage de sources radioactives scellees ou non scellees, est presente. A cette fin, a partir des recommandations de la Commission Internationale de Protection Radiologique et compte tenu: - de leur nocivite radioactive; de leur activite specifique par unite de masse et du risque de contamination; les radioelements ont ete classes suivant le danger qu'ils presentent par rapport au plutonium. 4. Le Service charge de la Protection contre les Radiations intervient comme conseiller des la conception des laboratoires specialises et veille ensuite a ce que les prescriptions reglementaires de securite soient observees. 5. Des donnees elaborees, indispensables a la protection contre les rayonnements, sont mises a la disposition des utilisateurs en particulier: - table des radio

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1965-01-01

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

  9. New Methods and Facilities for the Measurement of Physical Properties of Reactor Components and Irradiated Materials; Nouveaux Procedes et Instruments de Mesure des Proprietes Physiques des Elements de Reacteur et des Matieres Irradiees; Novye metody i sredstva izmereniya fizicheskikh s vojstv komponentov reaktora i obluchennykh materialov; Nuevos Metodos y Equipos para Medir Propiedades Fisicas de Componentes de Reactor y de Materiales Irradiados

    Energy Technology Data Exchange (ETDEWEB)

    Foerster, F.; Mueller, P. [Institut Dr. Foerster, Reutlingen, Federal Republic of Germany (Germany)

    1965-09-15

    direct reading of the permeability and stainless- steel components. The correlation between permeability and {Delta} ferrite content is explained. Measurements of the {Delta} ferrite percentage across welds in stainless-steel tubes and measurements of the {Delta} ferrite precipitations as a function of the plastic strain are discussed (hammer-forging of reactor fuel-elements). (author) [French] Les auteurs decrivent un instrument permettant de mesurer et d'enregistrer automatiquement le module de Young, le module de cisaillement et la capacite d'amortissement en fonction de la temperature et du temps. On mesure le module de Young en excitant des specimens de diverses dimensions a leur frequence propre. On mesure la capacite d'amortissement d'apres la libre decroissance de la vibration ou la largeur a mi-hauteur de la courbe de resonance. Le memoire donne des exemples de mesures de la guerison apres irradiation et apres deformation inelastique, ainsi que des exemples du degre de graphitisation. Les auteurs demontrent que l'on peut detecter des defauts et des variations de densite dans les banes de graphite. Ils expliquent, en outre, une methode d'etude de la fixation de pastilles d' UO{sub 2} sur des tubes en acier austenitique a parois minces. Us decrivent un four special pour l'etude du comportement elastique ou inelastique de specimens 'chauds ' a des temperatures variant entre 20 et 1000 Degree-Sign C. Les auteurs discutent le controle de la qualite de metaux non ferreux par mesure de ia conductivite electrique au moyen de courants de Foucault et decrivent un instrument permettant de mesurer sans aucun contact la conductivite electrique de metaux non ferreux. Ils expliquent la correlation entre la conductivite electrique et l'allongement sous l'effet des contraintes dans le cas de metaux et d'alliages non ferreux. Ils s'attachent particulierement a la mesure d'echantillons de petites dimensions. Ils decrivent un dispositif pour la mesure directe a distance dans la

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1962-07-01

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

  11. Uses of radioactive isotopes and radiation sources in biological studies in U. A. R; Utilisation des radioisotopes et des sources de rayonnement dans les etudes biologiques en RAU

    Energy Technology Data Exchange (ETDEWEB)

    Hashish, S. E. [Radiobiology Department, U. A. R. Atomic Energy Establishment, Cairo, United Arab Republic (Egypt)

    1970-01-15

    An attempt is made to give examples rather than a review of the uses of radioactive isotopes and radiation sources in biological studies in U.A.R. Studies along these lines started early in 1955 and are still progressing. The prospects of future developments and improvements are unlimited. The studies are classified according to the radio technique adopted. The techniques so far used in U.A.R. include all the techniques known elsewhere. Some detailed modifications and combinations of more than one technique have been successfully introduced. Both in basic and applied biological studies, one or more of the following techniques have been applied, namely tracer technique, isotopic dilution analysis, autoradiography, radiochromatography and electrophoresis, double or multi-bioassays, radioactivation analysis, neutron absorption analysis, and use of different radiation source for somatic and/or genetic effect studies. Mass spectrometry for stable isotopic studies in the field of biology has been recently used. Studies undertaken in the applied fields of biology e. g, in medicine (diagnosis and therapy) and agriculture (soil, plant and animal) have proved extremely valuable from the practical and developmental points of view. (author) [French] Le mémoire a pour objet d'illustrer plutôt que d'exposer systématiquement les utilisations des radioisotopes et des sources de rayonnement dans des études biologiques en République Arabe Unie. Ces études, entreprises au début de 1955, se poursuivent. Les possibilités de développement et de perfectionnement sont illimitées. Les études sont classées d'après la radiotechnique adoptée. Les techniques régulièrement utilisées jusqu' à présent en République Arabe Unie couvrent toute la gamme des techniques connues ailleurs. On a réussi à apporter des modifications de détail et à combiner plusieurs techniques. Dans les études de biologie tant fondamentale qu' appliquée, une ou plusieurs des techniques suivantes

  12. Methodological guide: management of industrial sites potentially contaminated by radioactive substances; Guide methodologique: gestion des sites industriels potentiellement contamines par des substances radioactives

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    At the request of the Ministries of Health and the Environment, IPSN is preparing and publishing the first version of the methodological guide devoted to managing industrial sites potentially contaminated by radioactive substances. This guide describes a procedure for defining and choosing strategies for rehabilitating such industrial sites. (author)

  13. 1. round table - Spent fuels composition. Back-end of the fuel cycle and reprocessing, plutonium and other nuclear materials management. 2. round table - Separation-transmutation. 3. round table - Scenarios for a long term inventory of nuclear materials and wastes; 1. table ronde - La composition des combustibles uses. L'aval du combustible et le retraitement, la gestion du plutonium et des autres matieres nucleaires. 2. table ronde - Separation-transmutation. 3. table ronde - Scenarii pour un inventaire des matieres et des dechets nucleaires a LT

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    The law from December 30, 1991, precisely defines 3 axes of researches for the management of high level and long-lived radioactive wastes: separation/transmutation, surface storage and underground disposal. A global evaluation report about these researches is to be supplied in 2006 by the French government to the Parliament. A first synthesis of the knowledge gained after 14 years of research has led the national commission of the public debate (CNDP) to organize a national debate about the general options of management of high-level and long-lived radioactive wastes before the 2006 date line. The debate comprises 4 public hearings (September 2005: Bar-le-Duc, Saint-Dizier, Pont-du-Gard, Cherbourg), 12 round-tables (October and November 2005: Paris, Joinville, Caen, Nancy, Marseille), a synthesis meeting (December 2005, Dunkerque) and a closing meeting (January 2006, Lyon). This document is the synthesis of the round table debates which took place at Paris on the reprocessing of spent fuels. Three aspects are discussed: the risks linked with the recovery of valorizable materials, the economical viability of the separation/transmutation option, and the future of the nuclear option in the French energy policy. Six presentations (transparencies) are attached with these proceedings which treat of: the reprocessing/recycling to the test, perspectives of future wastes, present day wastes/valorizable materials and future scenarios, critical analysis scenarios, why reprocessing spent fuels?, processing of spent fuels and recycling, separation and transmutation of long-lived radioactive wastes, thorium-uranium cycle. (J.S.)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2003-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

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

  16. Research strategies and programs related to the National Plan of Management of Radioactive Materials and Wastes. Issue 2008

    International Nuclear Information System (INIS)

    2008-01-01

    After having recalled the legal context defining the requirements of the PNGMDR (Plan national de gestion des matieres et dechets radioactifs, national plan of management of radioactive materials and wastes), this report presents several research programs which address various domains: waste packaging and behaviour (decontamination, waste characterization, waste processing, the storage sizing inventory model, parcel behaviour, used fuel evolution, future wastes), warehousing and storage in deep geological formation (characterization of the Meuse/Haute-Marne site, scientific program, simulation programs, measurement means for storage monitoring, knowledge base, security and reversibility options for storage design, security studies, warehousing options), storage of radiferous and graphite wastes, investigation of separation/transmutation scenarios, investigations related to separation, investigations related to fuel fabrication, investigations related to the transmutation of minor actinides, researches in social and human sciences

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-01

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

  18. Possibility of using radioactivity control measurements for determining contamination paths in nutritional vectors; Etude des possibilites d'utilisation des resultats de la surveillance de la radioactivite pour la recherche des trajectoires d'evolution de la contamination des vecteurs alimentaires

    Energy Technology Data Exchange (ETDEWEB)

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

    1966-07-01

    The object of the report is to study the possibility of using results of radioactivity controls for determining the paths followed by contamination in nutritional vectors; these are necessary for calculating protection norms. Radioactive contamination of a nutritional vector is expressed in terms of parameters which suggest that a certain number of criteria may be used for choosing the results which are to be exploited. An actual example of a 'vertical' study based on results of measurements made purely for control purposes shows the difficulties which may be encountered. A list of the results obtained by the control networks set up in the Community Countries, either for the atmosphere, for milk, or for other foodstuffs, shows that these networks are not at the present organised in such a way as to make such a study possible. It appears desirable that a large part of the work carried out by the control Services be oriented in such a way as to yield the complementary information required for experimental studies of radioactive contamination transfers. (author) [French] L'objet du rapport est l'examen des possibilites d'utilisation des resultats de la surveillance de la radioactivite pour la recherche des trajectoires d'evolution de la contamination des vecteurs alimentaires, necessaires au calcul des niveaux de protection. La contamination radioactive d'un vecteur alimentaire s'exprime en fonction de parametres, qui suggerent de retenir un certain nombre de criteres pour la selection des resultats a exploiter. Un exemple concret d'etude 'verticale' basee sur des resultats de mesures faites uniquement dans un but de controle met en evidence les difficultes rencontrees. L'inventaire des resultats obtenus par les reseaux de controle des differents Pays de la Communaute, soit pour l'atmosphere, soit pour le lait, soit pour d'autres aliments, montre que ces reseaux ne sont pas actuellement organises de facon a permettre de telles etudes, Il parait souhaitable qu

  19. The determination of sulphur in materials of high neutron absorption cross-section by fast-neutron activation analysis; Determination du soufre dans les matieres de forte section efficace d'absorption neutronique, au moyen d'une analyse par activation avec des neutrons rapides; Opredelenie sery v materialakh s bol'shim secheniem pogloshcheniya nejtronov metodom aktivatsionnogo analiza bystrykh nejtronov; Determinacion del azufre en sustancias de elevada seccion eficaz de absorcion neutronica mediante analisis por activacion con neutrones rapidos

    Energy Technology Data Exchange (ETDEWEB)

    Gibbons, D; Simpson, H [Wantage Research Laboratory (A.E.R.E.), Wantage, Berks. (United Kingdom)

    1962-01-15

    The production of radiophosphorus by the fast neutron (n, p) reaction on sulphur is used for the determination of sulphur by activation analysis. Using this technique it is possible to determine sulphur in materials of high thermal-neutron absorption cross-section because the absorption cross-sections for fast neutrons are, in general, much lower than those for slow neutrons, so that self-shielding errors are considerably reduced. Interference due to the slow neutron (n, {gamma}) reaction on neutral phosphorus is eliminated by a double irradiation technique involving irradiation in regions of differing slow/fast flux-ratios. The method has been applied to the determination of sulphur in chromium and arsenic. (author) [French] La production de radiophosphore par reaction (n, p) de neutrons rapides sur le soufre est utilisee pour la determination du soufre au moyen d'une analyse par activation. Cette methode permet la determination du soufre dans les matieres de forte section efficace d'absorption des neutrons thermiques; en effet, les sections efficaces d'absorption des neutrons rapides sont, d'une maniere generale, beaucoup plus faibles que pour les neutrons lents, de sorte que les erreurs d'autoprotection se trouvent considerablement reduites. L'interference due a la reaction (n, {gamma}) des neutrons lents sur le phosphore naturel est eliminee par une double irradiation, qui implique une irradiation dans les regions ou le rapport du flux de neutrons lents au flux de neutrons rapides a des valeurs differentes. La methode a ete appliquee a la determination du soufre dans le chrome et l'arsenic. (author) [Spanish] La formacion de fosforo radiactivo por la accion de los neutrones rapidos sobre el azufre, reaccion (n, p), puede servir para determinar este elemento mediante analisis por activacion. El empleo de esta tecnica permite efectuar determinaciones de azufre en materiales de elevada seccion eficaz de absorcion de neutrones termicos porque, en general, las

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Perot, B

    1997-12-31

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

  2. The CNRN Research Programme for the Study of Radioisotope Accumulation by Marine Organisms and its Effects as Regards Radioactive Contamination of the Ocean; Le Programme de Recherches du CNRN sur l'Accumulation des Radioisotopes par les Organismes Marins et son Effet sur la Contamination Radioactive de l'Ocean; 041f 0420 041e 0414 ; Programa de Investigaciones del CNRN para Estudiar la Acumulacion de Radioisotopos en los Organismos Marinos y sus Efectos sobre la Contaminacion Radiactiva del Oceano

    Energy Technology Data Exchange (ETDEWEB)

    Buzzati-Traverso, A. A.; Bernhard, M. [National Committee for Nuclear Research (Italy)

    1960-07-01

    The paper describes a research programme undertaken by the Comitato Nazionale per le Ricerche Nucleari (CNRN) with a view to considering the whole complex ecological system of the sea in order to trace the paths of radioactive materials that may reach marine products for human consumption. The programme will start with an intensive study of a limited area representative of the Mediterranean and will fall into two parts, descriptive analysis and experimental analysis. The area chosen, details of the laboratory and staff and the general tasks to be carried out are briefly described. Finally, some early results are given. (author) [French] Le memoire expose le programme de recherches que le Gomitato Nazionale per le Ricerche Nucleari (CNRN) a entrepris en vue d'etudier l'ensemble du systeme ecologique complexe de la mer pour retracer les voies suivies par les matieres radioactives qui peuvent parvenir aux produits marins propres a la consommation humaine. Le programme, qui debutera par une etude intensive d'une petite zone representative de la Mediterranee, se subdivisera en deux parties: analyse descriptive et analyse experimentale. Le memoire decrit succinctement la zone choisie, le laboratoire et le personnel, ainsi que les problemes generaux a resoudre. Il donne enfin quelques-uns des premiers resultats obtenus. (author) [Spanish] En la memoria se describe el programa de investigaciones preparado por el Gomitato Nationale per le Ricerche Nucleari (CNRN) con miras a estudiar: todo el complejo sistema ecologico del mar para determinar el camino seguido, por las sustancias radiactivas que pueden llegar hasta los productos marinos; destinados al consumo humano. El programa comenzara con un estudio minucioso de una limitada zona representativa del Mediterraneo, y se dividira en dos partes, a saber, una descriptiva y otra experimental. Los autores describen brevemente la zona escogida y proporcionan datos relativos al laboratorio, al personal y a los trabajos previstos

  3. Tritium in Meteorites and in Recovered Satellite Material; Tritium dans les meteorites et dans les matieres provenant d'un satellite recupere; Tritij v meteoritakh i v vozvrashchennom sputnike; Tritio en meteoritos y en el material de un satelite recuperado

    Energy Technology Data Exchange (ETDEWEB)

    Fireman, E L [Smithsonian Astrophysical Observatory, Cambridge, MA (United States)

    1962-01-15

    Tritium was measured in separated phases and in whole rock samples of the Bruderheim chondritic meteorite and in samples of lead and iron material of recovered satellites. Radioactive isotopes of argon were also measured. The tritium and argon radioactivity in the Bruderheim meteorite can be reasonably well explained by the interaction of cosmic ray particles of some thousand million volts energy with the meteoritic material. The tritium content of the recovered satellite material was more than a factor of a hundred too large to be explained by the interactions of cosmic rays or by the interactions of solar flare particles with the satellite. The high tritium content of the satellite material must result from a flux of incident tritium particles that stop in the satellite. (author) [French] Tritium dans les meteorites et dans les matieres provenant d'un satellite recupere. On a mesure la teneur en tritium d'echantillons de diverses parties et de l'ensemble de la roche formant la chondrite de Bruderheim, ainsi que celle d'echantillons de plomb et de fer preleves sur des satellites recuperes. On a egalement mesure la teneur en radioargon dans la meteorite de Bruderheim. La presence de tritium et de radioargon peut fort bien s'expliquer par l'interaction d'elements de la meteorite et de rayons cosmiques corpusculaires ayant une energie de l'ordre du milliard de volts. La teneur en tritium des satellites recuperes etait plus de cent fois trop elevee pour pouvoir etre expliquee par une interaction entre les rayons cosmiques ou les particules provenant d'eruptions solaires et le satellite etudie. La forte teneur en tritium des matieres provenant des satellites est certainement due a un flux incident de particules de tritium qui sont retenues dans le satellite. (author) [Spanish] Se midieron las concentraciones de tritio en fases separadas y en muestras enteras de roca del meteorito condritico de Bruderheim, y en muestras de plomo y de hierro de satelites recuperados

  4. Gel nano-particulates against radioactivity; Des nanoparticules en gel contre la radioactivite

    Energy Technology Data Exchange (ETDEWEB)

    Deroin, Ph

    2004-11-01

    The Argonne research center (USA) has developed a 'super-gel' compound, a polymer close to those used in baby's diapers, which can reach a 90% efficiency in the radioactive decontamination of porous materials, like bricks or concrete. The contaminated materials are sprayed with a mixture of polymer gel and wetting agent with nano-particulates in suspension. Under the action of the wetting agent, radioactivity migrates from the pores to the gel and is trapped by the nano-particulates. The drying and recycling of the gel allows to reduce the volume of radioactive wastes. Short paper. (J.S.)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1953-06-15

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

  6. Control apparatus for radioactive contamination of the filtering device adapted on the protection apparatus of the respiratory tracts (1961); Appareil de controle de la contamination radioactive des dispositifs filtrants adaptes sur les appareils de protection des voies respiratoires (1961)

    Energy Technology Data Exchange (ETDEWEB)

    Dujancourt, S; Roche, J [Commissariat a l' Energie Atomique, Centre de Production de Plutonium, Marcoule (France). Centre d' Etudes Nucleaires

    1961-07-01

    That apparatus allows to detect and localize the radioactive contamination of the mask cartridge, for alpha, beta and gamma radiations, concerning external contamination, and for beta and gamma radiations, concerning internal contamination. It consists of lead coffin, in which the cartridge is inserted for control. Halogen counters are in contact with it. Operation conditions (Geiger or proportional) and their position on regard to the cartridge are controlled from outside. A sealer counts the pulses, given by the different counters. (authors) [French] Cet appareil permet de detecter et de localiser la contamination radioactive de cartouches filtrantes de masques, en {alpha}, {beta} et {gamma}, en ce qui concerne la contamination exterieure, et en {beta} et {gamma} en ce qui concerne la contamination interieure. Il est constitue par un coffre en plomb dans lequel est introduite la cartouche a controler. Des compteurs halogenes sont au contact de celle-ci. Leur regime de fonctionnement (Geiger ou proportionnel) et leur position par rapport a la cartouche sont commandes de l'exterieur. Une echelle de comptage compte les impulsions donnees par les differents compteurs. (auteurs)

  7. Management of sites potentially polluted by radioactive substances - Methodological guidebook; Gestion des sites potentiellement pollues par des substances radioactives - Guide methodologique

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-12-15

    This document is the update of the 'methodological guidelines for the management of industrial areas potentially contaminated by radioactive substances', published in 2001 by IRSN. Revisions intended to bring coherence between management of areas polluted by radioactive substances and the general policy applied to polluted sites described in a document published in Feb. 2007 by the French Ministry in charge of Environment. Requirements introduced both by the law relative to waste management of June 28, 2006 and the ministerial order of 17 November 2008 were introduced. The involvement of all stakeholders during the process was stressed. The updating mainly lead to introduce a clear distinction between polluted areas where uses are established and those without use or at redevelopment stage. When the uses are established, an 'Interpretation of the condition of environment' is conducted. Alternatively, the remediation process follows a 'management plan'. The revision also led to the disappearance of the 'doubt removal' phase which has been incorporated as an entire part in the site characterisation. Among other significant changes, it may be noted the evolution of the 'risk assessment' tools from simplified risk assessment and detailed risk assessment to a single tool allowing the quantitative assessment of exposure (EQER). Finally, the guidelines highlight stakeholder involvement in identifying the different participants and in reminding the benefits of a consultative approach. Whatever the remediation process: interpretation of the condition of environment or management plan; site characterisation is required as soon as a pollution is suspected. It includes literature reviews and field investigations primarily to confirm or deny the presence of pollution and, where appropriate, to determine its location, nature and level. The effort accorded to site characterisation must be proportionate to identified issues. The

  8. Manufacture of Wood-Plastic Combinations by Use of Gamma Radiation; Fabrication de combinaisons bois-matiere plastique a l'aide des rayons gamma; Proizvodstvo drevesno-plastmassovykh sostavov s pomoshch'yu gamma-izlucheniya; Impregnacion de maderas con materiales plasticos en presencia de radiaciones gamma

    Energy Technology Data Exchange (ETDEWEB)

    Kent, J. A.; Winston, A.; Boyle, W.; Updyke, L. [Engineering Experiment Station, West Virginia University, Morgantown, West Virginia (United States)

    1963-11-15

    brittleness over the unmodified wood. Data are presented fot hardness, elastic limit in compression, dimensional stability, static bending and shear. (author) [French] d'ethylene glycol, le dimethacrylate de polyethylene glycol, le dtanate de tetraisopropyle, le methacrylate d'allyle et le divlnyle benzene (pour lestyrene). Les essais mecaniques sur les combinaisons bois-matiere plastique montrent que la durete, la limite d'elasticite sous compression, la stabilite dimensionnelle, et certaines autres proprietes sont ameliorees. En revanche, la fragilite augmente. Les autens donnent des chiffres pour la durete, la limite d'elasticite sous compression, la stabilite dimensionnelle, la flexion et le cisaillement. (author) [Spanish] Los autores describen un proceso susceptible de aprovechamiento comercial para producir maderas impregnadas mediante el empleo de los rayos gamma. En este proceso cabe distinguir dos fases : la impregnacion de la madera con el monomero adecuado, y la polimerizacion in situ del monomero por irradiacion gamma. Se estudiaron los factores que ejercen influencia sobre la penetracion del monomero en la estructura de la madera; los ensayos realizados revelaron que, en la practica, es posible lograr una buena distribucion del polimero en el producto resultante. Los autores impregnaron muestras de hasta 4 pulg (10,1 cm) de espesor y 5 pies (1,52 m) de longitud, examinandolas para determinar su penetracion por el monomero, y sometieron con exito otras muestras de espesor analogo,:a un proceso de polimerizacion. El comportamiento de las maderas blandas es muy distinto del de las maderas duras por lo que se refiere a la penetracich del monomero. No obstante, resulta posible, dentro de ciertos limites, regular la absorcion del monomero a fin de alcanzar la concentracion deseada de polfmeros en diversas clases de maderas. La memoria reproduce curvas de conversion correspondientes a la radiopolimerizacion del metacrilato de metilo, acetato de vinilo y estireno en

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Wormser, G.

    1960-05-03

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

  11. 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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1959-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

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

  14. 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.)

  15. 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.)

  16. Determination of diets for the populations of eleven regions of the European community to be used for obtaining radioactive contamination levels. First results concerning the food consumption of individuals classified in nine age-groups; Determination des regimes alimentaires des populations de onze regions de la Communaute Europenne et vue de l'etude des niveaux de contamination radioactive. Premiere serie de resultats concernant la consommation alimentaire des individus groupes en neuf classes d'ages

    Energy Technology Data Exchange (ETDEWEB)

    Ledermann, S; Lacourly, G; Garnier, A; Cresta, M; Lombardo, E [Commissariat a l' Energie Atomique, 92 - Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1968-07-01

    The present document continues the report CEA-R--2979 - EUR--2768-f. The processing of the data given by the family food enquiry carried out in eleven regions of the European Community, has permitted to determine the food consumption of individuals classified in nine age-groups, in order to study the radioactive contamination levels in the food-chain. The used statistical method is described, and the obtained results are presented in form of double-entry tables giving for each region and for each age-group the mean weekly food-consumption and the contribution of each diet in nutrition principles, in minerals, vitamins, trace elements and calories. (authors) [French] Ce rapport fait suite au rapport CEA-R--2979 - EUR--2768-f. Le traitement de l'information apportee par les enquetes alimentaires familiales realisees dans onze regions de la Communaute Europeenne a permis de determiner les consommations alimentaires des individus groupes en neuf classes d'age, en vue de l'etude des niveaux de contamination radioactive dans les chaines alimentaires. La methode statistique employee est decrite et les resultats obtenus sont presentes sous forme de tableaux a double entree donnant pour chacune des regions etudiees et pour chacune des neuf classes d'age, les consommations moyennes hebdomadaires, ainsi que les apports en principes nutritifs, mineraux, vitamines et oligo-elements, et calories de chaque regime. (auteurs)

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

    Energy Technology Data Exchange (ETDEWEB)

    Bourdrez, Jean; Girault, Jacques; Wormser, Gerald

    1962-12-14

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

    The rapid development of nuclear energy demands an urgent solution to the health problems arising from the discharge into the environment of radioactive residues produced by nuclear installations. - To be able to evaluate the risks run by the population and to fix tolerance limits for waste discharge, it is necessary to possess an exact knowledge of the course taken by the radioelements discharged, from their source until they reach man. The incorporation of radioelements in food cycles is the first risk to take into consideration. The factors involved in all stages of this transmission must be foreseen, whether they concern physical or biological media, because of their continuity and their interdependence. Finally, socio-economic and dietetic data must be collected in order that the risks and tolerance levels estimated are based on concrete and experimental rather than theoretical knowledge. The risk of nuclear accidents in the atomic industry, although very improbable, must be taken into consideration because of the seriousness of their consequences. The health problems arise in the field of professional hygiene on the one hand and in that of public hygiene on the other. In the first field the risk is two-fold and involves irradiation and contamination. The public sphere is reduced essentially to the risk of contamination by radioactive substances accidentally released in the surrounding medium. The health studies to be conducted in this field therefore include research not only on irradiation or contamination therapeutics but also on the transfer of radioelements from the accident site to man, mainly through food cycles, in their physical and in their biological components. Studies of this kind form the basis of decisions in the health field which would have to be taken in the case of an accident. (authors) [French] Le developpement rapide de l'energie nucleaire rend urgente la solution des problemes sanitaires poses par le rejet dans le milieu ambiant des

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1968-06-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2009-07-01

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

  1. The observatories for the radioactivity. results of measures; Les observatoires de la radioactivite. resultats des mesures

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    This IPSN's report on the monitoring of the radioactivity in France provides many graphs and tables of measures results recorded during the year 2000. The graphs show the activity levels (Bq or Bq fraction, per mass or volume unit) of many radionuclides in selected indicators and for levels upper than the detection limits. The metrology and the selected samples are presented. These samples are different for the three types of observatories: atmospheric, coast and terrestrial observatories. A chronological account of the results from 1959 to 2000 is also provided for the Cesium 137 and the beryllium 7 in the aerosols. (A.L.B.)

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

  4. Elaboration of an alpha-numeric classification for file of matters of the documentation service of the CEA; Elaboration d'une classification alfha-numerique pour le fichier matieres du service de documentation du Commissariat a l'Energie Atomique

    Energy Technology Data Exchange (ETDEWEB)

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

    1953-07-01

    We give the principles of a classification of matters to square basis, suiting the needs of the Service, of Documentation of the C.E.A. We present the detail of the categories in the order of the 'columns', likewise the big scientific subdivisions at the CEA. (authors) [French] On donne les principes d'une classification matieres a base carree, convenant aux besoins du Service de Documentation du C.E.A. On presente ensuite le detail des rubriques dans l'ordre des ''colonnes'', c'est-a-dire, des grandes subdivisions scientifiques du C.E.A. (auteurs)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

    The purpose of this paper is to discuss the technical and administrative aspects of radioactive waste management in the light of our present experience and knowledge and to relate that discussion to possible future requirements for the adequate engineering, legal and administrative control of radioactive effluents from atomic energy operations. Initially, the various kinds of radioactive wastes are classified in a general way to emphasize that the many-faceted problem of waste management is not susceptible of a single, unique solution. The role of specific environments in waste management practices is briefly summarized and the basic approaches (''dilute and disperse'' and ''concentrate and contain'') to waste control are defined. A distinction is made between basic radiation protection standards and the operating or performance criteria that must be established in connexion with effluent control operations in' order to assure that the basic standards are met. The development of standards and criteria and their application in the promulgation of health and safety regulations and legal and administrative procedures are discussed. In this connexion, the utilization to the maximum practicable extent of existing laws and administrative procedures through existing authorities at various levels of government is suggested as being advantageous from the points of view of public relations and of administration. Although the total costs for treatment and disposal of radioactive wastes are substantial, the cost per unit of electrical energy produced is a rather small percentage of the total cost per unit of energy. Other economic factors related to handling and disposal of wastes are also noted, including the relation of plant site to disposal location. In addition, other considerations related to waste management, such as site selection and transport, are discussed. (author) [French] Les auteurs, a la lumiere des connaissances actuelles, examinent les aspects techniques et

  6. Extraction apparatus used in the treatment of irradiated fuels; Les appareils d'extraction utilises dans le traitement des combustibles irradies

    Energy Technology Data Exchange (ETDEWEB)

    Faugeras, P; Talmont, X [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1960-07-01

    The two qualities necessary in an extractor in the case of solvent extraction of radioactive materials are that they should occupy little space and require little maintenance. In this paper various types of apparatus designed to this effect are examined: firstly mixer-decanter types with mechanical shaking and with shaking and decantation ultrasonically accelerated; then pulsed columns; finally hydro-cyclones. The chemical engineering studies peculiar to the running, supply and control of each of these extractors are described in detail. In certain cases some results obtained on radioactive solutions on a pilot scale are given. (author) [French] Faible encombrement, peu d'entretien, telles sont les deux qualites qu'un extracteur doit posseder dans le cas d'extraction par solvant de matieres radioactives. Dans ce texte seront examines differents types d'appareils concus dans cet esprit: d'abord les appareils typez melangeurs-decanteurs a agitation mecanique, a agitation et decantation accelerees aux ultra-sons; puis les colonnes pulsees; enfin les hydrocyclones. Pour chacun de ces extracteurs seront detaillees les etudes de genie chimique propres a son fonctionnement, a son alimentation, a son controle. Pour certains seront notes quelques resultats obtenus sur des solutions radioactives a l'echelle pilote. (auteur)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

  8. Communications of 15 November 1999 Received from Member States Regarding the Export of Nuclear Material and of Certain Categories of Equipment and Other Material; Communications En Date Du 15 Novembre 1999 Recues D'Etats Membres Concernant L'Exportation De Matieres Nucleaires Et De Certaines Categories D'Equipements Et D'Autres Matieres

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-03-15

    The Director General of the International Atomic Energy Agency has received letters of 17 October 1996 from the Resident Representatives of Argentina, Australia, Austria, Bulgaria, Canada, the Czech Republic, Denmark, Finland, France, Germany, Greece, Hungary, Ireland, Italy, Japan, Republic of Korea, the Netherlands, Norway, Poland, Portugal, Romania, the Russian Federation, the Slovak Republic, South Africa, Spain, Sweden, the United Kingdom, and the United States of America, concerning the export of nuclear material and of certain categories of equipment and other material [French] Le Directeur general de l'Agence internationale de l'energie atomique a recu des lettres datees du 15 novembre 1999 que les representants permanents des pays suivants lui ont adressees au sujet de l'exportation de matieres nucleaires et de certaines categories d'equipements et d'autres matieres : Afrique du Sud, Allemagne, Argentine, Australie, Autriche, Belgique, Bulgarie, Canada, Coree (Republique de), Danemark, Espagne, Etats-Unis d'Amerique, Finlande, France, Grece, Hongrie, Irlande, Italie, Japon, Luxembourg, Norvege, Pays-Bas, Pologne, Portugal, Republique slovaque, Republique tcheque, Roumanie, Royaume-Uni, Suede, Suisse, Turquie et Ukraine.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1962-01-15

    deux surfaces est etudiee en fonction de la vitesse de deplacement, de la rugosite des surfaces en contact et de la presence de lubrifiants. Pour etudier la repartition de l'usure, on insere des chevilles de fonte contenant de l'Ir{sup 192} dans les chemises d'un moteur-diesel et l'on preleve des echantillons d'huile dont on mesure la radioactivite. On utilise des particules radioactives de fer et d'oxyde de fer pour etudier leur role dans le processus d'usure. La reactibilite de surfaces metalliques qui ont travaille est etudiee a l'aide d'acide stearique marque au C{sup 14} et de S{sup 35} en solution. La vitesse de reaction des produits ajoutes a l'huile d'engrenages est etudiee au moyen de courtes impulsions electriques que l'on envoie dans des fils metalliques immerges dans des solutions de composes marques au S{sup 35} et au P{sup 32}. La constitution de pellicules retardant l'usure a la surface des dents d'engrenages est etudiee en fonction de la pression de friction, de la vitesse et du temps de fonctionnement. Un probleme commun a nombre de ces applications est celui de la conversion de l'activite mesuree en quantites absolues de matieres presentes dans les pellicules de surface ou dans les dechets resultant de l'usure. Des methodes de calibrage ont ete mises au point a cette fin. (author) [Spanish] La solucion de muchos de los problemas de lubricacion y desgaste requiere el estudio de procesos que ocurren en escala muy pequena a los que pueden aplicarse con exito metodos de gran sensibilidad basados en el empleo de indicadores radiactivos. Los autores citan varios ejemplos de estas aplicaciones, realizadas en la Lubrication and Wear Division del National Engineering Laboratory (Reino Unido). La memoria estudia la relacion cuantitativa entre la transferencia de metal y la friccion en las capas limite, en funcion de la velocidad de deslizamiento, de la rugosidad de la superficie y de la presencia de lubricantes. A fin de estudiar la distribucion del desgaste

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Petit, J.C

    1998-04-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1959-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

    Various methods which have been considered for processing and treating radioactive wastes of both low and high level are discussed. Low-Level Wastes-Gases are diluted and discharged to the atmosphere through stacks or are filtered through highly retentive filters. Typical installations are described. Incineration of combustible wastes has been examined and descriptions and operating data are given. Baling is often a useful adjunct to a solids collection system. A variety of processes for liquid wastes have been studied. Typical systems are described and operating data given. High-Level Wastes-Gases are sometimes vented directly through stacks but more often some treatment is required. The treatment takes the form of chemical scrubbing, removal of iodine on silver reactors, rare-gas removal and filtration. Highly contaminated solids may require decontamination in place before they can be removed. High-level liquid wastes represent the largest single waste-disposal problem facing the industry at the present time. This problem includes reduction in the volume of the waste originally produced by process changes or changing the process; concentration of the produced waste or reduction to solids by one of several methods including concentration, use of Portland cement, adsorption on clays or other natural materials, and calcination. The technical and economic problems associated with temporary storage are considered. It may become necessary to do waste processing at only a few carefully selected sites. Estimates are made of the amounts that might be involved in transport and of the equipment needed. The attendant hazards and costs are considered. (author) [French] L'auteur etudie les diverses methodes qui ont ete envisagees pour le traitement des dechets de faible et de haute radioactivite. Dechets, de faible radioactivite - Les gaz sont, soit dilues et evacues dans l'atmosphere par de hautes cheminees, soit filtres au moyen d'appareils a grande puissance de filtrage. L

  14. Research into the radio-active contamination of foodstuffs of animal origin; Recherches sur la contamination radioactive des aliments d'origine animale

    Energy Technology Data Exchange (ETDEWEB)

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

    1965-03-01

    The author assembles in a very complete way all the actually available data relating to the transfer of the most important radionuclides from the environment through animal products to man. As these are not directly utilizable for the countries of the European Community, he proposes to go further into the question in order to be able to take into account the changing ecological conditions. (author) [French] L'auteur a rassemble d'une facon tres complete les don ees actuellement disponibles relatives au transfert des radio uclides les plus importants du milieu ambiant par l'intermediaire des aliments d'origine animale a l'homme. Celles i n'etant pas directement utilisables pour les pays de la Communaute Economique Europeenne, il propose des etudes complementaires pour tenir compte de la variabilite des conditions ecologiques. (auteur)

  15. Research into the radio-active contamination of foodstuffs of animal origin; Recherches sur la contamination radioactive des aliments d'origine animale

    Energy Technology Data Exchange (ETDEWEB)

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

    1965-03-01

    The author assembles in a very complete way all the actually available data relating to the transfer of the most important radionuclides from the environment through animal products to man. As these are not directly utilizable for the countries of the European Community, he proposes to go further into the question in order to be able to take into account the changing ecological conditions. (author) [French] L'auteur a rassemble d'une facon tres complete les don ees actuellement disponibles relatives au transfert des radio uclides les plus importants du milieu ambiant par l'intermediaire des aliments d'origine animale a l'homme. Celles i n'etant pas directement utilisables pour les pays de la Communaute Economique Europeenne, il propose des etudes complementaires pour tenir compte de la variabilite des conditions ecologiques. (auteur)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1969-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1958-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-02-24

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1967-11-01

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

  20. Nuclear raw materials; Matieres premieres nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Cameron, J. [Division of Nuclear Power and Reactors, International Atomic Energy Agency, Vienna (Austria)

    1970-01-15

    It is clear that in the next decades there will be a substantial and increasing demand for uranium to fuel nuclear power stations. In a developing country, the discovery and development of uranium resources can be of importance either for the development of national nuclear power or for the commercial export of uranium. As the time taken between the start of a uranium exploration program and the uranium production stage.may be of the order of 6 - 10 years, it is now opportune to start new exploration so that advantage of the increased demand in the mid-1970s may be achieved. Thorium will also be of interest, but in the more distant future when the thorium cycle for advanced converters and breeder reactors is fully developed [French] Il est certain qu' au cours des prochaines décennies la demande d'uranium pour les centrales nucléaires sera importante et ne cessera de croître. Dans un pays en voie de développement, la découverte et la mise en valeur de ressources d'uranium peut avoir une grande importance, soit en vue de produire de l'énergie nucléoélectrique, soit en vue d'exporter l'uranium. Etant donné que les délais entre le démarrage d'un programme de prospection de l'uranium et le début de la production peuvent être de l'ordre de six ans, il est actuellement opportun de commencer les opérations d'exploration pour pouvoir profiter de la demande accrue qui s' affirmera vers le milieu de la prochaine décennie. Le thorium présentera aussi un certain intérêt, mais à plus long terme. Il faut pour cela que le cycle du thorium pour convertisseurs avancés et surgénérateurs ait été pleinement développé. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

    ) [French] L'installation de Hanford se trouve dans une region semi-aride-de sediments non consolides en couche tres epaisse, qui ont ete deposes par les eaux et reposent sur un lit rocheux basaltique. Ces roches forment deux couches geologiques, la couche inferieure etant beaucoup moins permeable que la couche superieure. La Columbia traverse les terrains de l'installation et ce n'est qu'a environ 55 kilometres en aval du dernier reacteur qu'on commence a utiliser les eaux pour la consommation humaine. Les effluents de faible intensite provenant des reacteurs sont evacues dans la Columbia apres un sejour d'une a trqis heuges dans des reservoirs. Dans les effluents, on a pu identifier plus de 60 radioisotopes, qui, pour la plupart, ont y une tres courte periode. On a observe l'appauvrissement de l'eau fluviale en plusieurs radioisotopes par suite de mecanismes autres que la desintegration. Cet appauvrissement atteint 40% en moyenne sur les 55 kilometres qui separent les reacteurs et Pasco; il serait du a des processus d'assimilation biologique et de sedimentation. Les solutions de dechets de faible intensite provenant des usines de traitement chimique sont evacuees dans le sol ou elles filtrent a travers les sediments sur une profondeur de 70 a 120 metres avant d'atteindre la nappe aquifere. Pendant leur passage a travers le sol, la plupart des substances radioactives sont retenues par adsorption ou par d'autres reactions. L'eau et les quelques contaminants qui atteignent le niveau hydrostatique se deplacent avec les eaux souterraines en direction de la Columbia. La vitesse et la direction de ce deplacement sont determines par la forme de la surface piezometrique et les caracteristiques hydrauliques de l'aquifere. La configuration locale de la nappe a ete fortement influencee par l'evacuation de grandes quantites d'eau. Compte tenu du gradient hydraulique et du degre de permeabilite des aquiferes, on estime a 180 annees la duree moyenne du deplacement de J'eau. On reconnait

  3. Rapid method of identification of {beta}-ray emitters and of {beta}-radioactive impurity dosage (1961); Methode rapide d'identification des emetteurs-{beta} et de dosage d'impuretes radioactives-{beta} (1961)

    Energy Technology Data Exchange (ETDEWEB)

    Le Gallic, Y; Legrand, J; Grinberg, B [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1961-07-01

    We describe a simple method of radioactive analysis, which allows an accurate determination of maximal energies of {beta}-emitters, and detection and titration of radioactive impurities in radionuclides as well. The method described, which uses a plastic scintillator, is based on the fact that the curve obtained by plotting the number of pulses measured against the threshold is a straight line, in the case of pure {beta}-emitters. We then derive a simple relation between the data of this straight line and the maximal energy of the {beta}-spectrum of the radionuclide under consideration. (authors) [French] Description d'une methode simple d'analyse radioactive, permettant de determiner avec precision l'energie maximum des emetteurs-{beta}, ainsi que de deceler et de doser les impuretes radioactives dans un radionuclide. La technique decrite utilise un scintillateur plastique. On exploite le fait que la courbe du nombre d'impulsions mesurees, en fonction du seuil de discrimination, est une droite, pour un emetteur-{beta} pur. Une relation simple entre les caracteristiques de cette droite et l'energie maximum du spectre-{beta} du radionuclide, correspondant, a ete etablie. (auteurs)

  4. Communication Received from the Permanent Mission of the Netherlands regarding Certain Member States' Guidelines for the Export of Nuclear Material, Equipment and Technology; Communication recue de la mission permanente des Pays-Bas concernant les Directives de certains Etats Membres applicables a l'exportation de matieres, d'equipements et de technologie nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-09-05

    The Agency has received a Note Verbale from the Permanent Mission of the Kingdom of the Netherlands, dated 12 July 2011, in which it requests that the Agency circulate to all Member States a letter of 12 July 2011 from the Chairman of the Nuclear Suppliers Group, Ambassador Piet de Klerk, to the Director General, on behalf of the Governments of Argentina, Australia, Austria, Belarus, Belgium, Brazil, Bulgaria, Canada, China, Croatia, Cyprus, Czech Republic, Denmark, Estonia, Finland, France, Germany, Greece, Hungary, Iceland, Ireland, Italy, Japan, Kazakhstan, Republic of Korea, Latvia, Lithuania, Luxembourg, Malta, the Netherlands, New Zealand, Norway, Poland, Portugal, Romania, Russian Federation, Slovakia, Slovenia, South Africa, Spain, Sweden, Switzerland, Turkey, Ukraine, the United Kingdom of Great Britain and Northern Ireland and the United States of America, providing further information on those Governments' Guidelines for Nuclear Transfers [French] L'Agence a recu une note verbale de la mission permanente du Royaume des Pays-Bas, en date du 12 juillet 2011, lui demandant de communiquer a tous les Etats Membres une lettre du 12 juillet 2011 du president du Groupe des fournisseurs nucleaires, l'ambassadeur Piet de Klerk, adressee au Directeur general au nom des gouvernements des Etats suivants : Afrique du Sud, Allemagne, Argentine, Australie, Autriche, Belarus, Belgique, Bresil, Bulgarie, Canada, Chine, Croatie, Chypre, Danemark, Espagne, Estonie, Etats-Unis d'Amerique, Federation de Russie, Finlande, France, Grece, Hongrie, Irlande, Islande, Italie, Japon, Kazakhstan, Lettonie, Lituanie, Luxembourg, Malte, Norvege, Nouvelle-Zelande, Pays-Bas, Pologne, Portugal, Republique de Coree, Republique tcheque, Roumanie, Royaume-Uni de Grande-Bretagne et d'Irlande du Nord, Slovaquie, Slovenie, Suede, Suisse, Turquie et Ukraineb. Cette lettre apporte des informations supplementaires sur les Directives de ces gouvernements applicables aux transferts nucleaires.

  5. Use of ion exchange and early treatment of radioactive contamination in the digestive tract; Utilisation des echangeurs d'ions et traitement precoce de la contamination radioactive par voie digestive

    Energy Technology Data Exchange (ETDEWEB)

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

    1958-07-01

    The efficiency of cation exchange resins for the treatment of digestive contamination with strontium has been studied on rats. The results obtained show that the most efficient resins are those of sulfonic type when administered in the ammonium form. The treatment is still efficient when applied 45 minutes after the ingestion of strontium. In the most favourable cases, the radioactivity of the skeleton was lower by a factor 6 in the treated animals than in controls. This easily applicable, rather safe and non specific treatment deserves to be retained for use. (author) [French] Une etude de l'efficacite des resines echangeuses de cations dans le traitement d'une contamination digestive par le strontium a ete entreprise chez le rat. Les resultats montrent que parmi les resines, les plus efficaces sont celles de type sulfonique, administrees sous forme ammonium. Le traitement est encore efficace 45 minutes apres l'ingestion du strontium. Dans les meilleurs cas, le squelette des rats traites etait six fois moins radioactif que celui des temoins. Ce traitement d'emploi facile, peu dangereux, non specifique, merite d'etre retenu. (auteur)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

    The rapid development of nuclear energy demands an urgent solution to the health problems arising from the discharge into the environment of radioactive residues produced by nuclear installations. - To be able to evaluate the risks run by the population and to fix tolerance limits for waste discharge, it is necessary to possess an exact knowledge of the course taken by the radioelements discharged, from their source until they reach man. The incorporation of radioelements in food cycles is the first risk to take into consideration. The factors involved in all stages of this transmission must be foreseen, whether they concern physical or biological media, because of their continuity and their interdependence. Finally, socio-economic and dietetic data must be collected in order that the risks and tolerance levels estimated are based on concrete and experimental rather than theoretical knowledge. The risk of nuclear accidents in the atomic industry, although very improbable, must be taken into consideration because of the seriousness of their consequences. The health problems arise in the field of professional hygiene on the one hand and in that of public hygiene on the other. In the first field the risk is two-fold and involves irradiation and contamination. The public sphere is reduced essentially to the risk of contamination by radioactive substances accidentally released in the surrounding medium. The health studies to be conducted in this field therefore include research not only on irradiation or contamination therapeutics but also on the transfer of radioelements from the accident site to man, mainly through food cycles, in their physical and in their biological components. Studies of this kind form the basis of decisions in the health field which would have to be taken in the case of an accident. (authors) [French] Le developpement rapide de l'energie nucleaire rend urgente la solution des problemes sanitaires poses par le rejet dans le milieu ambiant des

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-02-15

    contenu de reservoir pour le stocker dans un autre. On a constate une radioactivite dans le terrain entourant les reservoirs defectueux, mais cette radioactivite n'a pas atteint l'eau outerraine. Un cinquieme reservoir a ete mis hors service parce qu'on a constate une deformation du revetement d'acier. A Savannah River, on a construit des citernes d'acier ordinaire dans des caves en beton. Quatre de ces citernes ont presente de petites fissures laterales a la suite d'une corrosion dans les zones a soudures. La faible quantite de dechets qui avait suinte a travers les fissures a ete recuperee dans la cave et remise dans les citernes. Le suintage a maintenant cesse et les reservoirs sont toujours en usage. A Idaho Falls, ce sont des citernes d'acier inoxydable construites dans des caves en beton. Leur utilisation ne s'est heurtee a aucun probleme et on n'a pas constate de defaillance des recipients. Ainsi, la methode courante de stockage des solutions radioactives donne des resultats excellents puisqu'elle empeche que des quantites appreciables de radioactivite ne s'echappent dans le milieu ambiant; mais on continue a penser qu'on pourrait trouver un meilleur procede d'un cout raisonnable pour assurer le stockage de longue duree des matieres radioactives. (author) [Spanish] En un principio, se atendio a la necesidad de confinar en lugar seguro los productos de fision y elementos transurinicos radiactivos construyendo grandes depositos subterraneos. Este sencillo procedimiento sigue aplicandose .en la actualidad, habiendose acumulado mas de 70 milliones de gallones de soluciones radiactivas en unos 200 depositos subterraneos pertenecientes a la Comision de Energia Atomica de los Estados Unidos. Se utilizan depositos de muy diferentes tipos. Esta variedad es consecuencia de la diversidad de las cantidades y composiciones de los desechos que han de almacenarse, de las condiciones ambientales de los diferentes lugares de almacenamiento y de los criterios tecnicos aplicados. Los

  9. Determination of the food consumption in eleven regions of the european community with a view to studying the radioactive contamination level: Methods used. Results of family enquiries; Determination des regimes alimentaires des populations de onze regions de la communaute europeenne en vue de l'etude des niveaux de contamination radioactive: Methodologie. Resultats des enquetes familiales

    Energy Technology Data Exchange (ETDEWEB)

    Cresta, M; Lacourly, G [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1966-07-01

    In the present report are given the results obtained from food surveys carried out during the period 1963-1965 and involving 9000 families living in eleven regions spread out over the six European Community countries. A partial analysis of the results obtained covers a reduced sample of 3725 families; it makes it possible to fix the composition of the mean individual, monthly and annual food consumptions for each of the eleven regions. Details of the organisation of the survey, of the data processing methods and of the method of presenting the results are given in the first part of the report. the second part presents, in numerical table form, the consumption of various foodstuffs and the feeding principles for each region covered by the survey. Tables summarizing the data make it possible to compare the mean individual consumptions in the various regions studied. (author) [French] Dans le present rapport sont rassembles les premiers resultats des enquetes alimentaires effectuees pendant la periode 1963-1965, aupres de 9000 familles, dans onze regions reparties dans les six pays de la Communaute Europeenne. L'exploitation partielle des donnees obtenues porte sur un echantillon reduit a 3725 familles et permet d'etablir la composition du regime alimentaire moyen individuel, mensuel et annuel de chacune des onze regions. L'organisation des enquetes, la methode de traitement des donnees et l'expression des resultats sont exposees dans la premiere partie du rapport. La seconde reunit, sous forme de tableaux numeriques, les consommations des differents aliments et principes alimentaires par region d'enquetes. Des tableaux recapitulatifs permettent, en outre, une comparaison des consommations moyennes, individuelles des differentes regions etudiees. (auteur)

  10. Determination of the food consumption in eleven regions of the european community with a view to studying the radioactive contamination level: Methods used. Results of family enquiries; Determination des regimes alimentaires des populations de onze regions de la communaute europeenne en vue de l'etude des niveaux de contamination radioactive: Methodologie. Resultats des enquetes familiales

    Energy Technology Data Exchange (ETDEWEB)

    Cresta, M.; Lacourly, G. [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1966-07-01

    In the present report are given the results obtained from food surveys carried out during the period 1963-1965 and involving 9000 families living in eleven regions spread out over the six European Community countries. A partial analysis of the results obtained covers a reduced sample of 3725 families; it makes it possible to fix the composition of the mean individual, monthly and annual food consumptions for each of the eleven regions. Details of the organisation of the survey, of the data processing methods and of the method of presenting the results are given in the first part of the report. the second part presents, in numerical table form, the consumption of various foodstuffs and the feeding principles for each region covered by the survey. Tables summarizing the data make it possible to compare the mean individual consumptions in the various regions studied. (author) [French] Dans le present rapport sont rassembles les premiers resultats des enquetes alimentaires effectuees pendant la periode 1963-1965, aupres de 9000 familles, dans onze regions reparties dans les six pays de la Communaute Europeenne. L'exploitation partielle des donnees obtenues porte sur un echantillon reduit a 3725 familles et permet d'etablir la composition du regime alimentaire moyen individuel, mensuel et annuel de chacune des onze regions. L'organisation des enquetes, la methode de traitement des donnees et l'expression des resultats sont exposees dans la premiere partie du rapport. La seconde reunit, sous forme de tableaux numeriques, les consommations des differents aliments et principes alimentaires par region d'enquetes. Des tableaux recapitulatifs permettent, en outre, une comparaison des consommations moyennes, individuelles des differentes regions etudiees. (auteur)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

  13. 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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1968-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-01-15

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

  20. 20 years of interlaboratory tests in the service of radioactivity measurement quality. 20 ans de tests interlaboratoires au service de la qualite des mesures de radioactivite

    Energy Technology Data Exchange (ETDEWEB)

    Cance, M. (CEA Centre d' Etudes de Saclay, 91 - Gif-sur-Yvette (France). Dept. des Applications et de la Metrologie des Rayonnements Ionisants)

    1992-01-01

    In the framework of French national metrological coordination, the Laboratoire de Metrologie des Rayonnements Ionisants (LMRI) organizes since 20 years, each year an interlaboratory test program. The tests concern radioactivity, radio analysis and neutron and gamma dosimetry. In this paper, a review of interlaboratory tests proposed by LMRI is proposed from 1971 to 1991. For the last twenty years, 97 tests have been realized, half in activity measurement, third in radio analysis and 20% in dosimetry. About forty radionuclides (from Tritium to Americium 241) are concerned by these tests with an activity range from 1 Becquerel to 100 megabecquerels. The 120 laboratories having participated at these tests belong essentially to CEA group, EDF or medical sector.

  1. Effet des Plastifiants sur la Temperature de Transition Vitreuse, Tg, du Butadiene a Terminaison Hydroxy et du Polyazoture de Glycidyle - Simulations et Experiences (Effect of the Plasticizers on the Vitreous Transition Temperature, Tg, of the Butadiene to Termination Hydroxy and the Polyazoture of Glycidyle - Simulations and Experiences)

    Science.gov (United States)

    2008-09-01

    Intentionnellement en blanc. DRDC Valcartier TR 2007-615 Executive summary The search of new energetic materials more powerful, less sensitive or more...Resume i Executive summary iii Sommaire iv Table des matieres v Liste des figures vii Listedes tableaux vii Liste des annexes vii Remerciements...plus caoutchouteux absorbe mieux les chocs , ce qui diminue les risques de detonation accidentelle. On choisira un plastifiant en tenant compte

  2. Radio-active pollution near natural uranium-graphite-gas reactors; La pollution radioactive aupres des piles uranium naturel - graphite - gaz

    Energy Technology Data Exchange (ETDEWEB)

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

    1967-07-01

    The results of numerous evaluations of the contamination are given: - Reactors in operation during maintenance operations. - Reactors shut-down during typical repair operations (coolants, exchangers, interior of the vessel, etc. ) - Following incidents on the cooling circuit and can-rupture. They show that, except in particular cases, it is the activation products which dominate. Furthermore, after ten years operation, the points at which contamination liable to emit strong doses accumulates are very localized and the individual protective equipment has not had to be reinforced. (authors) [French] Les resultats de nombreuses evaluations de la contamination sont donnes: - Piles en marche pendant les operations d'entretien - Piles a l'arret au cours des chantiers caracteristiques (refrigerants, echangeurs, interieur du caisson, etc.) - A la suite d'incidents sur le circuit de refroidissement et de rupture de gaine. Ils montrent que, sauf cas particulier, ce sont essentiellement les produits d'activation qui dominent. Par ailleurs apres 10 ans de fonctionnement, les points d'accumulation de la contamination susceptibles de delivrer des debits de dose importants restent tres localises et les moyens de protection individuels utilises n'ont pas du etre renforces. (auteurs)

  3. Radio-active pollution near natural uranium-graphite-gas reactors; La pollution radioactive aupres des piles uranium naturel - graphite - gaz

    Energy Technology Data Exchange (ETDEWEB)

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

    1967-07-01

    The results of numerous evaluations of the contamination are given: - Reactors in operation during maintenance operations. - Reactors shut-down during typical repair operations (coolants, exchangers, interior of the vessel, etc. ) - Following incidents on the cooling circuit and can-rupture. They show that, except in particular cases, it is the activation products which dominate. Furthermore, after ten years operation, the points at which contamination liable to emit strong doses accumulates are very localized and the individual protective equipment has not had to be reinforced. (authors) [French] Les resultats de nombreuses evaluations de la contamination sont donnes: - Piles en marche pendant les operations d'entretien - Piles a l'arret au cours des chantiers caracteristiques (refrigerants, echangeurs, interieur du caisson, etc.) - A la suite d'incidents sur le circuit de refroidissement et de rupture de gaine. Ils montrent que, sauf cas particulier, ce sont essentiellement les produits d'activation qui dominent. Par ailleurs apres 10 ans de fonctionnement, les points d'accumulation de la contamination susceptibles de delivrer des debits de dose importants restent tres localises et les moyens de protection individuels utilises n'ont pas du etre renforces. (auteurs)

  4. 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)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1958-07-01

    The problems dealing with the treatment of the radioactive effluents at the 'Commissariat a l'Energie Atomique' have been studied in order to allow evacuation into a river - after treatment - with respect for the standards regarding radiation protection. 2) At Saclay where there is no possibility of evacuating the effluents, the liquids are directed towards Fontenay-aux-Roses by means of tank wagons. They are removed temporarily into the sewers and will be evacuated later on into the Seine. 3) ln Le Bouchet, the effluents coming from the Factory where urano-thorianite ore is treated will undergo a two stages treatment. The elimination of radium in the first phase facilitates decontamination in the second phase. 4) In Marcoule: a study of synthetic effluents of the Marcoule type is being carried on in order to perfect a selective elimination method of Sr{sup 90} and Cs{sup 137} by coprecipitation. 5) In the general case of the final evacuation into a river, the following problems have been studied: - pre-dilution of treated waters between the storing tanks and the river; - admission in the river; dilution in the river (preliminary study by means of a tracer); - evolution of the activity in the water of the river (adsorption by inert or living elements), contamination of the banks; - locating of the site; - isotopic dilution. 6) Circumstantial study of that last problem. 7) The quantity of a given product in water conditions the isotopic dilution of its radioactive isotopes. When the analysis shows the lack of an element, stable isotopes should be added in order to compensate it. 8) That method led to difficult analysis (specially as far as Sr{sup 90} is concerned), for the percentage of stable isotopes necessary to an important isotopic dilution is very low. 9) The standard regarding the quantity of Sr{sup 90} in drinking water is 8.10{sup -8} c/m{sup 3} or 4.10{sup -10} g/m{sup 3}. So a percentage of 40 {mu}g/litre of Sr is enough which is difficult to find out in

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

  7. Analysis of determination modalities concerning the exposure and emission limits values of chemical and radioactive substances; Analyse des modalites de fixation des valeurs limites d'exposition et d'emission pour les substances chimiques et radioactives

    Energy Technology Data Exchange (ETDEWEB)

    Schieber, C.; Schneider, T

    2002-08-01

    This document presents the generic approach adopted by various organizations for the determination of the public exposure limits values to chemical and radioactive substances and for the determination of limits values of chemical products emissions by some installations. (A.L.B.)

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

    Energy Technology Data Exchange (ETDEWEB)

    Petit, J C

    1993-07-01

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

  9. Building classification trees to explain the radioactive contamination levels of the plants; Construction d'arbres de discrimination pour expliquer les niveaux de contamination radioactive des vegetaux

    Energy Technology Data Exchange (ETDEWEB)

    Briand, B

    2008-04-15

    The objective of this thesis is the development of a method allowing the identification of factors leading to various radioactive contamination levels of the plants. The methodology suggested is based on the use of a radioecological transfer model of the radionuclides through the environment (A.S.T.R.A.L. computer code) and a classification-tree method. Particularly, to avoid the instability problems of classification trees and to preserve the tree structure, a node level stabilizing technique is used. Empirical comparisons are carried out between classification trees built by this method (called R.E.N. method) and those obtained by the C.A.R.T. method. A similarity measure is defined to compare the structure of two classification trees. This measure is used to study the stabilizing performance of the R.E.N. method. The methodology suggested is applied to a simplified contamination scenario. By the results obtained, we can identify the main variables responsible of the various radioactive contamination levels of four leafy-vegetables (lettuce, cabbage, spinach and leek). Some extracted rules from these classification trees can be usable in a post-accidental context. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

  12. Impact de la preparation des anodes crues et des conditions de cuisson sur la fissuration dans des anodes denses

    Science.gov (United States)

    Amrani, Salah

    La fabrication de l'aluminium est realisee dans une cellule d'electrolyse, et cette operation utilise des anodes en carbone. L'evaluation de la qualite de ces anodes reste indispensable avant leur utilisation. La presence des fissures dans les anodes provoque une perturbation du procede l'electrolyse et une diminution de sa performance. Ce projet a ete entrepris pour determiner l'impact des differents parametres de procedes de fabrication des anodes sur la fissuration des anodes denses. Ces parametres incluent ceux de la fabrication des anodes crues, des proprietes des matieres premieres et de la cuisson. Une recherche bibliographique a ete effectuee sur tous les aspects de la fissuration des anodes en carbone pour compiler les travaux anterieurs. Une methodologie detaillee a ete mise au point pour faciliter le deroulement des travaux et atteindre les objectifs vises. La majorite de ce document est reservee pour la discussion des resultats obtenus au laboratoire de l'UQAC et au niveau industriel. Concernant les etudes realisees a l'UQAC, une partie des travaux experimentaux est reservee a la recherche des differents mecanismes de fissuration dans les anodes denses utilisees dans l'industrie d'aluminium. L'approche etait d'abord basee sur la caracterisation qualitative du mecanisme de la fissuration en surface et en profondeur. Puis, une caracterisation quantitative a ete realisee pour la determination de la distribution de la largeur de la fissure sur toute sa longueur, ainsi que le pourcentage de sa surface par rapport a la surface totale de l'echantillon. Cette etude a ete realisee par le biais de la technique d'analyse d'image utilisee pour caracteriser la fissuration d'un echantillon d'anode cuite. L'analyse surfacique et en profondeur de cet echantillon a permis de voir clairement la formation des fissures sur une grande partie de la surface analysee. L'autre partie des travaux est basee sur la caracterisation des defauts dans des echantillons d'anodes crues

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-05-01

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

  14. 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.)

  15. Water/rock interactions and mass transport within a thermal gradient Application to the confinement of high level nuclear waste; Interactions solide/solution et transferts de matiere dans un gradient de temperature. Application au confinement des dechets nucleaires de haute-activite

    Energy Technology Data Exchange (ETDEWEB)

    Poinssot, Ch [CEA Saclay, 91 - Gif-sur-Yvette (France). Dept. d` Entreposage et de Stockage des Dechets; [Ecole Normale Superieure, 92 - Fontenay-aux-Roses (France). Laboratoire de Geologie

    1999-12-31

    The initial stage of a high level nuclear waste disposal will be characterised by a large heat release within the near-field environment of the canisters. This heat flux caused by radioactive decay will lead to an increase of temperature and a subsequent thermal gradient between the `hot` canisters and the `cold`geological medium. In addition, this thermal gradient will decrease with time due to the heat decay although it could last hundred years. What will be the consequences of such a thermal field varying both on space and time for the alteration of the different constituents of the near field environment. In particular, what could be the effects on the radionuclides migration in the accidental case of an early breach of a canister during the thermal stage? This study brings significant answers to these questions in the light of a performance assessment study. This work is supported by a triple methodological approach involving experimental studies, modelling calculations and a natural analogues study. This complete work demonstrates that a thermal gradient leads to a large re-distribution of elements within the system: some elements are incorporated in the solid phases of the hot end (Si, Zr, Ca) whereas some others are in those of the cold end (Fe, Al, Zn). The confrontation of the results of very simple experiments with the results of a model built on equilibrium thermodynamics allow us to evidence the probable mechanisms causing this mass transport: out-of-equilibrium thermodiffusion processes coupled to irreversible precipitation. Moreover, the effects of the variation of temperatures with time is studied by the way of a natural system which underwent a similar temperature evolution as a disposal and which was initially rich in uranium: the Jurassic Alpine bauxites. In addition, part of the initial bauxite escaped this temperature transformations due to their incorporation in outer thrusting nappes. They are used as a reference. (author)

  16. Water/rock interactions and mass transport within a thermal gradient Application to the confinement of high level nuclear waste; Interactions solide/solution et transferts de matiere dans un gradient de temperature. Application au confinement des dechets nucleaires de haute-activite

    Energy Technology Data Exchange (ETDEWEB)

    Poinssot, Ch. [CEA Saclay, 91 - Gif-sur-Yvette (France). Dept. d`Entreposage et de Stockage des Dechets]|[Ecole Normale Superieure, 92 - Fontenay-aux-Roses (France). Laboratoire de Geologie

    1998-12-31

    The initial stage of a high level nuclear waste disposal will be characterised by a large heat release within the near-field environment of the canisters. This heat flux caused by radioactive decay will lead to an increase of temperature and a subsequent thermal gradient between the `hot` canisters and the `cold`geological medium. In addition, this thermal gradient will decrease with time due to the heat decay although it could last hundred years. What will be the consequences of such a thermal field varying both on space and time for the alteration of the different constituents of the near field environment. In particular, what could be the effects on the radionuclides migration in the accidental case of an early breach of a canister during the thermal stage? This study brings significant answers to these questions in the light of a performance assessment study. This work is supported by a triple methodological approach involving experimental studies, modelling calculations and a natural analogues study. This complete work demonstrates that a thermal gradient leads to a large re-distribution of elements within the system: some elements are incorporated in the solid phases of the hot end (Si, Zr, Ca) whereas some others are in those of the cold end (Fe, Al, Zn). The confrontation of the results of very simple experiments with the results of a model built on equilibrium thermodynamics allow us to evidence the probable mechanisms causing this mass transport: out-of-equilibrium thermodiffusion processes coupled to irreversible precipitation. Moreover, the effects of the variation of temperatures with time is studied by the way of a natural system which underwent a similar temperature evolution as a disposal and which was initially rich in uranium: the Jurassic Alpine bauxites. In addition, part of the initial bauxite escaped this temperature transformations due to their incorporation in outer thrusting nappes. They are used as a reference. (author)

  17. Decree no 2007-1557 from November 2, 2007, relative to basic nuclear facilities and to the nuclear safety control of nuclear materials transport; Decret no 2007-1557 du 2 novembre 2007 relatif aux installations nucleaires de base et au controle, en matiere de surete nucleaire, du transport de substances radioactives

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-11-15

    This decree concerns the enforcement of articles 5, 17 and 36 of the law 2006-686 from June 13, 2006, relative to the transparency and safety in the nuclear domain. A consultative commission of basic nuclear facilities is established. The decree presents the general dispositions relative to basic nuclear facilities, the dispositions relative to their creation and operation, to their shutdown and dismantling. It precises the dispositions in the domain of public utility services, administrative procedures and sanctions. It stipulates also the particular dispositions relative to other facilities located in the vicinity of nuclear facilities, relative to the use of pressure systems, and relative to the transport of radioactive materials. (J.S.)

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-01-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

  20. Fast neutron spectrometry and dosimetry; Spectrometrie et dosimetrie des neutrons rapides

    Energy Technology Data Exchange (ETDEWEB)

    Blaize, S; Ailloud, J; Mariani, J; Millot, J P [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    We have studied fast neutron spectrometry and dosimetry through the recoil protons they produce in hydrogenated samples. In spectrometric, we used nuclear emulsions, in dosimetric, we used polyethylene coated with zinc sulphide and placed before a photomultiplier. (author)Fren. [French] Nous avons etudie la spectrometrie et la dosimetrie des neutrons rapides en utilisant les protons de recul qu'ils produisent dans une matiere hydrogenee. En spectrometrie, nous avons employe des emulsions nucleaires, en dosimetrie, du polyethylene recouvert de sulfure de zinc place devant un photomultiplicateur. (auteur)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1968-10-01

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

  4. 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)

  5. Anatomic-physiological schema of the gastrointestinal tract, to be taken in account in determining the levels of radioactive contamination; Schema anatomo-physiologique du tractus gastro-intestinal a prendre en consideration pour le calcul des niveaux de contamination Radioactive

    Energy Technology Data Exchange (ETDEWEB)

    Fabry, C [Commissariat a l' Energie Atomique, Cadarache, Association EURATOM-CEA, Niveaux de Contamination (France). Centre d' Etudes Nucleaires

    1964-07-01

    Anatomical and physiological data of the gastrointestinal tract of adults and children were summarized in a standard schema, to be used in calculating the levels of radioactive contamination, in the food chain. (author) [French] Cette note a pour objet de rassembler les donnees anatomiques et physiologiques du tractus gastrointestinal, chez l'adulte et chez l'enfant, et d'en deduire un schema standard qui puisse servir de base au calcul des niveaux de contamination de la chaine alimentaire par les substances radioactives. (auteur)

  6. Anatomic-physiological schema of the gastrointestinal tract, to be taken in account in determining the levels of radioactive contamination; Schema anatomo-physiologique du tractus gastro-intestinal a prendre en consideration pour le calcul des niveaux de contamination Radioactive

    Energy Technology Data Exchange (ETDEWEB)

    Fabry, C. [Commissariat a l' Energie Atomique, Cadarache, Association EURATOM-CEA, Niveaux de Contamination (France). Centre d' Etudes Nucleaires

    1964-07-01

    Anatomical and physiological data of the gastrointestinal tract of adults and children were summarized in a standard schema, to be used in calculating the levels of radioactive contamination, in the food chain. (author) [French] Cette note a pour objet de rassembler les donnees anatomiques et physiologiques du tractus gastrointestinal, chez l'adulte et chez l'enfant, et d'en deduire un schema standard qui puisse servir de base au calcul des niveaux de contamination de la chaine alimentaire par les substances radioactives. (auteur)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

    The Ottawa River is a very large river. The water has a low solids content with little plankton. In many ways the river resembles a lake. Effluent is diluted, into a great volume of low-activity cooling water and enters the river at a concentration of radionuclides less than the MPCW for occupational workers. The concentration of total B {gamma} radionuclides above the plant is 2 x 10{sup -8} {mu}c/ml, and 1.6 km below the plant it is 3 x 10{sup -8} {mu}c/ml. Sampling of the river bottom shows that its radioactivity has been decreasing for several years in spite of continuous addition of activity adsorbed on colloidal silica deposited from the water. Large fish are the only river organisms used by man. Traces of Sr{sup 90} have occasionally been found in the bones, but none in the flesh. Although P{sup 32} forms only 0.04% of the total radioactivity found in the effluent, it makes up 75-95% of the total radionuclides found in most samples. A maximum concentration of 10{sup -3} {mu}c/g wet weight has been found in the whole bodies of small perch. (author) [French] Ottawa est un tres grand fleuve. Ses eaux ne contiennent que peu' de substances solides, notamment peu de plancton. A bien des egards, ce fleuve ressemble a un lac. Les effluents sont dilues dans. une grande quantite d'eau de refroidissement, de faible activite; lorsqu'ils penetrent dans le fleuve, leur concentration en radionuclides est inferieure a la concentration maximum admissible dans l'eau pour les travailleurs exposes professionnellement. La concentration totale en emetteurs beta et gamma est 2 x 10{sup -8} {mu}c/ml en amont de l'usine et 3 x 10{sup -8} {mu}c/ml a 1,6 km en aval. Les echantillons preleves au fond du fleuve montrent que sa radioactivite diminue depuis plusieurs annees, en depit des apports continuels de l'activite adsorbee par les silices colloiedaux en suspension qui se deposent. Les seuls organismes presents dans le fleuve et utilises par l'homme sont les gros poissons. On a

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-07-01

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

  9. Effets du milieu sur la propagation des neutrinos dans la matiere nucleaire

    CERN Document Server

    Margueron, J

    2001-01-01

    We study the elementary interactions between neutrinos and dense matter in a proroneutron star. Equations of state obtained with different nuclear effective interactions (skyrme, Gogny, relativistic Lagrangians) are first discussed.Then we characterize their stability in spin and isospin. We derive magnetic susceptibilities for all isospin asymmetry values as a function of Landau parameters G^{tau tau'}_0 (where tau, tau' = proton or neutron)We calculate nthe pure neutron matter response functions with and withoutcharge exchange, describing nuclear correlations in both approaches : non-relativistic and relativistic. At the end we calculate neutrino mean free paths for neutral current and charged current reactions.Comparisons between relativistic and non-relativistic approaches allow us to identify relativistic effects in nuclear matter at densities as low as twice the saturation density.RPA correlations make the medium more transparent to neutrinos compared to free Fermi gas.

  10. Elaboration d'une structure de collecte des matieres residuelles selon la Theorie Constructale

    Science.gov (United States)

    Al-Maalouf, George

    Currently, more than 80% of the waste management costs are attributed to the waste collection phase. In order to reduce these costs, one current solution resides in the implementation of waste transfer stations. In these stations, at least 3 collection vehicles transfer their load into a larger hauling truck. This cost reduction is based on the principle of economy of scale applied to the transportation sector. This solution improves the efficiency of the system; nevertheless, it does not optimize it. Recent studies show that the compactor trucks used in the collection phase generate significant economic losses mainly due to the frequent stops and the transportation to transfer stations often far from the collection area. This study suggests the restructuring of the waste collection process by dividing it into two phases: the collection phase, and the transportation to the transfer station phase. To achieve this, a deterministic theory called: "the Constructal Theory" (CT) is used. The results show that starting a certain density threshold, the application of the CT minimizes energy losses in the system. In fact, the collection is optimal if it is done using a combination of low capacity vehicle to collect door to door and transfer their charge into high-capacity trucks. These trucks will then transport their load to the transfer station. To minimize the costs of labor, this study proposes the use of Cybernetic Transport System (CTS) as an automated collection vehicle to collect small amounts of waste. Finally, the optimization method proposed is part of a decentralized approach to the collection and treatment of waste. This allows the implementation of multi-process waste treatment facilities on a territory scale. Keywords: Waste collection, Constructal Theory, Cybernetic Transportation Systems.

  11. Tritium in plants; Le tritium dans la matiere organique des vegetaux

    Energy Technology Data Exchange (ETDEWEB)

    Vichot, L.; Losset, Y. [CEA Valduc, 21 - Is-sur-Tille (France)

    2009-07-01

    The presence of tritium in the environment stems from its natural production by cosmic rays, from the fallout of the nuclear weapon tests between 1953 and 1964, and locally from nuclear industry activities. A part of the tritiated water contained in the foliage of plants is turned into organically bound tritium (OBT) by photosynthesis. The tritium of OBT, that is not exchangeable and then piles up in the plant, can be used as a marker of the past. It has been shown that the quantity of OBT contained in the age-rings of an oak that grew near the CEA center of Valduc was directly correlated with the tritium releases of the center. (A.C.)

  12. The key numbers of the mineral raw materials; Les chiffres cles des matieres premieres minerales

    Energy Technology Data Exchange (ETDEWEB)

    Mandil, C. [Directeur General de l`Energie et des Matieres Premieres, France (France)]|[Ministere de l`Industrie, des Postes et Telecommunications et du Commerce Exterieur, 75 - Paris (France)

    1996-12-31

    Mineral raw materials come from fossil reserves or ores resulting from the geologic and climatic history of the Earth. The access to economic development for 80% of the worldwide population and the high rate of demographic growth (probably 8 billions of inhabitants in 2025) are important factors that can greatly multiply the worldwide consumption of ores. In parallel, environmental concerns and the increasing need for a better equilibrium between wildlife preservation and the supply of economic needs, lead to a more reasonable and mastered use of natural resources. The aim of this book is to shade light and give global elements of thoughts on mineral resources, and for the main of those (about 30 metals and mineral substances), to review the most useful data and references about their production and consumption. For each question, chapters are devoted to the situation of France in its worldwide context. One chapter concerns the uranium ores (reserves, production, prices evolution, consumption, economic flux and companies involved). (J.S.).

  13. Possibility of gas flow measurements using ionization produced by radioactive sources. Performance obtained using continuous and pulsed ionization; Etude des possibilites de mesure des debits gazeux par l'ionisation creee au moyen de sources radioactives performances obtenues par ionisation continue et par ionisation pulsee

    Energy Technology Data Exchange (ETDEWEB)

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

    1969-07-01

    Two methods for measuring gas flow have been studied, based on the ionization of the fluid by a radioactive source. In the first one, called the continuous method, use is made of the relationship between the flow and the ionic density at a point situated down-stream from the ionizing source. In the second method, called 'pulsed', the time for a burst of ions to pass between two points in the circuit is measured. An attempt has been made to predict and to justify theoretically the experimental results, and to determine to what extent these methods can provide absolute measurements or measurements requiring a calibration using known gas flows. These methods are characterized by the absence of moving parts or of parts under reduced pressure and can yield results with an accuracy of between a few per cent to a few tenths of a per cent. The information, provided in either analog or digital form, can be adapted for use in servo-mechanisms or automatic systems. Two applications of an industrial type are described; they concern gas-flow measurements in a railway braking circuit, and in tubes of 20 and 30 cm diameter. (author) [French] Deux methodes de mesure de debit gazeux ont ete etudiees, basees sur l'ionisation du fluide par une source radioactive. Dans la premiere, dite continue, on exploite la relation existant entre le debit et la densite ionique en un point situe a l'aval de la source ionisante. Dans la seconde, dite pulsee, on mesure le temps de transit de bouffees d'ions entre deux points de la conduite. On s'est efforce de prevoir et de justifier par la theorie les resultats experimentaux, et de preciser dans quelle mesure ces methodes peuvent fournir des mesures absolues ou necessitent un etalonnage a partir de debits connus. Caracterisees par l'absence d'organe mobile ou deprimogene, ces methodes sont susceptibles d'une precision de quelques pour-cent a quelques pour-mille. L'information, fournie sous forme

  14. Possibility of gas flow measurements using ionization produced by radioactive sources. Performance obtained using continuous and pulsed ionization; Etude des possibilites de mesure des debits gazeux par l'ionisation creee au moyen de sources radioactives performances obtenues par ionisation continue et par ionisation pulsee

    Energy Technology Data Exchange (ETDEWEB)

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

    1969-07-01

    Two methods for measuring gas flow have been studied, based on the ionization of the fluid by a radioactive source. In the first one, called the continuous method, use is made of the relationship between the flow and the ionic density at a point situated down-stream from the ionizing source. In the second method, called 'pulsed', the time for a burst of ions to pass between two points in the circuit is measured. An attempt has been made to predict and to justify theoretically the experimental results, and to determine to what extent these methods can provide absolute measurements or measurements requiring a calibration using known gas flows. These methods are characterized by the absence of moving parts or of parts under reduced pressure and can yield results with an accuracy of between a few per cent to a few tenths of a per cent. The information, provided in either analog or digital form, can be adapted for use in servo-mechanisms or automatic systems. Two applications of an industrial type are described; they concern gas-flow measurements in a railway braking circuit, and in tubes of 20 and 30 cm diameter. (author) [French] Deux methodes de mesure de debit gazeux ont ete etudiees, basees sur l'ionisation du fluide par une source radioactive. Dans la premiere, dite continue, on exploite la relation existant entre le debit et la densite ionique en un point situe a l'aval de la source ionisante. Dans la seconde, dite pulsee, on mesure le temps de transit de bouffees d'ions entre deux points de la conduite. On s'est efforce de prevoir et de justifier par la theorie les resultats experimentaux, et de preciser dans quelle mesure ces methodes peuvent fournir des mesures absolues ou necessitent un etalonnage a partir de debits connus. Caracterisees par l'absence d'organe mobile ou deprimogene, ces methodes sont susceptibles d'une precision de quelques pour-cent a quelques pour-mille. L'information, fournie sous forme analogique ou numerique, se prete a la realisation de

  15. Some methods for the detection of fissionable matter; Quelques methodes de detection des corps fissiles

    Energy Technology Data Exchange (ETDEWEB)

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

    1967-03-01

    A number of equipments or processes allowing to detect uranium or plutonium in industrial plants, and in particular to measure solution concentrations, are studied here. Each method has its own field of applications and has its own performances, which we have tried to define by calculations and by experiments. The following topics have been treated: {gamma} absorptiometer with an Am source, detection test by neutron multiplication, apparatus for the measurement of the {alpha} activity of a solution, fissionable matter detection by {gamma} emission, fissionable matter detection by neutron emission. (author) [French] On examine ici plusieurs appareils ou procedes qui permettent de detecter l'uranium ou le plutonium dans les installations industrielles, et en particulier de mesurer les concentrations de solutions. Chacune des methodes a son domaine d'application et ses performances, qu'on a tente de definir par le calcul et par des experiences. Les sujets traites sont les suivants: absorptiometre {gamma} a source d'americium, essais de detection par multiplication neutronique, appareil de mesure de l'activite {alpha} d'une solution, detection des matieres fissiles par leur emission {gamma}, detection des matieres fissiles par leur emission neutronique. (auteur)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1966-06-01

    After giving the essential physico-chemical properties of the colloids, the author considers the biological role of these substances and, in connection with their transport by the blood, their capture by elements of the reticula-endothelial system. A summary is given of present knowledge concerning the role of serous proteins in the transport of substances, particularly that of radio-active colloidal gold. The blood fractions which can take part in colloidal gold transport are the red blood corpuscles, the leukocytes and histiocytic elements as well as the plasma. The radioactive distribution in these various fractions is obtained by autoradiography of blood sediments. After showing the importance of the role of the plasma in radioactive particle transport, the author, describes the attempts made to detect a possible of colloidal gold 198 on the various serous proteins using various methods of separation. The ''in vitro'' and ''in vivo'' bonds between colloidal gold-198 particles and either the serous proteins or healthy specimens or the effusion liquids of pathological origin in man, or due to an experimental inflammation with carregenin in the rat, have been studied. The bonding appears to be effective because of the protective macromolecular layer formed by the gelatine. The different positions of the colloidal grains on the electrophoregram can only be explained by their different physico-chemical characteristics. Gold in the ionic form, on the other hand, is combined only with the albumen is the amount metal present does not exceed a certain value. (author) [French] Apres avoir enonce les proprietes physicochimiques essentielles des colloides nous etudions le devenir biologique de ces substances et, en relation avec leur transport par le sang, leur captation par les elements du Systeme Reticulo-Endothelial. Nous resumons les connaissances acquises jusqu'alors sur le role des proteines seriques dans le transport des

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1966-06-01

    After giving the essential physico-chemical properties of the colloids, the author considers the biological role of these substances and, in connection with their transport by the blood, their capture by elements of the reticula-endothelial system. A summary is given of present knowledge concerning the role of serous proteins in the transport of substances, particularly that of radio-active colloidal gold. The blood fractions which can take part in colloidal gold transport are the red blood corpuscles, the leukocytes and histiocytic elements as well as the plasma. The radioactive distribution in these various fractions is obtained by autoradiography of blood sediments. After showing the importance of the role of the plasma in radioactive particle transport, the author, describes the attempts made to detect a possible of colloidal gold 198 on the various serous proteins using various methods of separation. The ''in vitro'' and ''in vivo'' bonds between colloidal gold-198 particles and either the serous proteins or healthy specimens or the effusion liquids of pathological origin in man, or due to an experimental inflammation with carregenin in the rat, have been studied. The bonding appears to be effective because of the protective macromolecular layer formed by the gelatine. The different positions of the colloidal grains on the electrophoregram can only be explained by their different physico-chemical characteristics. Gold in the ionic form, on the other hand, is combined only with the albumen is the amount metal present does not exceed a certain value. (author) [French] Apres avoir enonce les proprietes physicochimiques essentielles des colloides nous etudions le devenir biologique de ces substances et, en relation avec leur transport par le sang, leur captation par les elements du Systeme Reticulo-Endothelial. Nous resumons les connaissances acquises jusqu'alors sur le role des proteines seriques dans le transport des substances et particulierement dans le

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-02-15

    to future programme planning in waste management is discussed. (author) [French] Les difficultes inherentes au stockage en reservoir des dechets de haute activite, telles que le risque de fuite et la necessite du transfert des dechets liquides pendant des periodes extremement longues, ont donne lieu a l'execution aux Etats-Unis d'un vaste programme de recherches et de mises au point qui comporte l'etablissement de systemes pratiques d'elimination definitive de ces matieres. L'auteur decrit le programme de la 'Division de mise au point des reacteurs ' de la Commission de l'energie atomique des Etats-Unis, car il est important pour l'evolution des aspects economiques de l'energie d'origine nucleaire. Il donne un apercu des programmes a long terme de gestion des dechets dans les centres de production de plutonium, a Hanford et a Savannah River, compte tenu des conditions propres a leur situation geographique. L'auteur expose plusieurs methodes de 'conversion en solides 'actuellement a l'etude, dont l'emploi de lits fluidises, de pots chauffes, de colonnes de vaporisation a chaleur rayonnante, de fours a calciner rotatifs et d'eponges en matiSreTceramique. Il examine egalement la methode fondee sur l'addition aux dechets de materiaux vitrifiants en vue d'obtenir un produit plus stable. Il signale divers avantages et inconvenients de chacune de ces methodes. Il fait le point des travaux en cours et expose les plans des futurs programmes. L'auteur decrit les recherches sur certaines formations geologiques; structures salines, profonds bassins permeables et roches cristallines impermeables, pouvant servir au stockage ou a l'elimination definitive de solides calcines ou de divers types de dechets liquides. Il analyse des plans visant a faire une experience dans des structures salines avec des produits de haute activite. Il decrit brievement le programme de forages exploratoires que l'on execute a Savannah River pour determiner s'il est possible d'emmagasiner de vieux dechets

  19. 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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1959-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1968-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1962-01-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2006-02-15

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

  6. 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.)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1962-07-01

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

  8. The exposures to natural radioactivity as a result of human activities; Les expositions a la radioactivite naturelle du fait des activites humaines

    Energy Technology Data Exchange (ETDEWEB)

    Rannou, A.; Dupuis, M.; Bottollier-Depois, J.F.; Leprieur, F.; Pasquier, J.L.; Doremus, P.; Pierre, J.P. [Institut de Radioprotection et de Surete Nucleaire, 92 - Clamart (France); Bernhard, S. [ALGADE, 87 6 Bessines sur Gartempe (France); Delporte, V. [Drection Generale de la Surete Nucleaire et de la Radioprotection, 75 - Paris (France); Servent, J.P. [Institut National de Recherche et de Securite, 75 - Paris (France); Marchand, D. [DRASS Bretagne (France); Dupuis, M.; Bottollier-Depois, J.F.; Leprieur, F.; Pasquier, J.L.; Doremus, P.; Pierre, J.P. [Institut de Radioprotection et de Surete Nucleaire, 92 - Clamart (France); Surbeck, H. [Neuchatel Univ. (Switzerland); Degrange, J.P. [Centre d' Etude sur l' Evaluation de la Protection dans le Domaine Nucleaire, 92 - Fontenay aux Roses (France)

    2005-07-01

    The new regulation in matter of radiation protection, coming from the transposition of the European directive 96/29/EURATOM modifies the code of the public health and the labour code. The exposures to natural radioactivity by the very fact of human activities are the object of specific dispositions. These new dispositions apply to professional areas that were, until now, little concerned by the regulation relative to ionizing radiations. The S.F.R.P., in relationship with the Minister in charge of labour, and the A.F.T.I.M. (French organisation of safety technicians and engineers and labour physicians) organizes two days of information and exchange on the subject. This meeting concerns industry and research departments but also inspectors and labour physicians and other actors having a look on the risk management in societies. After some reminder on radioactivity and its effects, the regulation and the global risk management on working place, several actual examples are presented, covering the different known situations of exposure to the natural radioactivity ( radon, cosmic rays, use of radioactive material in an industrial process, production of radioactive waste). The days finish by a round table conference on the stakes and practical entailment of the new regulation. (N.C.)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

    This paper is presented in three major sections. In the first section the general approach to the overall problem of disposal of radioactive materials into the sea is presented. Those areas where oceanographic knowledge is required are indicated, and a general outline of the status of our present knowledge in these areas is presented. In the second section existing oceanographic knowledge is applied to waste disposal problems, including physical, chemical and biological aspects. It is shown that, on the basis of existing oceanographic knowledge, fairly large amounts (megacuries per year) of packaged wastes can be disposed of into the deep sea without endangering man's safe uses of the sea. Low-level packaged wastes of the order of several hundred curies per year per disposal site could be safely disposed of on the continental shelf. Discharge of several hundred curies with the spent ion-exchange beds from nuclear-powered ships can be made into surface layers of the open sea without undue risk. The special aspects of near-shore and estuarine environments with respect to nuclear ship operation are discussed. In the third section of the paper a brief discussion is given of some of the oceanographic research activities now under way in the United States applicable to the radioactive waste disposal problem. (author) [French] Ce memoire comprend trois parties principales. Dans la premiere, l'auteur expose la maniere dont on envisage le probleme general de l'elimination de matieres radioactives dans la mer. Il precise les domaines dans lesquels des connaissances oceanographiques sont indispensables et il expose, d'une facon generale, le niveau actuel de notre science en cette matiere. Dans la deuxieme partie, les connaissances oceanographiques actuelles sont appliquees aux problemes d'elimination des dechets, notamment aux aspects physiques, chimiques et biologiques. L'auteur montre que, selon les connaissances oceanographiques actuelles, on peut eliminer en haute mer des

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2011-07-15

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

  11. Estimation of the collective sanitary impact of the land contamination by the radioactivity found at Gif sur Yvette; Estimation de l'impact sanitaire collectif de la contamination des terrains par la radioactivite presente a Gif sur Yvette

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-06-01

    The company 'Societe Nouvelle du Radium' extracted radium and produced radium needles in Gif-sur-Yvette (Essonne) from 1904 to 1957. In 1959, this site was converted into a habitable zone. Since then, this district called the 'Petite Coudraie' has been going through several radioactivity measurements and decontamination works. In 2000, the detection of very high levels of radon above sanitary recommendations in one house encouraged the local authorities to launch a systematic investigation and risk analysis in order to take the necessary measures against radiological risks for the whole concerned district. The 'Direction Departementale des Affaires Sanitaires et Sociales' (D.D.A.S.S.), the French Institute of Public Health (InVS) and the Institute of Nuclear Protection and Security (I.P.S.N.) conducted a health impact assessment of the pollution in this area. The Office for the Protection against Ionizing Radiations (O.P.R.I.) and the I.P.S.N. first measured the radioactivity found on the surface area. The I.P.S.N. then conducted a dosimetric study based on the measurement results and realistic exposure scenarios of adults and children present in the area. Finally, on the base of these results, the InVs did a quantitative risk assessment of cancer due to exposure to the radioactive residuals from the past industrial activities which is the subject of this report. This assessment allows to estimate the extent of this potential health impact due to the contamination of the area with the current scientific knowledge. It assesses the contribution of the various sources ways of exposure to risk and therefore directs the measures of management priority. Finally, it also allows to appreciate the relevance of an epidemiological study on the population who was present in this area. (author)

  12. Communications Received from Certain Member States Regarding Guidelines for Transfers of Nuclear-related Dual-use Equipment, Materials, Software and Related Technology; Communications recues de certains Etats Membres concernant les directives applicables aux transferts d'equipements, de matieres et de logiciels a double usage dans le domaine nucleaire, ainsi que de technologies connexes

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-04-10

    The Director General of the International Atomic Energy Agency has received Notes Verbales, dated 1 December 2005, from the Resident Representatives to the Agency of Argentina, Australia, Austria, Belarus, Belgium, Brazil, Bulgaria, Canada, Croatia, Czech Republic, Estonia, Finland, France, Germany, Greece, Hungary, Ireland, Italy, Japan, Republic of Korea, Latvia, Lithuania, Luxembourg, Malta, the Netherlands, New Zealand, Poland, Portugal, Slovenia, South Africa, Spain, Sweden, Switzerland, Turkey, Ukraine, the United Kingdom of Great Britain and Northern Ireland and the United States of America, relating to transfers of nuclear-related dual-use equipment, materials, software and related technology [French] Le Directeur general de l'Agence internationale de l'energie atomique a recu des notes verbales datees du 1er decembre 2006 des representants permanents aupres de l'Agence des Etats suivants : Afrique du Sud, Allemagne, Argentine, Australie, Autriche, Belarus, Belgique, Bresil, Bulgarie, Canada, Croatie, Espagne, Estonie, Etats-Unis d'Amerique, Finlande, France, Grece, Hongrie, Irlande, Italie, Japon, Lettonie, Lituanie, Luxembourg, Malte, Nouvelle-Zelande, Pays-Bas, Pologne, Portugal, Republique de Coree, Republique tcheque, Royaume-Uni de Grande-Bretagne et d'Irlande du Nord, Slovenie, Suede, Suisse, Turquie et Ukraine, au sujet des transferts d'equipements, de matieres et de logiciels e double usage dans le domaine nucleaire, ainsi que de technologies connexes.

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Gensdarmes, F

    2000-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Le Dars, A

    2002-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-08-15

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

  17. SGSreco. A method for accurate and reliable determination of the radioactive inventory in radioactive waste barrels; SGSreco. Eine Methode zur genauen und verlaesslichen Bestimmung des Aktivitaetsinventares in radioaktiven Abfallfaessern

    Energy Technology Data Exchange (ETDEWEB)

    Krings, Thomas; Mauerhofer, Eric [Forschungszentrum Juelich GmbH (Germany). Inst. fuer Energie und Klimaforschung (IEK), Nukleare Entsorgung und Reaktorsicherheit (IEK-6)

    2013-07-01

    The computer code SGSreco is used for the evaluation of counting rate distributions from SGS (segmented gamma scan) measurements on radioactive waste barrels. The code is based on data fitting to a physical model function; the results include position parameters, point source activities and the activity of a homogeneous activity distribution. A simulation study has shown that the point source activity can be determined with 2% accuracy. Conventional methods are based on the assumption of a homogeneous activity distribution which is wrong for about 75% of the radioactive waste barrels, the determined nuclide specific activities have significant error rates. The use of SGSreco improves the accuracy and reliability of activity determinations and reduces the conservatism of activity estimations. The latter one allows an optimal utilization of the repository capacity with respect to the maximum activities at the end of the operational phase of the repository Konrad.

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

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

  19. Some properties of matter at very HTGH temperatures and high pressures (equations of state, opacity); Quelques proprietes de la matiere aux tres hautes temperatures et fortes pressions (equation d'etat, opacite)

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-06-15

    studying the influence of compressions on the band structure. (author) [French] Les equations de Thomas-Fermi, apparues comme approximation d'ordre zero des equations d'Hartree-Fock permettent d'etudier certains comportements de la matiere a haute pression. Dans un premier chapitre nous envisageons le calcul de grandeurs ne necessitant pas la resolution de l'equation de SCHOEDINGER. La grandeur des corrections quantiques et d'echange definissent le domaine de validite de la theorie. Pour chaque couple R et T, on peut calculer la pression et l'energie, pans le calcul de cette derniere, nous ayons du, dans la region voisine du noyau ou les-corrections divergent, remplacer la densite donnee par la theorie de Thomas-Fermi par celle deduite des fonctions d'onde qui, dans cette petite region, different tres peu de celle d'un atome d'hydrogene de charge z. Le calcul du degre d'ionisation est particulierement simple et evite la resolution des equations de SAHA. En plus de la repartition des electrons dans l'espace des r on peut aisement determiner la repartition suivant la valeur du nombre quantique I, et ce, pour chaque valeur du couple R, T. Dans le second chapitre, l'introduction du potentiel de Thomas et Fermi dans l'equation de SCHROEDINGER permet d'obtenir le spectre des energies propres d'un atome isole modele, sense representer un atome moyen de la matiere chaude et comprimee. La variation des niveaux avec la pression et la temperature s'en deduit. L'interpretation du phenomene d'ionisation par pression est particulierement simple dans ce modele. La variation des niveaux avec la pression et la temperature s'en deduit. L'interpretation du phenomene d'ionisation par pression est particulierement simple dans ce modele. La connaissance des fonctions d'onde permet le calcul des probabilites de transition,lesquelles, couplees avec les probabilites d ccupation autorisent le calcul des coefficients d'opacite. Seules les transitions lie-libre et libre-libre ont ete envisagees, mais

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

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

  1. 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.)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1958-07-01

    The problems dealing with the treatment of the radioactive effluents at the 'Commissariat a l'Energie Atomique' have been studied in order to allow evacuation into a river - after treatment - with respect for the standards regarding radiation protection. 2) At Saclay where there is no possibility of evacuating the effluents, the liquids are directed towards Fontenay-aux-Roses by means of tank wagons. They are removed temporarily into the sewers and will be evacuated later on into the Seine. 3) ln Le Bouchet, the effluents coming from the Factory where urano-thorianite ore is treated will undergo a two stages treatment. The elimination of radium in the first phase facilitates decontamination in the second phase. 4) In Marcoule: a study of synthetic effluents of the Marcoule type is being carried on in order to perfect a selective elimination method of Sr{sup 90} and Cs{sup 137} by coprecipitation. 5) In the general case of the final evacuation into a river, the following problems have been studied: - pre-dilution of treated waters between the storing tanks and the river; - admission in the river; dilution in the river (preliminary study by means of a tracer); - evolution of the activity in the water of the river (adsorption by inert or living elements), contamination of the banks; - locating of the site; - isotopic dilution. 6) Circumstantial study of that last problem. 7) The quantity of a given product in water conditions the isotopic dilution of its radioactive isotopes. When the analysis shows the lack of an element, stable isotopes should be added in order to compensate it. 8) That method led to difficult analysis (specially as far as Sr{sup 90} is concerned), for the percentage of stable isotopes necessary to an important isotopic dilution is very low. 9) The standard regarding the quantity of Sr{sup 90} in drinking water is 8.10{sup -8} c/m{sup 3} or 4.10{sup -10} g/m{sup 3}. So a percentage of 40 {mu}g/litre of Sr is enough which is difficult

  3. Economic Aspects of Air and Gas Cleaning for Nuclear Energy Processes; Aspects Economiques de l'Epuration de l'Air et des Gaz au Cours des Operations Nucleaires; 042d 041a 041e 041d 041e 0414 0; Aspectos Economicos de la Depuracion del Aire y de los Gases en los Procesos de Obtencion de Energia Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Silverman, Leslie [Harvard School of Public Health, Boston, MA (United States)

    1960-07-01

    In this paper the basic requirements for control of gaseous and particulate effluents are given as applied to problems of feed material production, isotope separation, fuel element fabrication, fuel recovery and reactor operation. There are also instances where non-radioactive nuclear materials with toxic or nuisance effluents such as from beryllium and zirconium production are of concern and these too must be controlled at reasonable costs. The factors involved in capital and operating costs of gas cleaning equipment and the types of applications in the United States are described in some detail. Gaseous effluent problems have, of course, been attacked and controlled by several types of device but their performance has been measured on a comparable basis. It is thus possible to judge operating characteristics on an economic basis as related to power consumption, adsorbent costs, space charges, corrosion problems and other operational factors. The United States Atomic Energy Commission through its contract with the Harvard University Air Cleaning Laboratory has initiated an evaluation program with cooperation, from the various facilities and contractors to the Commission. In this study the basic factors necessary to obtain quantitative cost delineation and evaluation have been outlined and some preliminary findings will be presented. The paper also presents a review of other economic studies made in the United States on particular process or facility applications. (author) [French] Le memoire definit les regles fondamentales auxquelles doit obeir le controle des effluents gazeux et particulaires dans les domaines suivants : production des matieres destinees a alimenter les reacteurs, separation des isotopes, fabrication des cartouches de combustible, recuperation du combustible et fonctionnement des reacteurs. De plus - et c'est notamment ce qui se passe avec la production de beryllium et de zirconium -- il y a des cas ou des matieres nucleaires non radioactives

  4. Detection of fission fragments by secondary emission; Detection des fragments de fission par emission secondaire

    Energy Technology Data Exchange (ETDEWEB)

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

    1965-07-01

    This fission fragment detecting apparatus is based on the principle that fragments traversing a thin foil will cause emission of secondary electrons. These electrons are then accelerated (10 kV) and directly detected by means of a plastic scintillator and associated photomultiplier. Some of the advantages of such a detector are, its rapidity, its discriminating power between alpha particles and fission fragments, its small energy loss in detecting the fragments and the relatively great amount of fissionable material which it can contain. This paper is subdivided as follows: a) theoretical considerations b) constructional details of apparatus and some experimental details and c) a study of the secondary emission effect itself. (author) [French] Le detecteur de fragments de fission que nous avons realise est base sur le principe de l'emission secondaire produite par les fragments de fission traversant une feuille mince: les electrons secondaires emis sont acceleres a des tensions telles (de l'ordre de 10 kV), qu'ils soient directement detectables par un scintillateur plastique associe a un photomultiplicateur. L'interet d'un tel detecteur reside: dans sa rapidite, sa tres bonne discrimination alpha, fission, la possibilite de detecter les fragments de fission avec une perte d'energie pouvant rester relativement faible, et la possibilite d'introduire des quantites de matiere fissile plus importantes que dans les autres types de detecteurs. Ce travail comporte: -) un apercu bibliographique de la theorie du phenomene, -) realisation et mise au point du detecteur avec etude experimentale de quelques parametres intervenant dans l'emission secondaire, -) etude de l'emission secondaire (sur la face d'emergence des fragments de fission) en fonction de l'energie du fragment et en fonction de l'epaisseur de matiere traversee avant emission secondaire, et -) une etude comparative de l'emission secondaire sur la face d'incidence et sur la face d'emergence des fragments de

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-05-15

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

  6. 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).

  7. The Use of Short-Lived Radioactive Isotopes in an Activation Analysis Service Programme; Emploi des Radioisotopes a Courte Periode dans un Service d'Analyses par Activation; ИСПОЛЬЗОВАНИЕ КОРОТКОЖИВУПИХ РАДИОАКТИВНЫХ ИЗОТОПОВ В ПРОГРАММЕ АКТИВАЦИОННОГО АНАЛИЗА; Empleo de Radioisotopos de Periodo Corto en los Servicios de Analisis por Activacion

    Energy Technology Data Exchange (ETDEWEB)

    Gibbons, D.; Simpson, H. [Wantage Research Laboratory, Wantage (United Kingdom)

    1963-03-15

    also give an improved sensitivity. Several types of automatic units for use in counting short-lived radioisotopes are described, including photographic recording techniques, an automation sample changer and various programming units. (author) [French] Les radioisotopes a courte periode, notamment ceux dont la periode est egale ou inferieure a une heure, presentent divers avantages lorsqu'ils sont utilises pour l'analyse par activation. Parmi ces avantages on peut citer les suivants: sensibilite et selectivite (dans certains cas) plus favorables; temps de traitement total plus court, d'ou resultats plus rapides et souvent a meilleur compte; enfin, pour les analyses non destructives, possibilite de reactivation pour de nouvelles mesures. On surmonte progressivement les difficultes inherentes a des periodes aussi comtes. On a mis au point des methodes de separation radiochimique rapide telles que le traitement peut etre effectue sans qu'il se produise une desintegration radioactive excessive. L'emploi de spectrometres gamma perfectionnes et de methodes modernes de traitement des donnees a elargi le champ des analyses non destructives, reduisant ainsi la necessite de proceder a des purifications radiochimiques. Les auteurs illustrent les applications des radioisotopes a courte periode aux analyses par activation en decrivant les problemes d'analyse qu'ils ont eu effectivement a resoudre dans leur service d'analyse par activation. C'est ainsi que si l'on veut determiner la quantite de rubidium presente dans des sels de cesium, l'emploi de {sup 86m}Rb, dont la periode est de 1,0 min, reduit considerablement l'accumulation de l'activite matricielle pour une perte de sensibilite faible. Pour determiner le calcium present dans le tissu, c'est le {sup 49}Ca, dont la periode est de 8,8 min, qui donne les resultats le plus rapidement etant donne que la duree de l'irradiation est tres reduite et qu'en moins d'une heure on peut suivre la courbe de desintegration pour un nombre

  8. Calculation of the working capital invested in fuel cycles and its interest charges (1963); Calcul des immobilisations financieres des cycles de combustible (1963)

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-07-01

    All the processes undergone by the nuclear material, including the various steps of fuel element manufacturing and of irradiated fuel reprocessing lead to working capital investments varying with the type of reactor, that must be taken into account in the kWh cost calculation. The author deals with a calculation method called: 'present worth method' and gives some examples concerning reactors the main fuel of which being either natural uranium or enriched uranium or plutonium. He especially points out the importance these investments may take in the case of fast breeder reactors. (author) [French] L'ensemble des etapes parcourues par la matiere fissile comprenant les divers stades d'elaboration des elements combustibles et de leur traitement apres irradiation, implique des immobilisations financieres tres differentes d'un type de reacteur a l'autre, dont il convient de tenir compte dans le calcul du cout du kWh. L'auteur expose une methode de calcul dite 'd'actualisation des couts' et donne quelques exemples relatifs aux reacteurs utilisant l'uranium naturel, l'uranium enrichi et le plutonium comme combustible principal. Il montre en particulier l'importance que peuvent avoir ces immobilisations dans le cas des reacteurs surregenerateurs. (auteur)

  9. Low Radioactivities Center. Report presented to the Scientific Committee, July 19, 1994; Centre des Faibles Radioactivites. Rapport presente au Comite Scientifique, 19 juillet 1994

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-07-01

    This document is the annual report of the Low Radioactivities Center for the year 1994. The Center is a joint CEA-CNRS laboratory devoted to biogeochemical, climate and Earth science studies. It has developed refined methods for the measurement of small amounts of stable and radioactive isotopes (lead, thorium, cesium, radium, radon, polonium, potassium, argon, beryllium, carbon, oxygen, helium..), in particular isotope dating methods such as K/Ar and C14 methods. The research activities are regrouped in four topics: the study and modelling of great biogeochemical cycles (troposphere physico-chemistry, carbon cycle, mass transfers between atmosphere, ocean and sediments); the evolution of climate (thermohaline circulation and heat transfers); the interactions between the internal activity of the Earth and the Earth`s surface (magnetic field instabilities, oceanic volcanism, geodynamics of orogenic domains, active volcanism); the outstanding events of the Earth`s history (Cretaceous-Tertiary boundary, cosmic phenomena, Quaternary evolution of the fossil man and of its environment). A complete list of the laboratory publications is given in the appendix together with a listing of the other activities (teaching, external collaborations, oceanic campaigns, seminars..). (J.S.). 659 refs., 39 figs., 1 tab., 3 photos., 4 appends.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

  12. Assessment of radioactivity controls performed by the IRSN on enamels pigmented by uranium and recommendations related to the use of radiation meters by the public; Bilan des controles de radioactivite effectues par l'IRSN sur des emaux pigmentes par de l'uranium et recommandations relatives a l'emploi de radiametres par des personnes du public

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-09-15

    This information note reports the results of measurements performed by the IRSN on enamel pictures possessed by a Limoges inhabitant who bought a radiometer and measured an unusually high radioactivity level due to the presence of uranium-based yellow pigments. The performed measurements are described and the results are discussed in terms of radioactivity level and of radionuclide identification

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-06-01

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

  14. The other side of utilization. Unwanted radioactivity in wastes and scrap metal; Die andere Seite des Gebrauchs. Ungewollte Radioaktivitaet in Abfaellen und Altmetallen

    Energy Technology Data Exchange (ETDEWEB)

    Schulze, Robert [Nuclear Control and Consulting GmbH, Niederzier (Germany); Gellermann, Rainer [Nuclear Control and Consulting GmbH, Braunschweig (Germany)

    2017-04-01

    Natural radionuclides in industrial wastes and mining residues cannot be neglected in the frame of radiation protection and are therefore part of the radiation protection system in the sense of the IAEA definition. In case of purposely added uranium or thorium or utilization of ionizing radiation these products are also part of the radiation protection system since 2001. The historically grown radiation protection system is incomplete with respect to radiation sources, contaminated objects or materials with enriched natural radioactivity. These materials are detected by radiation monitoring systems that are targeted to find lost technical radiation sources. Experiences with the survey of respective incidents show the multifaceted image of utilization and consumption if natural radionuclide containing products.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2004-07-01

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

  16. Variation of the material laplacian of G1 with the radius of the uranium bar; Variation du laplacien matiere de G1 avec le rayon du barreau d'uranium

    Energy Technology Data Exchange (ETDEWEB)

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

    1957-07-01

    In this report are described and interpreted some experiments, carried out in the pile G1 during a period of shut-down, which have made it possible to measure the variation of the material Laplacian of the lattice with the radius of the uranium bar. The variation of the reactivity of the pile is measured when an increasing number of fuel elements are progressively replaced in the central region by fuel elements of greater diameter; it is shown that, starting from measurements based on less than ten per cent of the total number of elements, the variation of reactivity corresponding to the replacement of all the elements can be determined; it is then easy to deduce the variations of the Laplacian. Results: the variations of the Laplacian with the uranium rod diameter are 0 (d. 26 mm), +0.065 {+-} 0.004 m{sup -2} (d. 28 mm) and +0.080 {+-} 0.008 m{sup -2} (d. 32 mm). (author) [French] Dans ce rapport sont decrites et interpretees des experiences realisees sur la pile G1 'froide', experiences qui ont permis de mesurer la variation du Laplacien matiere du reseau avec le rayon du barreau d'uranium. On mesure la variation de reactivite de la pile lorsqu'on remplace progressivement dans la region centrale un nombre croissant de cartouches par des cartouches de plus gros diametre; on montre qu'a partir de mesures portant sur moins de dix pour cent du nombre total de cartouches, on peut determiner la variation de reactivite qui correspondrait au remplacement de toutes les cartouches; il est facile d'en deduire les variations du Laplacien. Resultats: les variations du Laplacien en fonction du diametre du barreau d'uranium sont: 0 (d. 26 mm), +0.065 {+-} 0.004 m{sup -2} (d. 28 mm) and +0.080 {+-} 0.008 m{sup -2} (d. 32 mm). (auteur)

  17. Transportation of radioactive elements

    International Nuclear Information System (INIS)

    Thubert, Francis; Rentien, Guy; Jacquet, Michel

    1981-01-01

    The production and marketing of artificial radioactive elements engaged in by the 'Office des Rayonnements Ionisants' requires the use of specially designed packagings and assorted means of transport. The authors begin by describing the different kinds of products involved and the forms of packagings needed, and go on to discuss the various means of transport used, underlining the fact that, in terms of number and gravity, the incidents that have occurred to date have indeed been few and far between [fr

  18. Environmental radioactivity in Germany. Report of the federal installations and the Federal office of radiation protection. Data and evaluation; Umweltradioaktivitaet in der Bundesrepublik Deutschland. Bericht der Leitstellen des Bundes und des Bundesamtes fuer Strahlenschutz. Stand 2014. Daten und Bewertung

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2015-04-15

    This report is a compilation and evaluation of data on radioactivity in the environment and in the vicinity of nuclear facilities in Germany from 2011 to 2013. The mean radiation exposure of the public in Germany was about 4.0 mSv in 2013, of which natural radiation exposure accounted for about 2.1 mSv and man-made radiation exposure for 1.9 mSv. An international work group is in charge of the preparation of quality standards for radon measurements. These latter also serve as a basis to implement the regulations of the new EURATOM Basic Safety Standards Directive. Rice grown within the contaminated zone around Fukushima has been certified as reference material for food monitoring. The trace analysis laboratory for airborne radioactive substances obtained several striking results of measurements performed during the reporting period. Man-made radionuclides from the Fukushima nuclear accident were detectable, too. Assessment of anthropogenic radioactivity also requires thorough measurement of ''natural'' radiation components. Three different measurement areas are used as a reference for calibration. Discharges of radioactive substances into the exit air and wastewaters from nuclear power plants remained far below the authorised limit from 2011 to 2013. There has been a trend of decreasing discharges since 1975. The nine nuclear power plant units in operation at the end of the reporting period had a total capacity of 12.7 GW and accounted for 15 per cent of power generation. The annual mean values provided by the measuring network of the Deutscher Wetterdienst (DWD; German Meteorological Service) amounted to 0.6 mBq/m{sup 3}, 0.7 mBq/m{sup 3} and 0.7 mBq/m{sup 3} for the total -activity in the air and 58 Bq/m{sup 2}, 38 Bq/m{sup 2}, and 27 Bq/m{sup 2} for the total -activity deposited by precipitation in 2011, 2012 and 2013, respectively. The higher annual value for 2011 is due to the Fukushima releases. The activity concentrations of {sup 85}Kr

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

    Energy Technology Data Exchange (ETDEWEB)

    Perronnet, M

    2004-10-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Pellegrino, St

    2004-03-01

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

  1. Propagation of neutrinos in nuclear matter; Effets du milieu sur la propagation des neutrinos dans la matiere nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Margueron, J

    2001-07-01

    We study the elementary interactions between neutrinos and dense matter in a proto-neutron star. Equations of state obtained with different nuclear effective interactions (Skyrme, Gogny, Relativistic Lagrangians) are first discussed. Then, we characterize their stability in spin and isospin. We derive magnetic susceptibilities for all isospin asymmetry values as a function of Landau parameters G{sup {pi}}{sup {pi}}{sup '}{sub 0} (where {pi}, {pi}' = proton or neutron). From this work, we select a parametrization for each of the 3 effective forces: Sly230b,D1P,NL3. We calculate the pure neutron matter and asymmetric nuclear matter response functions with and without charge exchange, describing nuclear correlations in both approaches: non-relativistic (Hartree-Fock with Skyrme forces, then complete RPA) and relativistic (in the Hartree approximation). At the end, we calculate neutrino mean free paths neutral current and charged current reactions. Comparisons between relativistic and non-relativistic approaches allow us to identify relativistic effects in nuclear matter at densities as low as twice the saturation density. RPA correlations make the medium more transparent to neutrinos compared to free Fermi gas. The importance of the effective mass in mean free path calculations is also shown. (author)

  2. Semi-classical theory of fluctuations in nuclear matter; Theorie semi-classique des fluctuations dans la matiere nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Benhassine, B. [Nantes Univ., 44 (France)

    1994-01-14

    At intermediate energies the heavy ion collisions can be studied within the framework of a semi-classical approach based on the Vlasov-Uehling-Uhlenbeck (VUU) equation. Such an approach reduces the N-body problem to its description in terms of the one-body distribution function and constitutes the basis of several successful simulation models. Our aim in this work is to extend these average approaches to treat fluctuations. Within the framework of a linear approximation, we derived a Fokker-Planck transport equation in the one-body phase space. When it is reduced to its first moments, one recovers the VUU equation for the average dynamics together with the time evolution equation for the correlations. The collective transport coefficients are then obtained by projection on the one-body collective space. Independently, using a projection method introduced by Van Kampen, based on the constants of motion, we deduce the stationary expressions for the covariance matrix in phase space. We extract then, the equilibrium dispersions of one-body observables in a homogeneous case and in a spherical symmetric one. These results are compared with two types of simulation models in a relaxation time approximation. In the first one which is of Lagrangian type, the collective transport coefficients are directly extracted from the simulation and consequently the numerical fluctuations are washed out. The second model, due to its Eulerian character, allows us to make a microscopical comparison. (author) 58 refs.

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

    Energy Technology Data Exchange (ETDEWEB)

    Guedon, V.; Siclet, F.

    1995-03-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

    Generally the volumes of low- and intermediate-level radioactive wastes produced at chemical processing sites are so great as to make permanent storage prohibitively costly. In many instances chemical treatment may provide sufficient decontamination to allow the discharge of these effluents to surface streams or estuaries. However, in some circumstances such methods are costly and either do not make possible adequate decontamination, or result in excessively large volumes of semi-solid wastes that must be permanently stored. It is believed that in such a situation the deep underlying formations of the earth may constitute a safe and economic waste-disposal resource. In sandstone formations large volumes of waste may be stored with a high degree of containment integrity. Both the interstitial voids and ion-exchange properties serve to make available a great storage capacity. The disposal system employing deep formations of the earth is conceived to consist of a pattern of injection wells for introducing the waste, and of relief wells which serve to reduce well-head pressures, permit monitoring, and direct the flow in such a manner as to make maximum use of the formation. Information needed for the design of such a system includes data on the dispersion or short-circuiting properties of the formations, ion-exchange characteristics of the media, and the chemical and radiochemical properties of the waste. A two-well prototype injection system has been in operation for two years at the Engineering Field Station of the University of California. (author) [French] En general, les dechets de faible ou moyenne activite produits dans les usines de traitement chimique atteignent un volume tel que le cout de leur entreposage permanent est prohibitif. Dans plusieurs cas, un traitement chimique peut produire une decontamination suffisante pour que ces effluents puissent etre jetes dans des cours d'eau et des estuaires. Dans certaines circonstances, cependant, ces methodes sont

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

    The composition of nuclear power wastes is determined, firstly, by the treatment employed for fuel reprocessing, and secondly, by the initial fuel composition. In solvent-extraction processing, wastes of high, intermediate and low activity are produced in approximate volumetric ratios of one, five and 100, respectively. The wastes resulting from reprocessing of highly enriched fuels are large in volume because they contain the fuel diluent. Low-enrichment fuels usually consist of a uranium core clad with aluminium, zirconium or stainless steel, and they produce two waste streams: one, an intermediate-activity waste containing about 0.1% of the fission products, results from the chemical dissolution ; the other is a high-activity waste containing the remainder of the fission products in a dilute nitric acid solution. The volume of evaporated waste varies from 0.8 1/kg of uranium for low- enrichment fuels to 500 1/kg of uranium for highly-enriched fuels. The average volume of combined high- and intermediate-level waste from the anticipated United States nuclear power industry is about five 1/kg of uranium. In the United States it is estimated that the nuclear power industry will have produced about 3,000 million curies of radioactivity in 27 million litres of solution by 1970, and 60,000 million curies in 1,100 million litres of solution by 2000. Power reactor, wastes present new storage and disposal problems because of their composition. (author) [French] La composition des dechets nucleaires est determinee, d'abord, par le procede employe pour le traitement du combustible et, ensuite, par la composition du combustible lui-meme. Le procede de l'extraction par solvants produit des dechets ayant une activite elevee, moyenne ou faible dans des proportions volumetriques d'environ 1,5 et 100 respectivement. Les dechets provenant du traitement des combustibles fortement enrichis, representent un volume important parce qu'ils contiennent le diluant du combustible. Les

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

  8. Les reseaux de politique publique comme facteur d'influence du choix des instruments de politique energetique canadienne a des fins environnementales de 1993 a nos jours

    Science.gov (United States)

    Fathy El Dessouky, Naglaa

    Au cours de la derniere decennie, les modes de la gouvernance ont pris place dans un contexte totalement different de celui qu'ils avaient auparavant. Les gouvernements modernes se rendent compte qu'ils perdent de plus en plus leur capacite a elaborer et a gerer les changements d'une maniere autonome. Ainsi, les fonctions et les activites traditionnellement accomplies exclusivement par le gouvernement engagent de nos jours une gamme d'acteurs etatiques et non etatiques. A l'encontre du concept traditionnel de l'Etat controleur, la gouvernance contemporaine est ainsi devenue moins une question d'offre de service et davantage une gestion indirecte des reseaux de politique publique. Dans cette entreprise, les gouvernements contemporains, cherchant plus d'information, de soutien et de legitimite en matiere de formulation des decisions, ont besoin d'etablir des relations avec les divers groupes d'interet qui, a leur tour, voulaient plus de promotion et de protection en faveur de leurs interets a travers leur implication au processus de l'elaboration et de la mise en oeuvre des politiques publiques. Ainsi, l'approche des reseaux de politique publique represente aujourd'hui un courant considerable au sein du champ d'analyse des politiques publiques. Toutefois, les preoccupations des chercheurs pour cette approche, dans le domaine des politiques energetiques a des fins environnementales, semblent recentes, et les etudes realisees sont encore trop peu nombreuses. Au Canada, au debut des annees 1990, le gouvernement ainsi que plusieurs groupes d'interets, des differents secteurs energetique, industriel et environnemental, ont commence a intensifier leurs efforts pour s'attaquer au probleme du changement climatique d'origine energetique, genere surtout par le secteur de l'industrie. Au cours de la derniere decennie, la question touchant plutot le sujet du developpement energetique durable represente le plus important domaine des politiques publiques ayant surgi recemment dans

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

    Energy Technology Data Exchange (ETDEWEB)

    Gwinner, B

    2004-03-01

    In the release scenario considered for geologic repository, water is thought to be the main aggressive agent with regards to bituminized radioactive waste (composed in general of 60 weight % of bitumen, 40% of soluble/insoluble salts and a few ppm of radionuclides). Since liquid water can diffuse in pure bitumen, leaching of bituminized waste results in the dissolution of the most soluble salts and leads to the development of a more or less concentrated saline solution-filled pore structure (called permeable layer). In consequence of the generation of a porous layer in the bituminized waste, leaching of salts and radionuclides can then take place. Research performed at the Atomic Energy Commission (CEA) aims therefore at understanding the consequences of ground-water immersion on the transport properties and radionuclides leaching of bituminized waste materials. To this end, a constitutive model (called COLONBO) which describes mathematically the leaching of bituminized waste has been developed. The COLONBO model is based on the following assumptions: 1. Water and dissolved salts migrate in the permeable layer according to Fick's first law. The diffusion of water and salts are quantified by effective diffusion coefficients which are unknown. 2. The mechanical properties of the bitumen matrix are not considered during leaching (free swelling). Up to now, the COLONBO model has been used only to model experimental water uptake and salt leach curves, leading (theoretical) estimates of the effective diffusion coefficients of water and salts in the permeable layer. The aim of this work was to validate experimentally the numerical results obtained with the COLONBO model. First, the correspondence between experimental and simulated water uptake and salt leach rates obtained on various bituminized waste materials is checked, leading estimates of the effective diffusion coefficients of water and salts in the permeable layer. Second, the evolution of the thickness and of

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

    Energy Technology Data Exchange (ETDEWEB)

    Pin, P

    2004-10-15

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

  11. Jeans criteria and stars formation in the Omnes matter-anti-matter supermassive star model; Critere de Jeans et formation d'etoiles dans le modele d'etoile supermassive matiere-antimatiere d'Omnes

    Energy Technology Data Exchange (ETDEWEB)

    Montmerle, Thierry

    1971-10-08

    This research thesis reports the study of the formation of stars in a quasar nucleus by using the Jeans criterion, and by adopting a model made of a super-massive star comprising an anti-matter nucleus surrounded by a matter envelope. After an overview of different observation results, and a presentation of different existing quasar models, the author details the Omnes model and its related problems. He reports the study of opacities to thermal photons (scattering and continuous absorption), and to γ radiation (absorption mechanism, creation of pairs in the interaction between γ rays and medium or between photons). The study of γ radiation transfer in a completely ionised gas is then reported (transfer equations, transfer equation coupling, heating of the semi-infinite medium, application to the nucleus with a plane approximation). Sound speed is then studied without γ (physical conditions, adiabatic case, non relativistic case, relativistic case), and in presence of γ. In the last chapter, the author discusses the application of the Jeans instability criterion to a medium governed by radiation. Results are discussed as well as consequences for the Omes model and for multiple-star models [French] Nous nous proposons d'etudier la formation d'etoiles dans le noyau d'un quasar au moyen du critere de Jeans. Nous adoptons un modele constitue d'une etoile supermassive (M> 10{sup 5} Mo) comprenant un noyau d'antimatiere entoure d'une enveloppe de matiere ('modele d'Omnes'). Apres avoir fait un bref tour d'horizon des divers resultats d'observation obtenus a ce jour et expose les differents modeles de quasar actuellement proposes (chapitre 1), nous decrirons en detail le modele d'Omnes. Nous exposerons un certain nombre de problemes qui lui sont lies, et nous donnerons la motivation du present travail (chapitre 2). Examinant plus particulierement l'opacite du milieu aux photons thermiques et aux photons γ (issus de l'annihilation matiere-antimatiere, nous etablirons

  12. Interpretation of criticality experiments on homogeneous solutions of plutonium and uranium; Interpretation des experiences de criticite sur des solutions homogenes de plutonium et d'uranium

    Energy Technology Data Exchange (ETDEWEB)

    Ithurralde, M F; Kremser, J; Leclerc, J; Lombard, Ch; Moreau, J; Robin, C [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1964-07-01

    Criticality experiments on solutions of fissionable materials have been carried out in tanks of various geometries (cylinder, isolated annular cylinder, interacting annular cylinders); the reflexion conditions have also been varied (without reflection, semi-reflection and total reflexion by water). The range of the studied concentrations is rather large (18,8 to 104 gms/liter). The interpretation of these experiments has been undertaken in order to resolve the problems of the industrial use of homogeneous plutonium and uranium solutions. Several methods the fields of application of which are different have been used: diffusion method, transport method and Monte-Carlo method. (authors) [French] Des experiences critiques sur des solutions de matieres fissiles ont ete faites dans des cuves de diverses geometries (cylindre, cylindre annulaire isole, cylindre annulaire en interaction), les conditions de reflexion ont ete egalement variees (sans reflexion, semi reflexion et reflexion totale par l'eau). La gamme des concentrations etudiees est assez etendue (18,8 a 104 g/l ). L'interpretation de ces experiences a ete entreprise dans le but de pouvoir resoudre les problemes poses par l'emploi industriel de solutions homogenes de plutonium et d'uranium, plusieurs methodes dont les domaines d'application sont differents ont ete employees: methode de diffusion, methode de transport, methode de Monte-Carlo. (auteurs)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1972-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

    As solid radioactive waste varies in form, dimensions and volume, the Atomic Energy Commission first of all reduces the volume by breaking up and compressing the waste. Since the temporary storage of such waste is always attended by the risk of contamination, an efficient packing system has been devised and adopted. This consists of embedding the waste in the heart of a specially-designed block of concrete possessing the following characteristics: Great strength Maximum insolubility Resistance to corrosion Maximum imperviousness Protection against radiation. It is thus quite safe to store these blocks with a view to final dumping. (author) [French] Les dechets actifs solides etant de formes, de dimensions et de volumes varies, le C.E.A. procede en premier lieu a une reduction de volume par fractionnement et compactage. L'emmagasinage provisoire de tels dechets ne pouvant se concevoir sans risques de contamination, un procede efficace d'emballage a ete etudie et realise. Il consiste a noyer les dechets dans un beton specialement etudie qui presente les caracteristiques suivantes: - Forte resistance mecanique . - Insolubilite maximum - Resistance a la corrosion - Etancheite maximum - Protection contre le rayonnement Il est alors possible de conserver sans danger les blocs formes en vue d'un rejet definitif ulterieur. (author) [Spanish] Como los desechos radiactivos solidos difieren mucho por su forma, dimension y volumen, el Commissariat efectua en primer lugar una reduccion de volumen desmenuzandolos y comprimiendolos. El almacenamiento provisional de esos desechos presenta siempre riesgos de contaminacion, por lo que se ha estudiado y llevado a la practica un sistema especial de embalaje. Este sistema consiste en empotrar los desechos en un hormigon especialmente estudiado que ofrece las siguientes caracteristicas: - Fuerte resistencia mecanica - Maximum de insolubilidad - Resistencia a la corrosion - Maximum de estanquidad - Proteccion contra las radiaciones De

  15. Developpement d'une methode calorimetrique de mesure des pertes ac pour des rubans supraconducteurs a haute temperature critique

    Science.gov (United States)

    Dolez, Patricia

    Le travail de recherche effectue dans le cadre de ce projet de doctorat a permis la mise au point d'une methode de mesure des pertes ac destinee a l'etude des supraconducteurs a haute temperature critique. Pour le choix des principes de cette methode, nous nous sommes inspires de travaux anterieurs realises sur les supraconducteurs conventionnels, afin de proposer une alternative a la technique electrique, presentant lors du debut de cette these des problemes lies a la variation du resultat des mesures selon la position des contacts de tension sur la surface de l'echantillon, et de pouvoir mesurer les pertes ac dans des conditions simulant la realite des futures applications industrielles des rubans supraconducteurs: en particulier, cette methode utilise la technique calorimetrique, associee a une calibration simultanee et in situ. La validite de la methode a ete verifiee de maniere theorique et experimentale: d'une part, des mesures ont ete realisees sur des echantillons de Bi-2223 recouverts d'argent ou d'alliage d'argent-or et comparees avec les predictions theoriques donnees par Norris, nous indiquant la nature majoritairement hysteretique des pertes ac dans nos echantillons; d'autre part, une mesure electrique a ete realisee in situ dont les resultats correspondent parfaitement a ceux donnes par notre methode calorimetrique. Par ailleurs, nous avons compare la dependance en courant et en frequence des pertes ac d'un echantillon avant et apres qu'il ait ete endommage. Ces mesures semblent indiquer une relation entre la valeur du coefficient de la loi de puissance modelisant la dependance des pertes avec le courant, et les inhomogeneites longitudinales du courant critique induites par l'endommagement. De plus, la variation en frequence montre qu'au niveau des grosses fractures transverses creees par l'endommagement dans le coeur supraconducteur, le courant se partage localement de maniere a peu pres equivalente entre les quelques grains de matiere

  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. Extensions of the techniques for the accelerated unspecific isotopic labelling of organic compounds; Applications nouvelles des techniques accelererees du marquage non specifique de composes organiques; Rasprostranenie metodov uskoreniya mecheniya nespetsifichnymi izotopami organicheskikh slozhnykh soedinenij; Nuevas aplicaciones de las tecnicas de marcacion inespecifica acelerada de compuestos organicos

    Energy Technology Data Exchange (ETDEWEB)

    Ghanem, N A [National Research Centre, El-Dokki, Cairo (Egypt); Westermark, T [Division of Physical Chemistry, Royal Institute of Technology, Stockholm 70 (Sweden)

    1962-03-15

    The paper aims at reviewing new means of obtaining acceleration in the reaction of a radioactive gas with a target material to be labelled and examples of successful cases. The techniques include the use of microwave and radiowave discharges, glow discharges affected through DC or AC sources, and simply ultraviolet radiation. Specific activities of more than 100 mc/g in purified significant quantities of products were obtained. Periods of exposure to discharge were of the order of one minute and decomposition was limited in most cases. Calculations of utilization of the energy absorbed during the labelling process were compared with the energy from ionizing radiation used by Wilzbach and others, and G values for isotope replacement are given. In polystyrene labelling, evidence is found that the mechanisms is governed by an atom-molecule reaction. (author) [French] Les auteurs passent en revue des methodes recentes visant a accelerer la reaction d'un gaz radioactif avec des matieres a marquer; ils citent des cas de reussite. Les techniques etudiees comportent l'emploi de decharges de micro-ondes et d'ondes hertziennes, de decharges luminescentes par des sources de courant continu ou alternatif et de simples rayons ultraviolets. On a obtenu des activites specifiques superieures a 100 mc/g dans des quantites importantes de produits purifies. Les temps d'exposition a la decharge etaient de l'ordre d'une minute; dans la plupart des cas, la decomposition etait limitee. Les auteurs comparent la quantite d'energie absorbee au cours du marquage a celle qui est necessaire lorsqu'on emploie des rayonnements ionisants, comme l'ont fait Wilzbach et autres; ils donnent les valeurs G de remplacement des isotopes. Dans le marquage du polystyrene, il semble bien que le processus soit regi par une reaction atome-molecule. (author) [Spanish] El objeto de la memoria es pasar revista a nuevos metodos para acelerar la reaccion de un gas radiactivo con el material de blanco que se desea

  18. Use of Radioactive Tracers in the Study of Insect-Plant Relationships; Emploi des radioindicateurs dans l'etude des relations insecte-plante; Ispol'zovanie radioaktivnykh indikatorov dlya izucheniya vzaimnoj svyazi mezhdu nasekomymi ch rasteniyami; Empleo de marcadores radiactivos para estudiar las relaciones insecto-planta

    Energy Technology Data Exchange (ETDEWEB)

    Crossley, Jr., D. A. [Radiation Ecology Section, Health Physics Division, Oak Ridge National Laboratory, Oak Ridge, TN (United States)

    1963-09-15

    In early uses of radioactive tracers in ecological investigations of pests insect, dispersion and migration phenomena were studied with radioisotopes as markers for individual insects. A more recent development is the use of radioisotopes to evaluate insect-plant and predator-prey associations through estimates of food utilization. Biological elimination of radioisotopes, a nuisance in dispersion studies, is being utilized as a measure of feeding rates. In both field and laboratory experimentation, insects are allowed to reach steady-state concentrations of radioisotopes through feeding. Then the rate of intake is equal to the rate of elimination of the radioisotope: (rate of ingestion) = (steady-state amount) x (fractional rate of loss). Measurements of elimination rates (biological half-lives) permit the steady-state concentrations to be ttanslated into intake rate functions. Food consumption studies have been performed for single-insect-species populations and for multiple- species populations. In a single-species investigation, radiocaesium in a tagged field site was used to estimate the consumption of willow leaves by populations of the beetle Chrysomela knabi. Direct measurements of food consumption made in the laboratory showed good agreement with field estimates of feeding rates based on the radioisotope techniques. Biological half-lives differed for the larval stages and these had to be considered separately. Radioisotopes provided a means of separating overwintering adults from newly emerged ones, through the more rapid elimination of caesium from overwintering adults. In multiple-species work, the relationship between size of insect and elimination rate was used to derive an average biological half-life for radiocaesium elimination from herbivorous insects in a field site tagged with caesium-137. This average rate, used in conjunction with data on plant and insect biomasses and concentrations of radiocaesium, permitted an evaluation of plant consumption

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

    incorporer dans d'autres substances les dechets a eliminer est la production d'une masse solide contenant les produits de fission. L'inconvenient que constituent les frais de traitement plus eleves peut etre parfois compense par une reduction des frais de stockage. La faible conductivite thermique des corps solides donne plus d'importance a la temperature de stockage que dans le cas de liquides. Les dechets acides de nitrate d'aluminium provenant du traitement des combustibles du type de ceux que l'on utilise dans les reacteurs d'essai des materiaux peuvent etre transformes en aluminium granule par voie de calcination dans un lit fluidifie a une temperature allant de 350 Degree-Sign a 550 Degree-Sign C. Les principaux elements de l'installation sont: un calculateur chauffe au NaK, un systeme d'epuration des gaz d'echappement et un ensemble de recipients pour le stockage des matieres solides obtenues. L'auteur donne un apercu du processus de traitement et du programme de recherche et de mise au point. L'auteur examine un certain nombre de systemes futurs de stockage et leurs incidences sur le milieu ambiant en prenant pour base les resultats positifs de la demonstration du systeme de calcination a ht fluidifie et d'emmagasinage a haute temperature ainsi que d'autres considerations. (author) [Spanish] En la planta de tratamiento quimico de Idaho, los desechos acidos procedentes de la recuperacion del uranio enriquecido de los combustibles nucleares que contienen aluminio, zirconio y acero inoxidable se almacenan en tanques subterraneos de dos formas, con capacidades nominales de 30,000 y 300,000 galones. El autor describe la organizacion y funcionamiento de la seccion de tanques, asi como los metodos utilizados para la evacuacion de desechos de baja actividad. La evacuacion de desechos con arreglo al, principio de la 'concentracion y confinamiento' tiene por finalidad la obtencion de una masa solida que retenga los productos de fision. Los gastos mas elevados que este

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

  2. Radioactive preparation of defects in solids; Creation de defauts dans les solides au moyen de radioisotopes; Ispol'zovanie radioaktivnosti dlya obrazovaniya defektov v tverdykh telakh; Creacion de deiectos en los solidos mediante radioisotopos

    Energy Technology Data Exchange (ETDEWEB)

    Lambe, J [Physics Department, Ford Motor Company, Scientific Laboratory, Dearborn, MI (United States)

    1962-01-15

    One of the major areas of interest in solid state physics is the study of defects in nearly perfect crystals. The controlled formation of such defects is thus an important aspect of these studies. Chemical additions and radiation damage are among the techniques which have been widely used to make such defects. In the present work some possibilities have been examined of using radioactive decay to form defects in solids. The technique is simply to make as perfect a material as possible but with some of the host crystal atoms radioactive. When these atoms decay the daughter product essentially forms the defect. As a simple means of testing the feasibility of this technique, it was used to prepare tritium atoms trapped in a crystal of solid molecular tritium. The experiments indicate that the technique is feasible and should have particular application to the preparation of free radicals in organic materials which are fairly resistant to radiation damage. (author) [French] L'etude des defauts que presentent les cristaux presque parfaits revet un interet primordial pour la physique de l'etat solide. La formation controlee de defauts de ce genre constitue ainsi un aspect important des travaux dans cette branche de la physique. Parmi les techniques frequemment employees a cette fin, figurent l'addition de produits chimiques et l'induction de dommages par exposition a des rayonnements. Au cours de leurs travaux, les auteurs ont etudie la possibilite de recourir a la desintegration radioactive de plusieurs manieres pour creer des defauts dans les solides. Le procede consiste simplement a produire une matiere ayant une structure aussi parfaite que possible mais dont certains cristaux renferment des atomes radioactifs. Lorsque ces atomes se desintegrent, le defaut est constitue essentiellement par le produit de filiation. Pour explorer par un moyen simple la possibilite d'utiliser ce procede, l'auteur a prepare des atomes de tritium fixes dans un cristal de tritium

  3. 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.)

  4. 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

  5. Guide for thesis quality at CEA / Physical Sciences Division; Guide pour la qualite des theses a la Direction des Sciences de la Matiere

    Energy Technology Data Exchange (ETDEWEB)

    Renault, J.Ph.; Rotureau, P. [CEA Saclay, Dept. de Recherche sur l' Etat Condense, les Atomes et les Molecules (DSM/DRECAM/SCM-URA 331), 91 - Gif sur Yvette (France); Skaza, F.; Lapoux, V. [CEA Saclay, Dept. d' Astrophysique, de Physique des Particules, de Physique Nucleaire et de l' Instrumentation Associee (DSM/DAPNIA/SPhN), 91- Gif sur Yvette (France); Saas, St.; Nguyen, F. [CEA Cadarache, Dept. de Recherches sur la Fusion Controlee (DSM/DRFC), 13 - Saint Paul lez Durance (France); Chaleard, C. [CEA Fontenay-aux-Roses, 92 (France); Thromat, N.; Pussieux, Th. [CEA Saclay, Dept. de Recherche sur l' Etat Condense les Atomes et les Molecules (DSM/DRECAM), 91 - Gif sur Yvette (France); Duc, R. [CEA Saclay, Direction des Sciences de la Matiere (DSM), 91 - Gif-sur-Yvette (France)

    2003-07-01

    Thesis is a basic component of scientific research. It has to be successful, for the student whose future depends widely on it, as well as for the host laboratory awaiting a profitable return on investment. The present guide, dedicated to students and their managers, aims to lead them to success by implementing a customized Quality approach. That tool, built as following the DSM Quality referential, wants to be, like this latter one: 'Useful, Usable, Used'. (authors)

  6. Review of the seismic risk in the design of civil engineering of nuclear installations excepted the long term storage of radioactive wastes; Prise en compte du risque sismique a la conception des ouvrages de genie civil d'installations nucleaires de base a l'exception des stockages a long terme des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    This guide aims to define, for the nuclear installations excepted the long term storage of radioactive wastes, from site data, the design specifications of earthquake resistant civil engineering and the possible methods for: the determination of the seismic response of the buildings, taking into account the interactions with the materials and the evaluation of the associated strains to size the installation; the determination of seismic displacements to be considered to size the materials. (A.L.B.)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

  8. The Effect of Fission Products on the Radioactivity of some Hydrobionts of the Pacific Ocean; Effet des Produits de Fission sur la Radioactivite de Certains Organismes Marins de l'Ocean Pacifique; 0412 041b 0418 0414 ; Influencia de los Productos de Fision en la Radiactividad de Algunos Organismos Marinos del Oceano Pacifico

    Energy Technology Data Exchange (ETDEWEB)

    Moiseev, P. A.; Kardashev, A. V. [All-Union Marine Fisheries and Oceanographical Scientific Research Institute, Moscow, USSR (Russian Federation)

    1960-07-01

    The paper emphasizes the fact that currents in the water masses disperse radioactive elements over large distances, with the result that many marine fauna and flora far removed from the centres of contamination may accumulate dangerous concentrations of such elements. (author) [French] Dans ce memoire, on souligne que les masses d'eau des courants marins transportent les elements radioactifs a de grandes distances; il s'ensuit que de nombreux animaux et vegetaux marins vivant loin des foyers de contamination peuvent accumuler ces elements jusqu'a des concentrations dangereuses. (author) [Spanish] En el informe se pone de manifiesto que las corrientes de agua transportan elementos radiactivos a grandes distancias, por lo cual muchos animales y vegetales marinos, que habiten lejos de los focos de contaminacion, pueden acumular estos elementos en concentraciones peligrosas. (author) [Russian] V doklade podcherkivaetsja, chto vodnye massy raznosjat techenijami radioaktivnye jelementy na bol'shie rasstojanija, v rezul'tate chego mnogie morskie zhivotnye i rastenija, obitajushhie daleko ot ochagov zarazhenija, mogut nakaplivat' ztj jelementy do opasnyh koncentracij. (author)

  9. The structure of nuclear matter; La structure de la matiere nucleaire

    Energy Technology Data Exchange (ETDEWEB)

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

    1959-07-01

    Report on the most recent developments in the theory of systems of interacting fermions. After having given the general form of the ground state energy in perturbation theory, one indicates the terms whose summation tends to the Brueckner approximation. The numerical results obtained with this theory are briefly mentioned. A discussion is given about the difficulty occurring in the case of potentials which are attractive near the Fermi surface due to the existence of the Cooper bound states. The main ideas of the proof of the Van Hove Hugenholtz theorem on the Fermi energy are indicated and its implications for the Brueckner theory are given. The extension of the methods described here to statistical mechanics are briefly mentioned. In the discussion, Professor Brueckner reports on the most recent results concerning the application of his theory to finite nuclei. Professor Migdal reviews the results which he has obtained with the method of Green's functions on the superconducting properties of finite nuclei. Professor Weisskopf gives a qualitative explanation of the success of the Brueckner theory. (author) [French] Rapport sur les recents travaux portant sur la theorie des systemes de fermions en interaction. Apres avoir donne la forme generale du developpement de l'energie de l'etat fondamental dans la theorie des perturbations, on indique les termes dont la sommation conduit a l'approximation de Brueckner. Les resultats numeriques obtenus a l'aide de cette theorie sont brievement mentionnes. Une discussion est donnee de la difficulte survenant dans le cas des potentiels attractifs au voisinage de la surface de Fermi par suite de l'existence des etats lies de Cooper. Les idees essentielles de la demonstration du theoreme de Van Hove et Hugenholtz sur l'energie de Fermi sont indiquees ainsi que ses consequences pour la theorie de Brueckner. L'extension des methodes decrites a la Mecanique Statistique est brievement mentionnee. Dans la discussion, le professeur

  10. Non-linearite et couplages lumiere-matiere en electrodynamique quantique en circuit

    Science.gov (United States)

    Bourassa, Jerome

    L'électrodynamique quantique en circuit est un contexte unique pour l'optique quantique et le calcul quantique. Dans cette architecture où des qubits supraconducteurs, composés de jonctions Josephson, sont fortement couplés au champ électromagnétique de résonateurs coplanaires, la dynamique du système est semblable à celle des atomes dans des cavités optiques. La polyvalence de la conception des circuits supraconducteurs permet d'étudier l'interaction lumière-matière de différents régimes et manières. Ainsi, plusieurs qubits peuvent être couplés à un seul résonateur afin de les enchevêtrer. Une jonction Josephson peut également être intégrée directement au résonateur afin de produire une interaction non linéaire entre les photons. De la même manière, il a été suggéré que le couplage qubitrésonateur pourrait devenir l'échelle d'énergie dominante du système : le régime de couplage ultrafort. Malgré que la dynamique qubit-résonateur soit bien comprise, les modèles actuels ne permettent pas de prédire correctement les effets dispersifs du résonateur sur les qubits tels : le décalage de Lamb, l'interaction d'échange virtuelle et le temps de relaxation. Comme il n'y a pas non plus de modèle général permettant de déterminer les caractéristiques d'un résonateur non linéaire, on comprend mal comment rendre la non-linéarité plus forte, ni même si le régime de couplage ultrafort peut être physiquement réalisé dans ces circuits. Dans le cadre de ma thèse, je me suis intéressé à la modélisation de qubits et de résonateurs afin de mieux comprendre l'interaction lumière-matière en circuits, dans le but de développer des conceptions alternatives d'architectures plus performantes ou qui explorent des régimes d'interactions méconnus. Pour ce faire, j'ai développé une méthode analytique générale permettant de trouver l'hamiltonien exact de circuits distribués non linéaires, une méthode basée sur la m

  11. Radioactive survey of the environment of the nuclear sites of French Nuclear Board: an overview; Bilan de la surveillance de la radioactivite dans l'environnement des sites du commissariat a l'energie atomique

    Energy Technology Data Exchange (ETDEWEB)

    Robeau, D; Montjoie, M; Sauve, A M; Laporte, J; Rahaplen, A; Alphonse, L; Huc, C [C.E.A./Institut de Protection et de Surete Nucleaire, Centre d' Etudes de Fontenay-aux-Roses, Fontenay-aux-Roses (France); Bensimon, C; Cissoko, G [Compagnie Internationale de Services Informatiques (France)

    1992-07-01

    C.E.A. has set up a network of radioactive survey around its nuclear sites. This network involves terrestrial, atmospheric and marine results of radioactive measurements. This survey is structured in four levels. The level 0 homogenizes stations of measurements, level 1 centralizes real-time measurements of gross {alpha} and {beta} measurements of atmospheric radioactivity, level 2 and 3 centralizes postponed {alpha}-{beta} spectrometric measurements of radioactivity on water, deposition, grass, vegetables. People can have a squint at these results of measurements using popular MINITEL telephonic network. (author)

  12. 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

  13. 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

  14. Study of the behaviour of organic carbon in the soil, and carbon 14 study of podzols; Contribution a l'etude du comportement du carbone organique dans le sol et etude des podzols a l'aide du carbone 14

    Energy Technology Data Exchange (ETDEWEB)

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

    1969-07-01

    Using the penetration into soil of carbon 14 of thermo-nuclear origin, the behaviour and renewal rate were studied on different organic fractions of the soil. It was established that 18% of the total organic matter is renewed in about 400 years. In addition the formation of podzol-type fossil soils in France was dated from the first millenary B.C., i.e. the end of the sub-boreal period and the beginning of the atlantic period. (author) [French] En utilisant la penetration dans le sol du carbone 14 d'origine thermonucleaire, on a etudie le comportement et la vitesse de renouvellement des differentes fractions de la matiere organique du sol. On a pu preciser que 18% de la matiere organique globale se renouvelait en 400 ans environ. Par ailleurs, la formation en France des sols fossiles du type podzol a ete datee du premier millenaire avant J.C. c'est a dire a la fin de la periode subboreale et au debut de la periode atlantique. (auteur)

  15. Instrument for continuous supervision of the radioactivity of CO{sub 2} coolant in piles - DCCA -CO{sub 2} (1960); Dispositif de controle continu de la radioactivite du CO{sub 2} de refroidissement des piles - DCCA - CO{sub 2} (1960)

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

    This paper describes an apparatus for continuous measurement of CO{sub 2} activity, which can be used on piles cooled by circulation of gas. The first part is devoted mainly to describing the apparatus used and the character of the radioactivity and thermodynamic measurements carried out, and giving the general characteristics of the gas circuit required if the instrument is to be suitably gas-tight. In the second part theoretical calculations are given, particularly on the determination of the ionisation current in an ionisation chamber with circulating gas. Several parameters enter into this determination, such as the mean path of {beta} particles in the ionisation chamber, the linear number of ion pairs formed in the gas by these {beta} particles as a function of their energy, the temperature and pressure of the gas in the ionisation chamber. This part also evaluates the sensitivity areas of the apparatus for measuring the concentrations of radioactive gases such as argon-41 and fission gases from uranium-235 in the CO{sub 2} coolant. In the last part are described the results of measurements performed with such an apparatus on the pile EL2, the special investigations carried out on the CO{sub 2} coolant of this pile, and the information gained during normal operation and during accidents. The DCCA - CO{sub 2} which has just been put in operation at G2 is briefly presented. In the conclusion the possibilities offered by this apparatus are underlined. (author) [French] Ce rapport a pour but de presenter le Dispositif de Controle continu de l'Activite du CO{sub 2} pouvant etre utilise aupres des piles refroidies par une circulation de gaz. La premiere partie du rapport consiste essentiellement a decrire l'ensemble de l'appareillage mis en oeuvre, a preciser la nature des mesures de radioactivite et de thermodynamique effectuees et a citer les caracteristiques generales du circuit de gaz pour avoir un dispositif presentant une etancheite efficace. Dans la seconde

  16. Instrument for continuous supervision of the radioactivity of CO{sub 2} coolant in piles - DCCA -CO{sub 2} (1960); Dispositif de controle continu de la radioactivite du CO{sub 2} de refroidissement des piles - DCCA - CO{sub 2} (1960)

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

    This paper describes an apparatus for continuous measurement of CO{sub 2} activity, which can be used on piles cooled by circulation of gas. The first part is devoted mainly to describing the apparatus used and the character of the radioactivity and thermodynamic measurements carried out, and giving the general characteristics of the gas circuit required if the instrument is to be suitably gas-tight. In the second part theoretical calculations are given, particularly on the determination of the ionisation current in an ionisation chamber with circulating gas. Several parameters enter into this determination, such as the mean path of {beta} particles in the ionisation chamber, the linear number of ion pairs formed in the gas by these {beta} particles as a function of their energy, the temperature and pressure of the gas in the ionisation chamber. This part also evaluates the sensitivity areas of the apparatus for measuring the concentrations of radioactive gases such as argon-41 and fission gases from uranium-235 in the CO{sub 2} coolant. In the last part are described the results of measurements performed with such an apparatus on the pile EL2, the special investigations carried out on the CO{sub 2} coolant of this pile, and the information gained during normal operation and during accidents. The DCCA - CO{sub 2} which has just been put in operation at G2 is briefly presented. In the conclusion the possibilities offered by this apparatus are underlined. (author) [French] Ce rapport a pour but de presenter le Dispositif de Controle continu de l'Activite du CO{sub 2} pouvant etre utilise aupres des piles refroidies par une circulation de gaz. La premiere partie du rapport consiste essentiellement a decrire l'ensemble de l'appareillage mis en oeuvre, a preciser la nature des mesures de radioactivite et de thermodynamique effectuees et a citer les caracteristiques generales du circuit de gaz pour avoir un dispositif presentant une etancheite efficace

  17. A Scintillation Camera for Kinetic Studies of the Distribution of Radioactive Nuclides in the Brain; Chambre a Scintillation pour des Etudes sur la Cinetique de la Repartition des Radionucleides dans le Cerveau; Stsintillyatsionnaya kamera dlya kineticheskogo issledovaniya raspredeleniya radioaktivnykh izotopov v tkani mozga; Camara de Centelleo para Estudiar la Cinetica de la Distribucion de Radionuclidos en el Cerebro

    Energy Technology Data Exchange (ETDEWEB)

    Gross, W. [Radiological Research Laboratory, Department Of Radiology, Columbia University, New York, NY (United States); Schlesinger, E. B.; De Boves, S. [Department of Neurological Surgery, Columbia University, New York, NY (United States)

    1964-10-15

    A scintillation camera specifically designed for the study of the kinetics of the distribution of radioactive nuclides in the brain has been developed. This device employs two banks of 3/4 in x 1 in sodium iodide-thallium activated crystals, 63 crystals per bank arranged in a 7 x 9 close-packed array on 1-in centres. These banks can be placed so that both lateral views or one lateral and one P-A or A-P view can be obtained simultaneously. The field of view of each crystal is limited by a collimator consisting of nineteen tapered holes whose axes are all parallel. This design gives a response of nearly equal full-width at half height to a simulated tumour source at all distances up to 4 in from the front of the collimator. This response is sufficiently wide to avoid significant ''dead'' areas and yet narrow enough to permit accurate observation of the activity distribution within a very few minutes using normal tracer doses of iodine-131. Each crystal is optically coupled to its own photomultiplier in an integral package. The output pulses of the photomultipliers are analysed by discriminators and the information stored in digital form in a quarter of the memory of a 512-channel pulse-height analyser. Time coincident pulses from the various detectors can be accepted by this equipment so that losses are negligible. Read-out in several forms is available. In digital form either a typewritten record or punched paper tape can be obtained. The latter may be read back into the equipment for review. Analogue read-out is made on a large screen oscilloscope. The scope beam is defocused and two 63 point display rasters generated to correspond to the spatial location of the scintillation counters. Intensity modulation of the oscilloscope beam as well as background erasure is used to assist in visualizing the activity distribution. (author) [French] Les auteurs ont mis au point une chambre a scintillation specialement concue pour des etudes sur la cinetique de la repartition

  18. 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.)

  19. Development of an application simulating radioactive sources

    International Nuclear Information System (INIS)

    Riffault, V.; Locoge, N.; Leblanc, E.; Vermeulen, M.

    2011-01-01

    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)

  20. Optimization of fuel cycles: marginal loss values; Optimisation des cycles de combustibles: valeurs marginales des pertes

    Energy Technology Data Exchange (ETDEWEB)

    Gaussens, J [Commissariat a l' Energie Atomique, 75 - Paris (France); Lasteyrie, B de; Doumerc, J [Compagnie pour l' Etude et la Realisation de Combustibles Atomiques, 75 - Paris (France)

    1965-07-01

    comme definitivement perdue, alors que le reste pourrait etre recupere et recycle. Le cout eleve des pertes, recyclees ou non, d'autant plus eleve que l'uranium est plus enrichi, exige qu'il en soit tenu compte dans l'optimisation generale des cycles de combustible. Il importe donc de determiner leur niveau le plus souhaitable economiquement, aux diverses etapes d'elaboration du combustible nucleaire. Mais en France et dans d'autres pays, la production de matieres fissiles est geree par l'Etat, tandis que la fabrication de l'element combustible est effectuee par l'industrie privee. Les criteres d'optimisation et l'interet economique accorde aux pertes sont donc differents pour les deux parties de la chaine de fabrication. Pour tenter neanmoins d'atteindre un optimum conforme a l'interet collectif sans intervenir dans la politique de prix de l'entreprise, on peut utiliser la propriete des couts marginaux d'etre egaux entre eux a l'optimum, pour un volume de production donne. On peut donc ajuster le niveau des pertes pour realiser cette egalite des couts marginaux dont le calcul est plus facile a obtenir de la firme que la justification des prix eux-memes. On s'apercoit d'ailleurs que, bien qu'axee essentiellement sur les pertes, cette analyse globale peut conduire a une meilleure utilisation d'autres facteurs de production. On donne un expose theorique et des exemples pratiques de cette methode d'optimisation economique dans le cadre de la fabrication d'elements combustibles destines a des reacteurs du type: uranium naturel, moderes au graphite et refroidis par le gaz carbonique. (auteurs)

  1. Monte-Carlo method - codes for the study of criticality problems (on IBM 7094); Methode de Monte- Carlo - codes pour l'etude des problemes de criticite (IBM 7094)

    Energy Technology Data Exchange (ETDEWEB)

    Moreau, J; Rabot, H; Robin, C [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1965-07-01

    The two codes presented here allow to determine the multiplication constant of media containing fissionable materials under numerous and divided forms; they are based on the Monte-Carlo method. The first code apply to x, y, z, geometries. The volume to be studied ought to be divisible in parallelepipeds, the media within each parallelepiped being limited by non-secant surfaces. The second code is intended for r, 0, z geometries. The results include an analysis of collisions in each medium. Applications and examples with informations on time and accuracy are given. (authors) [French] Les deux codes presentes dans ce rapport permettent la determination des coefficients de multiplication de milieux contenant des matieres fissiles sous des formes tres variees et divisees, ils reposent sur la methode de Monte-Carlo. Le premier code s'applique aux geometries x, y, z, le volume a etudier doit pouvoir etre decompose en parallelepipedes, les milieux a l'interieur de chaque parallelepipede etant limites par des surfaces non secantes. Le deuxieme code s'applique aux geometries r, 0, z. Les resultats comportent une analyse des collisions dans chaque milieu. Des applications et des exemples avec les indications de temps et de precision sont fournis. (auteurs)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

  3. Cooperation in the Event of Nuclear Accidents; Cooperation en Matiere d'Accidents Nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Bresson, G. [CEA, Centre d' etudes nucleaires, de Fontenay-aux-Roses (France)

    1969-10-15

    This paper is concerned only with the action to be taken in respect of an individual directly affected by an accident and not with the more general measures relating to the population as a whole. Keeping the same sequence of ideas, the paper deals with nuclear establishments and cites criteria for classifying them; hence only the relationship between the establishment and the hospital, and between the radiation protection experts and medical personnel, is discussed. The complex organization of emergency measures, reception of the victim of the accident, and the treatment possibly required should be based on standard practice and published material, both national and international, allowance being made for the characteristics of each sector. A ''flexible'' plan of co-ordination is given as an illustration. Action must be taken in such cases at the site of the accident, inside and outside the establishment, and above all at the hospital. All categories of persons are involved in the process, i.e. fellow-workers, management, specialized services, and medical personnel, each with their own part to play. The manpower and equipment brought into service therefore vary, and depend upon the internal and external relations maintained by the establishment. The measures envisaged should provide for the transport, reception and treatment of those involved in the accident. An existing organization of this kind is described as an illustration. Finally, no action can be of value without full knowledge of the facts and thorough training of the personnel. Some clearly defined ideas on the.subject are considered under this heading. (author) [French] Le memoire ne traite que de la conduite a tenir envers un accidente et non du probleme, plus general, des mesures relatives a une population. Dans le meme ordre d'idees, l'etude porte sur les etablissements nucleaires et leurs criteres de classement; il ne s'agit donc que des liaisons entre retablissement et l'hopital et entre les

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-02-15

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

  5. LA COMPARAISON DE LA MUSIQUE TURQUE ET OCCIDENTALE EN MATIERE DE GAMME, RYTHME ET TONALITE

    Directory of Open Access Journals (Sweden)

    Kubilay Kolukirik

    2012-12-01

    Full Text Available Après avoir fini mon Doctorat en musique à l’université d’Ankara en Turquie, j’ai travaillé en tant que Maitre de conférences à l’université de Nevşehir. J’ai alors été contacté par le Conservatoire Claude Debussy, situé dans le 17eme arrondissement de Paris, afin d’effectuer une recherche comparative sur le Jazz et la musique folklorique Turque. Dans ce contexte j'ai participé aux cours de jazz de Philippe Poussard avec mon instrument authentique turc nommé "bağlama". Avec ce dernier nous avons joué des chansons folkloriques Turques, et j'ai ressenti que lui et ses étudiants ont été impressionnés par la musique que nous avons jouée ensemble, enimprovisant. Nous avons ensuite discuté de différents sujets à propos des musiques Turque et Occidentale. J'ai alors constaté que les étudiants de ce conservatoire n'ont aucune connaissance sur la musique Turque en générale. J'ai alors décidé d’effectuer une analyse théorique sur les questions fondamentales de la musique Occidentale etde la musique Turque. Je pense qu'il est important de donner des informations sur la théorie de la musique dans les établissements scolaires occidentaux. Ceci est important pour la communication entre les deux cultures musicales. En rédigeant mon article j'ai utilisé la méthode d'analyse de documents. J'ai aussi utilisé mes expériences personnelles acquises au Conservatoire pour faire un travail de comparaison appliquée. J'ai constaté qu'en termes de gamme, rythme et tonalité il y avait beaucoup de différences mais également des similitudes dans la musique Turque et Occidentale. L'objectif de cet article est de comparer les théories musicales Turque et Occidentale c’est à dire étudier leurs aspects similaires et différents en terme de gamme, rythme et de tonalité.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2005-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

  8. ANALYSE DES PERCEPTIONS LOCALES ET DES FACTEURS ...

    African Journals Online (AJOL)

    AISA

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

  13. 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)

  14. Some particular aspects of control in nuclear power reactors; Conception de la surete en france et influence des imperatifs de surete sur la conception des reacteurs

    Energy Technology Data Exchange (ETDEWEB)

    Vathaire, F de; Vernier, Ph; Pascouet, A [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1964-07-01

    This paper reviews the experience acquired in France on the question, of reactor safety. Since a special paper is being presented on reactors of the graphite gas type, the safety of the other types studied in France is discussed here: - heavy water-gas reactors, - fast neutron reactors, - water research reactors of the swimming-pool and tank types. The safety rules peculiar to the different types are explained, with emphasis on their influence on the reactor designs and on the power limits they impose. The corresponding safety studies are presented, particular stress being placed on the original work developed in these fields. Special mention is made of the experimental systems constructed for these studies: the reactor CABRI, pile loop for depressurization tests, loops outside the pile, mock-ups etc. (authors) [French] La presente communication propose une synthese de l'experience acquise en France en matiere de surete des reacteurs. Les reacteurs de la filiere graphite-gaz faisant l'objet d'une communication particuliere, on examine ici la surete des autres types de reacteurs etudies en France: - reacteurs eau lourde-gaz, - reacteurs a neutrons rapides, - reacteurs de recherche a eau des types piscines et tank. Les imperatifs de surete propres aux differentes filieres sont developpes, en mettant l'accent sur leur influence sur la conception des reacteurs et sur les limitations de puissance qu'ils entrainent. Les etudes de surete correspondantes sont presentees, en insistant plus particulierement sur les travaux originaux developpes dans ces domaines. On indique notamment les moyens d'essais qui ont ete construits pour ces etudes: le reacteur CABRI, boucle en pile pour essais de depressurisation, boucles hors pile, maquettes, etc. (auteurs)

  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. Evaluation d'une approche pedagogique respectant les facons d'apprendre des filles en sciences et en TIC en 9e annee au Nouveau-Brunswick

    Science.gov (United States)

    Lirette-Pitre, Nicole T.

    2009-07-01

    La reussite scolaire des filles les amene de plus en plus a poursuivre une formation postsecondaire et a exercer des professions qui demandent un haut niveau de connaissances et d'expertise scientifique. Toutefois, les filles demeurent toujours tres peu nombreuses a envisager une carriere en sciences (chimie et physique), en ingenierie ou en TIC (technologie d'information et de la communication), soit une carriere reliee a la nouvelle economie. Pour plusieurs filles, les sciences et les TIC ne sont pas des matieres scolaires qu'elles trouvent interessantes meme si elles y reussissent tres bien. Ces filles admettent que leurs experiences d'apprentissage en sciences et en TIC ne leur ont pas permis de developper un interet ni de se sentir confiante en leurs habiletes a reussir dans ces matieres. Par consequent, peu de filles choisissent de poursuivre leurs etudes postsecondaires dans ces disciplines. La theorie sociocognitive du choix carriere a ete choisie comme modele theorique pour mieux comprendre quelles variables entrent en jeu lorsque les filles choisissent leur carriere. Notre etude a pour objet la conception et l'evaluation de l'efficacite d'un materiel pedagogique concu specifiquement pour ameliorer les experiences d'apprentissage en sciences et en TIC des filles de 9e annee au Nouveau-Brunswick. L'approche pedagogique privilegiee dans notre materiel a mis en oeuvre des strategies pedagogiques issues des meilleures pratiques que nous avons identifiees et qui visaient particulierement l'augmentation du sentiment d'auto-efficacite et de l'interet des filles pour ces disciplines. Ce materiel disponible par Internet a l'adresse http://www.umoncton.ca/lirettn/scientic est directement en lien avec le programme d'etudes en sciences de la nature de 9e annee du Nouveau-Brunswick. L'evaluation de l'efficacite de notre materiel pedagogique a ete faite selon deux grandes etapes methodologiques: 1) l'evaluation de l'utilisabilite et de la convivialite du materiel et 2

  17. 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)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1962-07-09

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

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

    African Journals Online (AJOL)

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-07-01

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

  1. Molecular Dynamics Simulation of Spontaneous Imbibition in Nanopores and Recovery of Asphaltenic Crude Oils Using Surfactants for EOR Applications Simulations de dynamique moléculaire d’imbibition spontanée dans des nanopores et pour la récupération d’huiles brutes asphalténiques en utilisant des agents tensioactifs pour des applications d’EOR

    Directory of Open Access Journals (Sweden)

    Stukan M.R.

    2012-12-01

    Full Text Available We present Molecular Dynamics (MD simulations of the imbibition process in nanopores in case of two different mechanisms of the wettability modification. We compare the imbibition of an aqueous surfactant solution into an oil-wet pore driven by surfactant adsorption onto the oil-wet rock surface (coating mechanism and the imbibition of an aqueous surfactants solution driven by surfactants removing the contaminant molecules from the originally water-wet surface (cleaning mechanism. Our results show qualitative difference in the imbibition dynamics in these two cases and indicate that MD simulation is a useful tool to investigate details of the imbibition mechanisms at the pore scale with direct implications for Enhanced Oil Recovery (EOR operations. Nous presentons des simulations de Dynamique Moleculaire (DM du processus d’imbibition dans des nanopores dans le cas de deux mecanismes differents de modification de mouillabilite. Nous comparons l’imbibition d’une solution aqueuse d’agent tensioactif dans un pore mouille d’huile entrainee par une adsorption d’agent tensioactif sur la surface de roche mouillee d’huile (mecanisme de revetement et l’imbibition d’une solution aqueuse d’agent tensioactif entrainee par des agents tensioactifs eliminant les molecules contaminantes de la surface originellement mouillee d’eau (mecanisme de nettoyage. Nos resultats montrent une difference qualitative en matiere de dynamique d’imbibition dans ces deux cas et indiquent que la simulation de DM constitue un outil utile pour etudier les mecanismes d’imbibition a l’echelle des pores avec des implications directes pour des operations de recuperation renforcee d’huile (EOR, Enhanced Oil Recovery.

  2. The Determination of Components of Radioactive Decay Mixtures by Computer Analysis of Count-Rate Data; Determination des Composants de Melanges Radioactifs en Decroissance par Analyse a l'Ordinateur des Resultats du Comptage; Opredelenie komponentov smesej radioaktivnogo raspada posredstvom analiza dannykh skorostej scheta s pomoshch'yu schetno-reshayushchego ustrojstva; Determinacion de los Componentes de Mezclas Radiactivas por Analisis de los Datos de Recuento Mediante Calculadoras

    Energy Technology Data Exchange (ETDEWEB)

    Airman, W. D.F.; Tyler, S. A.; Dipertand, M. H.; Sedlet, J. [Argonne National Laboratory, Argonne, IL (United States)

    1965-10-15

    The components of a mixture of n radioactive isotopes can be determined from the change in activity with time provided that the activity of at least n-1 components changes significantly during the period of observation, either by direct decay or by the growth of decay products. ft is possible to predict a set of possible components for each mixture encountered, based on considerations such as the origin and history of the mixture and the separation chemistry and counting technique(s) used. If such considerations are properly applied, the set of possible components will include all of the actual components in the mixture. The appropriate growth and/or decay equations can then be formulated and solved simultaneously to obtain each component, or the mixture can be resolved graphically by extrapolations of the linear portions of the total decay-growth curve. However, when the number of components is large and/or when complex decay schemes are involved, these two techniques either cannot be applied or the errors associated with the estimates cannot be assessed. Selection of decay components by a least-squares procedure provides better estimates than solution by simultaneous equations alone. Consequently, a least-squares Fortran computer programme (designated CORD) has been developed which solves the general problem: given the times and counts per unit time from a sample, the possible radioisotopic parents and decay schemes and all associated decay constants and detection efficiencies compute the amount of each parent actually present at a predetermined zero time. In addition, the programme yields the amounts of the parents and daughters present at all data times. Initially used with bioassay and environmental samples, the programme has been specifically designed for analysing count-rate data obtained by non-spectroscopic alpha- or beta-counting. However, it should be adaptable to total gamma and spectroscopic data, provided the energy ranges over which these

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

    The earth is the sphere of interest of the geologist, and it is the only place on or in which wastes can he dispersed or stored. In that sense, problems of radioactive waste disposal are primarily geological. Accumulated geologic knowledge and established principles have been applied widely in the United States to problems of disposal, and the unique nature of these problems has led to research and significant advances of knowledge in specialized aspects of geology. A common activity has been appraisal of sites for nuclear energy facilities. This includes analysis and evaluation of geologic, topographic, hydrologic, geochemical and seismic factors. Also, regional analyses are made of the gross characteristics of. major physical subdivisions of the United States and the relation of these characteristics to waste storage and disposal. Special problems include the actual and potential behaviour of ordinary wastes in specific geologic environments. Other studies concern possible use of structural basins, stratigraphic traps, and salt beds and salt domes for storage and containment of high-level waste. Much general and some detailed study has been made of background radiometry. Water is the critical factor in waste disposal; accordingly certain natural processes by which water may be purified or chemically altered have been investigated. Significant results have been achieved in studies of dispersion and diffusion processes in ground water and surface water ; the rate of travel of contaminants in streams; the mechanics of ground-water flow in granular materials ; ground-water flow in cavernous rocks ; and the behaviour of water and chemical solutions in the zone of aeration. Thermal and chemical-stability problems that would develop if high-level waste were injected in geologic formations also have been investigated. Geologic, petrologic and geophysical studies have been made of specific areas, and research in clay mineralogy, ion exchange and geochemistry has been

  4. The use aeroplanes and vehicles for prospecting. The technique of the detection radioactivity. The future opened up by the use of the discrimination of energies; Methodes de prospection autoportee et aeroportee. La technique de la detection des rayonnements. Les perspectives offertes par la discrimination des energies

    Energy Technology Data Exchange (ETDEWEB)

    Guitton, J; Berbezier, J; Blangy, B; Lallemant, C [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    The idea of installing activity detectors on aeroplanes and vehicles has been widely applied by the CEA since the start of prospecting in the arid and tropical regions of the Communaute Francaise. Three systems of detection have been developed and compared in a systematic manner: a group of 50 G.M. tubes; the sodium iodide scintillator; the plastic scintillator. The sodium iodide scintillator is used as a standard reference; the results are compared by graphical recording. Airborne prospecting is carried out in two stages: the initial flights, which follow a kilometre square network, make possible the discovery of the most likely zones; these likely zones are then examined in greater detail using light aeroplanes or helicopters. The two types of airborne scintillation measuring devices which have been developed by the CEA are described in this article. The practical results obtained during systematic and detailed airborne prospecting campaigns in the Hoggar are described. The difficulty in airborne uranium prospecting is to be able to immediately distinguish while in flight, anomalies caused by uranium from those caused by thorium. (author) [French] L'idee de monter des detecteurs de rayonnements sur des avions ou des vehicules a ete largement appliquee par le CEA des le debut des prospections dans les pays sahariens et tropicaux de la Communaute Fran ise. On a realise et compare d'une maniere systematique trois moyens de detection: groupe de 50 tubes GM; scintillateur d'iodure de sodium, scintillateur plastique. L'appareil de reference sera le scintillateur d'iodure de sodium; les resultats sont compares par enregistrement graphique. La prospection aeroportee se fait en deux etapes; les premiers vols systematiques suivant un quadrillage kilometrique permettent de reperer les zones interessantes; ces dernieres font l'objet d'examens plus detailles effectues en avion leger ou en helicoptere. Dans cet article, on decrit les deux types de scintillometres aeroportes

  5. variabilite des productions et des revenus des exploitations

    African Journals Online (AJOL)

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

  7. 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)

  8. 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)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2006-07-01

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

  10. Measurement of the diffusion length of thermal neutrons in the beryllium oxide; Mesure de la longueur de diffusion des neutrons thermiques dans l'oxyde de beryllium

    Energy Technology Data Exchange (ETDEWEB)

    Koechlin, J C; Martelly, J; Duggal, V P [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1955-07-01

    The diffusion length of thermal neutrons in the beryllium oxide has been obtained while studying the spatial distribution of the neutrons in a massive parallelepiped of this matter placed before the thermal column of the reactor core of Saclay. The mean density of the beryllium oxide (BeO) is 2,95 gr/cm{sup 3}, the mean density of the massif is 2,92 gr/cm{sup 3}. The value of the diffusion length, deducted of the done measures, is: L = 32,7 {+-} 0,5 cm (likely gap). Some remarks are formulated about the influence of the spectral distribution of the neutrons flux used. (authors) [French] La longueur de diffusion des neutrons thermiques dans l'oxyde de beryllium a ete obtenue en etudiant la repartition spatiale des neutrons dans un massif parallelepipedique de cette matiere placee devant la colonne thermique de la Pile de Saclay. La densite moyenne de l'oxyde de beryllium (BeO) est de 2,95 gr/cm{sup 3}, la densite moyenne du massif de 2,92 gr/cm{sup 3}. La valeur de la longueur de diffusion, deduite des mesures effectuees est: L 32,7 {+-} 0,5 cm (ecart probable). Des remarques sont formulees quant a l'influence de la repartition spectrale du flux de neutrons utilise. (auteurs)

  11. Role of LPG as an energy substitute in Algeria; Role des G.P.L. comme energie de substitution en Algerie

    Energy Technology Data Exchange (ETDEWEB)

    Boukadoum, Abdelhamid; Houghlaouene, Samir

    2010-09-15

    Algeria is a leader country in LPG industry. The availability of resources and the upstream production development efforts have oriented the large energy choices in terms of domestic market need satisfaction. LPG (propane and butane) plays a massive role in the change towards clean energy (case of LPG versus gas) and towards more practical energy (i.e. the case of bulk propane versus the packed butane, or versus natural gas). [French] L'Algerie est un pays leader dans l'industrie des GPL. La disponibilite des ressources et les efforts de developpement de la production en amont ont oriente les grands choix energetiques en matiere de satisfaction des besoins du marche domestique. En effet, les GPL (propane et butane) jouent un role majeur dans la substitution vers les sources d'energie propres (cas du GPL/C par rapport aux essences) et vers des energies plus commodes (par exemple le cas du propane vrac par rapport au butane conditionne, voire par rapport au gaz naturel).

  12. 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.)

  13. 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

  14. Energies and raw material. Annual report; Energies et matieres premieres. Rapport annuel

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-07-01

    The annual report of the french General Direction of the Energy and the Raw Material (DGEMP) deals with the energy policy. The following subjects are analysed: the french program of fight against the global warming; the biogas; the radioactive wastes management program; the french nuclear industry re-organization; Tchernobyl; the electric power and gas public service; the risk prevention concerning the electric power production; the international Gaz De France protocol; the closing of the Ales mine; the cooperation ELF and TOTAL; the french para-petroleum industry; the raw material prices; the french mining situation; the french energy policy audit by the AIE; the energy accidents of december. The DGEMP organization chart with contacts and the publications are also included. (A.L.B.)

  15. Lessons learned in terms of crisis management; Les enseignements en matiere de gestion de crise

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    This document outlines that nobody was prepared to the crisis which occurred after the Chernobyl accident, whether in Russia, Europe or France. In order to illustrate the fact that crisis management has been different from one country to another, the report describes how the crisis has been managed in Norway (which has been quickly reached by fallouts and with a rather high level) and in Switzerland. It comments radioactivity measurements performed in France during spring 1986 by the SCPRI, the CEA and the ISPN. It discusses the lessons drawn in France in terms of emergency situation management regarding the protection of the population, crisis management, and the French post-accidental doctrine. It comments the lessons drawn in eastern European countries, with the cooperative implication of the IRSN. International projects are evoked: the Chernobyl Centre, the French-German Initiative, the European projects (EURANOS, NERIS, FARMING, STRATEGY, MOSES and SAMEN)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2004-06-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1969-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-11-15

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

  19. The procedure of alternative site selection within the report of the study group on the radioactive waste final repository selection process (AKEnd); Das Verfahren der alternativen Standortsuche im Bericht des Arbeitskreises Auswahlverfahren Endlagerstandorte (AKEnd)

    Energy Technology Data Exchange (ETDEWEB)

    Brenner, M. [Jena Univ. (Germany)

    2005-07-01

    The paper discusses the results of the report of the study group on the radioactive waste final repository selection process with respect to the alternative site selection procedure. Key points of the report are the long-term safety, the alternativity of sites and the concept of one repository. The critique on this report is focussed on the topics site selection and licensing procedures, civil participation, the factor time and the question of cost.

  20. Civili, langue des Baloango

    DEFF Research Database (Denmark)

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

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

  1. Des racines et des ailes

    Directory of Open Access Journals (Sweden)

    Stéphanie Vincent-Geslin

    2012-05-01

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

  2. 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

  3. Absolute Measurement of Radioactive Materials at the Physikalisch-Technische Bundesanstalt; Mesure absolue des substances radioactives a l'Institut federal de physique appliquee; Absolyutnoe izmerenie radioaktivnykh veshchestv v fiziko-tekhnicheskom federal'nom institute; Determinacion absoluta de la actividad de sustancias radiactivas en el Instituto Federal de Fisica Aplicada

    Energy Technology Data Exchange (ETDEWEB)

    Weiss, H M [Physikalisch-Technische Bundesanstalt, Braunschweig (Germany)

    1960-06-15

    A short report is given about the routine methods of standardization of radionuclides. The measurements are done by 4 {pi} {beta} proportional counters, 4 {pi} {beta}-{gamma} coincidence counting and for secondary standardization of {gamma} emitters by 4 {pi} {gamma} ionization chamber. The equipments used and the procedures of source preparation are described. (author) [French] L'auteur presente un rapport succinct sur les methodes courantes de normalisation des radionuclides. Les mesures sont effectuees au moyen de compteurs proportionnels 4 {pi} {beta}, par voie de comptage par coincidences 4 {pi}{beta}-{gamma} et, en ce qui concerne la normalisation secondaire des emetteurs de rayons {gamma}, au moyen d'une chambre d'ionisation 4 {pi} {gamma}. Le memoire contient une description du materiel utilise et des procedes employes pour la preparation des sources. (author) [Spanish] En la memoria se describen brevemente los metodos corrientes de calibracion de radionuclidos. Las mediciones a que se refiere se han efectuado con contadores proporcionales {beta} 4 {pi}, contadores de coincidencias {beta}-{gamma} 4{pi}l; para la calibracion secundaria de emisores {gamma} se ha utilizado una camara de ionizacion {gamma} 4 {pi}. Se describen los aparatos empleados y los procedimientos de preparacion de las fuentes. (author) [Russian] Privoditsya kratkij doklad po obychnym metodam standartizatsi i radioizotopov. Izmereniya osushchestvlyalis {beta}-proportsional'nym i schetchikami na 4 {pi}, schetchikami {beta}-{gamma} sovpadenij i {gamma}-ioniziruyushche j kameroj na 4 i dlya vtorichnoj standartizatsi i {gamma}-izluchatelej . Privoditsya opisanie, ispol'zuemogo oborudovaniya i protsedura podgotovki istochnika. (author)

  4. 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

  5. CACAO facility. Radioactive targets at Orsay

    International Nuclear Information System (INIS)

    Bacri, C.O.; Petitbon-Thevenet, V.; Mottier, J.; Lefort, H.; Durnez, A.; Fortuna, F.

    2014-01-01

    CACAO, Chimie des Actinides et Cibles radioActives a Orsay (actinide chemistry and radioactive targets at Orsay), is a new laboratory dedicated to the fabrication and characterization of radioactive targets. It is supported by the radiochemistry group and the stable target service of the IPNO. The recurring needs of physicists working in the nuclear fuel cycle physics and the growing difficulties to obtain radioactive targets elsewhere were the main motivating factors behind the construction of this new laboratory. The first targets of 235,238 U and 232 Th have already been prepared although the full operating licenses still need to be obtained. In this paper, the installation and the equipment of CACAO will be described. An extensive study of a U test target fabricated by the CACAO laboratory has been performed and results are reported here. The different techniques used to characterize the deposit are presented and the outcome is discussed. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

  7. Analyse of the potential of the high temperature reactor with respect to the use of fissile materials; Analyse des capacites des reacteurs a haute temperature sous l'aspect de l'utilisation des matieres fissiles

    Energy Technology Data Exchange (ETDEWEB)

    Damian, F

    2001-07-01

    The high temperature reactors fuel is made of micro-particles dispersed in a graphite matrix. This configuration makes it possible to reach high burnup, higher than 700 GWj/t. Thanks to the decoupling between the thermal and the neutronic behaviors in the core many types of fuels can be used. These characteristics give to HTR reactor very good capacities to burn fissile materials. This work was done in the frame of the evaluation of HTR capacities to enhance the value of the plutonium stocks. These stocks are currently composed of the irradiated fuels discharged from classical PWR or the dismantling of the nuclear weapons and represent a significant energy potential. These studies concluded that high cycles length can be reached whatever the plutonium quality is (from 50 % to 94 % of fissile plutonium). In addition, it was demonstrated that the moderator temperature coefficient becomes locally positive for highly burn fuel while the core global moderator temperature coefficient remained negative in the operation range of the reactor. A significant share of this work was first devoted to the setting of a modeling of the fuel element but also of the reactor's core with the codes of system SAPHYR. The whole of modeling was validated by reference calculations. This work of code assessment is justified by a preliminary work that showed that the classical calculation scheme used for PWR could not be transposed directly to HTR core. (author)

  8. Analyse of the potential of the high temperature reactor with respect to the use of fissile materials; Analyse des capacites des reacteurs a haute temperature sous l'aspect de l'utilisation des matieres fissiles

    Energy Technology Data Exchange (ETDEWEB)

    Damian, F

    2001-07-01

    The high temperature reactors fuel is made of micro-particles dispersed in a graphite matrix. This configuration makes it possible to reach high burnup, higher than 700 GWj/t. Thanks to the decoupling between the thermal and the neutronic behaviors in the core many types of fuels can be used. These characteristics give to HTR reactor very good capacities to burn fissile materials. This work was done in the frame of the evaluation of HTR capacities to enhance the value of the plutonium stocks. These stocks are currently composed of the irradiated fuels discharged from classical PWR or the dismantling of the nuclear weapons and represent a significant energy potential. These studies concluded that high cycles length can be reached whatever the plutonium quality is (from 50 % to 94 % of fissile plutonium). In addition, it was demonstrated that the moderator temperature coefficient becomes locally positive for highly burn fuel while the core global moderator temperature coefficient remained negative in the operation range of the reactor. A significant share of this work was first devoted to the setting of a modeling of the fuel element but also of the reactor's core with the codes of system SAPHYR. The whole of modeling was validated by reference calculations. This work of code assessment is justified by a preliminary work that showed that the classical calculation scheme used for PWR could not be transposed directly to HTR core. (author)

  9. 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)

  10. 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.)

  11. A State-of-the-Art Review of Enhanced Personal Protection Equipment Options (Analyse de Pointe des Options en Matiere D’equipement de Protection Individuelle Accrue)

    Science.gov (United States)

    2007-03-01

    A-26 8 Deltoid Auxillary Protectors (DAPs).........................................................................................A-27 9...8 Deltoid and Auxillary Protectors (DAPs) for Interceptor Body Armor (IBA) Product Description: DAP consists of two ambidextrous modular

  12. In the field of energy cost reduction, what is the potential?; En matiere de reduction des depenses d`energie: quel est le gisement?

    Energy Technology Data Exchange (ETDEWEB)

    Millet, B. [Departement Industrie, CEREN (France)

    1996-12-31

    Through a segmentation of the fuel and electric power consumptions in the various industrial sectors and energy consumption process types in France in 1990, the energy conservation potential in the French metalworking and mechanical industry is analyzed and its evolution up to 2005 is assessed. It is shown that the reduction potential amounts to 450 kTep or 20 percent of the metalworking and metallic construction industry energy consumption, with an important part for the out-of-process sector (space heating, compressed air production, lighting). In the process sector, important reductions could be realized in thermal treatments and metal heating prior forming

  13. Annual report 2005 General Direction of the Energy and raw materials; Rapport annuel 2005 Direction Generale de L'Energie et des Matieres Premieres

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    This 2005 annual report of the DGEMP (General Direction of the Energy and the raw Materials), takes stock on the energy bill and accounting of the France. The first part presents the electric power, natural gas and raw materials market in France. The second part is devoted to the diversification of the energy resources with a special attention to the renewable energies and the nuclear energy. The third part discusses the energy and raw materials prices and the last part presents the international cooperation in the energy domain. (A.L.B.)

  14. What is Essential for Virtual Reality Systems to Meet Human Performance Goals? (les Caracteristiques essentielles des systemes VR pour atteindre les objectifs militaires en matiere de performances humaines)

    Science.gov (United States)

    2001-03-01

    training world will be digital cinema, the convergence of television with the World Wide Web, and the continued rapid growth of multiplayer Internet...innocent civilians from being hurt in factional violence while preventing, as much as possible, new flare ups among the factions. By sharing an immersive

  15. Annual report 2001. General direction of energy and raw materials; Rapport annuel 2001. Direction generale de l'energie et des matieres premieres

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    This report summarizes the 2001 activity of the French general direction of energy and raw materials (DGEMP) of the ministry of finances and industry: 1 - security of energy supplies: a recurrent problem; 2001, a transition year for nuclear energy worldwide; petroleum refining in font of the 2005 dead-line; the OPEC and the upset of the oil market; the pluri-annual planning of power production investments; renewable energies: a reconfirmed priority; 2 - the opening of markets: the opening of French electricity and gas markets; the international development of Electricite de France (EdF) and of Gaz de France (GdF); electricity and gas industries: first branch agreements; 3 - the present-day topics: 2001, the year of objective contracts; AREVA, the future to be prepared; the new IRSN; the agreements on climate and the energy policy; the mastery of domestic energy consumptions; the safety of hydroelectric dams; Technip-Coflexip: the birth of a para-petroleum industry giant; the cleansing of the mining activity in French Guyana; the future of workmen of Lorraine basin coal mines; 4 - 2001 at a glance: highlights; main legislative and regulatory texts; 5 - DGEMP: November 2001 reorganization and new organization chart; energy and raw materials publications; www.industrie.gouv.fr/energie. (J.S.)

  16. Influence of natural organic matter on the speciation of radionuclides in a geochemistry context; Influence de la matiere organique naturelle sur la speciation des radionucleides en contexte geochimique

    Energy Technology Data Exchange (ETDEWEB)

    Marang, L

    2007-09-15

    The principal aim of this work is the study of the influence of natural organic matter, in particularly humic substances (HS), on the speciation of radionuclides (RN). The studied radionuclides are cobalt (II), europium (III) and uranium (VI). It has been shown that mobility and bioavailability of a metal are related to its speciation. The NICA-Donnan model describes metal ion binding to NOM: it accounts for NOM chemical heterogeneity, competition during binding and ionic strength effects. However the model has been calibrated with a limited number of experimental data for the RN. Indeed there is only a few speciation technique available for the study of the interactions RN-HS. Within the framework of this study, we have developed and optimised speciation technique (Flux Donnan Membrane Technique and the use of an un-solubilized humic acid) in order to acquire new experimental data, we have also studied the effect of the competition on RN speciation and finally we have tested the model capacity to predict the RN behavior in laboratory or in situ. (author)

  17. Nuclear raw materials. Knowledge status after the Geneva conference (September 1958); Les matieres premieres nucleaires. Etat des connaissances apres la conference de Geneve (Septembre 1958)

    Energy Technology Data Exchange (ETDEWEB)

    Lecoq, M.; Mabile, J. [Direction des Recherches et Exploitations Minieres (France); Carrat, G. [Service Central des Recherches, Direction des Recherches et Exploitations Minieres (France); Ginocchio, A. [Service Central des Productions, Direction des Recherches et Exploitations Minieres (France); Roques, E. [Service Concentration, Direction des Recherches et Exploitations Minieres (France); Waynbaum, M. [Service Developpement et Programmes Generaux, Direction des Recherches et Exploitations Minieres (France); Chervet, J.; Branche, G.; Geffroy, J. [Service de Mineralogie, Centre d' Etudes Nucleaires de Fontenay-aux-Roses (France); Le Goff, M. [Secretariat technique de la Direction des Recherches et Exploitations Minieres (France)

    1959-05-15

    The authors propose a synthesis of the numerous contributions presented at the Geneva conference. They first address deposits: uranium deposits (studies on uranium geochemistry and metallogeny, descriptions of various deposit types such as those associated with sedimentary layers or tectonic structures or petrographic types), thorium deposits, beryllium deposits, zirconium deposits. A second part addresses research methods and equipment: descriptive mineralogical studies, analytic physical or chemical methods, analytic field methods, isotope analysis, prospecting methods (geochemical techniques, radiometry, geophysical methods, general remarks on prospecting methods, organization of prospecting operations, and techniques of deep prospecting). The third part addresses the issues of reserves and resources: definitions, assessment techniques, geographical distribution of reserves and resources. The fourth part addresses the exploitation: quarries, underground exploitation, measures for personnel protection. The fifth part addresses ore concentration: determination of uranium ore and other raw material, concentration by physical means, ore concentration by chemical means, ore sampling, and plant monitoring and regulation. The last part addresses the economy of raw materials: uranium (cost price and production, and purchase and selling prices in different countries, world market in 1960 and on a longer term), thorium, beryllium, zirconium, lithium and helium.

  18. Annual report 2001. General direction of energy and raw materials; Rapport annuel 2001. Direction generale de l'energie et des matieres premieres

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    This report summarizes the 2001 activity of the French general direction of energy and raw materials (DGEMP) of the ministry of finances and industry: 1 - security of energy supplies: a recurrent problem; 2001, a transition year for nuclear energy worldwide; petroleum refining in font of the 2005 dead-line; the OPEC and the upset of the oil market; the pluri-annual planning of power production investments; renewable energies: a reconfirmed priority; 2 - the opening of markets: the opening of French electricity and gas markets; the international development of Electricite de France (EdF) and of Gaz de France (GdF); electricity and gas industries: first branch agreements; 3 - the present-day topics: 2001, the year of objective contracts; AREVA, the future to be prepared; the new IRSN; the agreements on climate and the energy policy; the mastery of domestic energy consumptions; the safety of hydroelectric dams; Technip-Coflexip: the birth of a para-petroleum industry giant; the cleansing of the mining activity in French Guyana; the future of workmen of Lorraine basin coal mines; 4 - 2001 at a glance: highlights; main legislative and regulatory texts; 5 - DGEMP: November 2001 reorganization and new organization chart; energy and raw materials publications; www.industrie.gouv.fr/energie. (J.S.)

  19. A contribution to the physical and chemical model of long-lived radioactive wastes by clayey materials; Contribution a la modelisation physico-chimique de la retention de radioelements a vie longue par des materiaux argileux

    Energy Technology Data Exchange (ETDEWEB)

    Gorgeon, L

    1994-11-25

    This work deals with the high-level and long-lived radioactive wastes confinement which come from the irradiated fuels reprocessing. These wastes are generally coated in a deep geological structure confinement matrix. The radiation protection of a such storage requires that the coating matrix, the technological barriers which separate the storage and the geological medium and the reception rock does not let the radioactive wastes pass. The materials used in this work for the confinement studies are clayey minerals and the retention mechanisms studies are realized on cesium 135, neptunium 237, americium 241 and uranium 233. The first part of this thesis concerns the clayey minerals retention properties towards ions in aqueous solutions. More particularly the relations between these properties and the chemical structure of these solids are investigated. In the second part are presented the experimental works which have allowed to specify the intrinsic characteristics of the studied minerals. Indeed the knowledge of these parameters is essential to quantitatively explain the results of the radionuclides retention. The adsorption mechanisms are described in a third part. (O.L.). 112 refs., 59 figs., 51 tabs.

  20. 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.)

  1. Effects of Incorporated Radioactivity and External Radiation on Heterogeneous Catalysis; Effets de la radioactivite incorporee et des rayonnements externes sur la catalyse heterogene; Vliyanie vvedennoj radioaktivnosti i vneshnego oblucheniya na geterogennyj kataliz; Efectos de la radiactividad incorporada y de la irradiacion externa sobre la catalisis heterogenea

    Energy Technology Data Exchange (ETDEWEB)

    Krohn, N. A.; Wymer, R. G. [Oak Ridge National Laboratory, Oak Ridge and University of Tennessee, Knoxville, Tennessee (United States)

    1963-11-15

    The vapour phase dehydration of cyclohexanol on magnesium sulphate and magnesium sulphatesodium sulphate catalysts and the dehydrogenation of methylcyclohexane to toluene on promoted chromiaalumina catalysts were studied in flow systems. The effects of incorporating radioisotopes into the catalysts and of pre-irradiation with cobalt-60 gamma rays were investigated. Magnesium sulphate and magnesium sulphate-sodium sulphate catalysts containing up to 45.5 mc (S{sup 35})/g were less active than non-radioactive catalysts of similar composition when compared on a unit surface area basis. The reduction in catalytic activity persisted even after the radioactivity had substantially decayed. Further, no change in catalytic activity was observed upon irradiation with X-rays while the reaction was in progress. From these results it is concluded that the emission of beta particles from the catalyst during its use has no effect. Reports of an enhancement of catalytic activity may be attributed to the fact that,for a given set of preparation conditions, the radioactive catalysts have larger surface areas than their non-radioactive counterparts, and that this was not taken into account. Pre-irradiation with cobalt-60 gamma rays to 10{sup 11} erg/g had no effect on the catalysts' activity. In contrast, pre-irradiation of the chromia-alumina catalysts with cobalt-60 gamma rays to a dose of 4.2 x 10{sup 11} erg/g enhanced the catalytic activity by about 34% at 485{sup o}C, but incorporation of up to 148 mc (Pm{sup 147})/g of catalyst had little or no effect. No substantial effect of radiation on surface area or on apparent activation energy was observed in this case. (author) [French] Les auteurs ont etudie dans des circuits la deshydratation du cyclohexanol en phase vapeur en presence de catalyseurs au sulfate de magnesium et au sulfate double de magnesium et de sodium, et la transformation du methylcyclohexane toluene par deshydrogenation en presence de catalyseurs au Cr{sub 2}O

  2. 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

  3. Effect of high energy electrons on the skin and on the underlying tissues of the rabbit. A clinical and histological study; Effets des electrons de haute energie sur la peau et les tissus sous-jacents du lapin. Etude clinique et histologique

    Energy Technology Data Exchange (ETDEWEB)

    Legeay, G; Vialettes, H; Adnet, J J; Court, L; Masse, R [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1967-07-01

    The authors consider in this report the effects of high-energy electrons on rabbit teguments and on the underlying tissues after a single high dose irradiation. After briefly considering the mechanism of interaction between the electrons and matter as a function of their energy, the authors describe the dosimetry carried out, as a function of the irradiation device. The animal received surface doses of 5700 to 22100 rads in the thigh; the electron energy varied from 21 to 30 MeV. A clinical study was carried out over a period of nine months with a view to following the evolution of the damage and the functional degradation of the underlying tissues. A histological study of the induced damage was made after a second irradiation using 30 MeV electrons to produce doses of 16400 rads. Interesting observations were made concerning the damage caused to muscular and nerve tissues. (authors) [French] Les auteurs etudient, dans ce rapport, les effets des electrons de haute energie sur les teguments du lapin et les tissus sous-jacents apres une irradiation unique a dose elevee. Apres un rappel du mecanisme de l'interaction des electrons avec la matiere en fonction de leur energie, la dosimetrie realisee est exposee en fonction du dispositif d'irradiation. Les animaux ont recu, au niveau de la cuisse, des doses en surface de 5700 a 22100 rads; les energies des electrons vont de 21 a 30 MeV. Une etude clinique des lesions, observees pendant 9 mois, decrit leur evolution ainsi que les alterations fonctionnelles des tissus sous-jacents. Une etude histologique des lesions induites a ete realisee au cours d'une seconde experience pour des doses de 16400 rads avec des electrons de 30 MeV. D'interessantes observations ont ete faites concernant les lesions des tissus musculaires et nerveux. (auteurs)

  4. Modelling of thermo-hydro-mechanical couplings and damage of viscoplastic rocks in the context of radioactive waste storage; Modelisation des couplages thermo-hydro-mecaniques et de l'endommagement des roches viscoplastiques dans le contexte du stockage de dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Kharkhour, H

    2002-12-01

    Trying to develop a model taking into account the complex rheology of a geologic media characterized by visco-plasticity, damage and thermo-hydro-mechanical couplings is unusual in geotechnics. This is not the case for radioactive waste storage that presents specificities from several viewpoints. Indeed, the scales of time and space concerned by this type of storage are disproportionate to those of civil engineering works or mines. Another specificity of the radioactive waste storage lies in the coupled processes involved. No effect likely to compromise the long-term security of the storage could be ignored. For example this is the case of damage, a phenomenon which does not necessarily lead to a major change of the mechanical behavior of the works but can influence the permeability of the medium in relation with a migration of radionuclides. It can be conceived that this phenomenon finds all its importance in the context of the thermo-hydro-mechanical couplings of a waste storage with high activity. However, the interaction between the damage and the THM coupled processes was the object of very few research subject up to now. This. is even more true for viscoplastic media considered as ductile, and therefore, less prone to cracking than brittle media. It is exactly in this 'original' but difficult context that took place the research presented in this report. This study was dedicated to the analysis of the phenomena and the thermal, hydraulic and mechanical couplings occurring in the near and far field of a high activity radioactive waste storage. Two examples of geological media were considered in this report: the clayey rock of Callovo-Oxfordian, called ' Argilites de l'Est ', target rock of the ANDRA project to carry out a subterranean laboratory for the study of long life radioactive waste storage; and the salt rock of the. subterranean laboratory in the old salt mine of Asse in Germany. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2004-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1962-07-01

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

  7. Computerized simulation of the mechanical behavior of wood-filled shock absorbers of radioactive materials transport casks; Rechnerische Simulation des mechanischen Verhaltens von holzgefuellten Stossdaempfern von Transportbehaeltern fuer radioaktive Stoffe

    Energy Technology Data Exchange (ETDEWEB)

    Neumann, Martin; Wille, Frank [Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin (Germany)

    2011-07-01

    In Germany the mechanical component inspection of transport containers for radioactive materials is performed by BAM (Bundesanstalt fuer Materialforschung und -pruefung) under consideration of national and international standards and guidelines. Experimental and calculative (analytical and numerical) techniques combined with material and/or component testing are the basis of assessment concepts according the state of the art. The authors describe the experiences of BAM concerning assessment and description of the mechanical behavior of shock absorbing components, including modeling strategies, material models, drop tests and experiment-calculation comparison. Energy absorbing components are used to reduce the impact forces at the container in case of a transport accident. In Germany wood filled thin-walled constructions are used. The deformation behavior of the wood is a main part of the calculative simulation procedures in comparison with experimental tests.

  8. The PHREEQC modeling of CO{sub 2} transport in highly saline solutions of a final radioactive waste repository; PHREEQC. Modellierung des Transportes von CO{sub 2} in hochsalinaren Loesungen eines Endlagers

    Energy Technology Data Exchange (ETDEWEB)

    Weyand, Torben [Bonn Univ. (Germany); Gesellschaft fuer Reaktorsicherheit mbH (GRS), Koeln (Germany); Bracke, Guido [Gesellschaft fuer Reaktorsicherheit mbH (GRS), Koeln (Germany); Reichert, Barbara [Bonn Univ. (Germany)

    2014-03-15

    The safe confinement of radioactive materials in the containment providing zone of the host rock (CPRZ) over a period of one million years is required for a final repository for highly radioactive heat-generating waste (BMU 2010). In order to assess the safe containment of radionuclides in the CPRZ a sound understanding of the ongoing processes in a repository is necessary. These processes include the transport and chemical interactions of the radionuclide {sup 14}C in the gas phase and in highly saline solutions in a final repository for radioactive waste. The geochemical code PHREEQC /PAR 13/ was used to study the chemical interactions of CO{sub 2} and {sup 14}C as {sup 14}CO{sub 2} during transport in the gas phase and highly saline solutions. The model and scenario was based on the concept for a repository in Gorleben /BOL 11/. A gas generation of CO{sub 2} containing {sup 14}C was assumed since the disposed containers with the radioactive waste corrode /LAR 13/. The advective transport is triggered by gas generation. The physical dissolution of CO{sub 2}, chemical equilibria with aquatic carbon-containing species (e. g. HCO{sub 3}{sup -}(aq), CO{sub 3}{sup 2-}(aq)) and solid phases (e. g. magnesite, MgCO{sub 3}) coupled with transport were modelled. Due to the addition of dissolved MgCl{sub 2} in the crushed salt backfill of the main drift the aquatic species MgCO{sub 3}(aq) and the mineral MgCO{sub 3}(s) is formed. The influence of CO{sub 2} partial pressure and the chemical interactions in the presence of dissolved Fe{sup 2+}, Ca{sup 2+}, Mg{sup 2+} and K{sup +} were studied. Due to the physical solution, the CO{sub 2} partial pressure has a major influence on the transport of {sup 14}C. In the presence of calcium CaCO{sub 3}(aq), the minerals calcite (CaCO{sub 3}(s)) and dolomite (MgCa(CO{sub 3}){sub 2}(s)) were formed in the highly saline solutions. No siderite (FeCO{sub 3}) in the presence of Fe{sup 2+} was formed. The transport of {sup 14}C was delayed

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

    Energy Technology Data Exchange (ETDEWEB)

    Zokimila, P

    2005-10-15

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

  10. 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)

  11. 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).

  12. 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.

  13. Investigation of the behaviour of impact limiting devices of transport casks for radioactive materials in the package approval and risk analysis; Untersuchung des Verhaltens stossdaempfender Bauteile von Transportbehaeltern fuer radioaktive Stoffe in Bauartpruefung und Risikoanalyse

    Energy Technology Data Exchange (ETDEWEB)

    Neumann, Martin

    2009-08-20

    Transport casks for radioactive materials with a Type-B package certificate have to ensure that even under severe accident scenarios the radioactive content remains safely enclosed, in an undercritical arrangement and that ionising radiation is sufficiently shielded. The impact limiter absorbs in an accident scenario the major part of the impact energy and reduces the maximum force applied on the cask body. Therefore the simulation of the behaviour of impact limiting devices of transport casks for nuclear material is of great interest for the design assessment in the package approval as well as for risk analysis in the field of transport of radioactive materials. The behaviour of the impact limiter is influenced by a number of parameters like impact limiter construction, material properties and loading conditions. Uncertainties exist for the application of simplified numerical tools for calculations of impact limiting devices. Uncertainities exist when applying simplified numerical tools. A model describing the compression of wood in axial direction of wood under large deformations for simulation with complex numerical procedures like dynamic Finite Element Methods has not been developed yet. Therefore this thesis concentrates on deriving a physical model for the behaviour of wood and analysing the applicability of different modeling techniques. A model describing the compression of wood in axial direction under large deformations was developed on the basis of an analysis of impact limiter of prototypes of casks for radioactive materials after a 9-m-drop-test and impact tests with wooden specimens. The model describes the softening, which wood under large deformation exhibits, as a function of the lateral strain constraint. The larger the lateral strain restriction, the more energy wood can absorb. The energy absorption capacity of impact limiter depends therefore on the ability of the outer steel sheet structure to prevent wood from evading from the main

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

  15. 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)

  16. 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)

  17. 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

  18. 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)

  19. Comparative Studies of Chemical Effects following Nuclear Reactions and Transformations on Metal Organic Phenyl Compounds; Etudes Comparatives des Effets Chimiques Induits par les Reactions et les Transformations Nucleaires sur des Composes Phenylmetalliques; 0421 0420 0410 0414 ; Estudios Comparativos de los Efectos Quimicos de las Reacciones y Transformaciones Nucleares en Compuestos Fenil-Organometalicos

    Energy Technology Data Exchange (ETDEWEB)

    Merz, E.; Riedel, H. J. [Kernforschungsanlage, Juelich, Federal Republic of Germany (Germany)

    1965-04-15

    concerne non seulement la categorie de produits typiques, mais aussi les rendements en pourcentage. Ainsi, les auteurs ont trouve, apres les reactions nucleaires sur le tetraphenylgermanium, plusieurs produits de recul de Ge et de Ga a caractere organometallique qu'il n'etait pas possible de deceler apres le processus de capture K dans le tetraphenylgermanium-{sup 68}Ge. La decroissance {beta}{sup -} dans le tetraphenylgermanium-{sup 77}Ge produit pratiquement les memes composes chimiques que ceux que l'on observe a la suite des reactions nucleaires. Toutefois, une augmentation notable de la fraction molecules generatrices marquees (retention) est typique de la transition {beta}{sup -}. Les resultats sont etudies a la lumiere de considerations theoriques sur la quantite d'energie cinetique transferee par le recul nucleaire a la molecule en reaction et l'excitation qui en resulte. Les auteurs emettent l'hypothese que le genre et la quantite de certaines nouvelles especes radioactives produites lors des evenements nucleaires sont fonction moins de la nature et de la concentration des fragments de recul primaires que des ions, des radicaux et des defauts de reseau induits dans les matieres irradiees par les effets de recul secondaires (interactions elastiques et inelastiques) , y compris l'influence particuliere de l'oxygene. (author) [Spanish] Los autores estudiaron los efectos quimicos producidos por atomos de retroceso de gran energia procedentes de reacciones nucleares en solidos y liquidos basandose en una amplia comparacion de los productos formados por los procesos (n, {gamma}) y (n,2n) en los compuestos fenilmetalicos de germanio, estano, cobre, arsenico y antimonio. Ademas, compararon los productos radiactivos de retroceso formados como consecuencia de los procesos de captura K en {sup 68}Ge-tetrafenilo con los resultados obtenidos mediante el proceso (n, {gamma}) en Ga-trifenilo y el proceso (n,p) en Ge-tetrafenilo. Por ultimo, estudiaron tambien la transicion {beta

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1962-01-15

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

  1. Control panel for radiation around reactors (1963); Tableaux de controle des radiations aupres des piles (1963)

    Energy Technology Data Exchange (ETDEWEB)

    Candes, P; Barthoux, A [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1964-07-01

    This report outlines the general philosophy of radiation control in French reactors and their annexes. The supervision is carried out continuously from a central control panel on which appear all the measurements made and the alarm signals. The equipment is described; one item makes it possible to measure simultaneously the radioactive dusts and gases. The specifications of the alarm system, which is considered to be the most important are given. Finally a new measuring technique is proposed which makes it possible to reduce considerably the cost of radiation control while at the same time providing the results in a form in which they can be easily treated, in particular in the case of the calculation of total doses. (authors) [French] Ce rapport definit la philosophie generale du controle des radiations dans les piles francaises et dans leurs annexes. La surveillance se fait d'une maniere continue a partir d'un tableau de controle centralise ou sont reportees toutes les mesures et les signalisations d'alarme. On decrit les appareils utilises, dont un permet la mesure simultanee des poussieres et gaz radioactifs, et on definit les specifications de la fonction alarme qui est consideree comme la plus importante. Enfin on propose une nouvelle technique de mesure qui permettrait de reduire considerablement le cout du controle des radiations tout en fournissant des resultats plus facilement exploitables, en particulier pour le calcul des doses integrees. (auteurs)

  2. Des Connaissances Aux Politiques

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

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

  3. Contribution to the study of the evaporation of aqueous uranyl nitrate solutions; Contribution a l'etude de l'evaporation des solutions aqueuses de nitrate d'uranyle

    Energy Technology Data Exchange (ETDEWEB)

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

    1967-05-15

    This work was carried out with a view to define the conditions under which is affected the concentration of aqueous uranyl nitrate solutions one of the steps in uranium extraction metallurgy. The first port is devoted to the experimental determination of the physical characteristics of aqueous uranyl nitrate solutions, from dilute to concentrated solutions. The second part of this work is devoted to the isothermal evaporation of solution a west ted-wall column; this chemical engineering study has been more particularly devoted to the definition of the influence of the dynamics of the liquid phase on the exchange of matter between the two phases in contact. (author) [French] La concentration par evaporation des solutions aqueuses de nitrate d'uranyle constitue une etape de la metallurgie de l'uranium dont ce travail a voulu preciser la connaissance. Dans ce but, une premiere partie a ete consacree a la determination experimentale de caracteristiques physiques des solutions aqueuses de nitrate d'uranyle, des solutions diluees aux solutions saturees. Dans une deuxieme partie, ce travail a porte sur l'evaporation isotherme des solutions dans une colonne a paroi mouillee; cette etude de genie chimique a ete plus particulierement orientee de facon a preciser l'influence de la dynamique de la phase liquide sur l'echange de matiere entre les deux phases en contact. (auteur)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-02-15

    'isolement du cesium-137 et du strontium-90 avec un facteur de decontamination d'au moins 10{sup 4}, ce qui permettrait d'envisager le rejet, apres un traitement d'effluents classique, au bout d'une periode de 10 a 20 ans. Le but du memoire est de faire le point de cette question en l'annee 1962. Les progres realises dans les methodes de separation du cesium et du strontium permettent d'envisager l'obtention de ce facteur 10{sup 4} dans des conditions exploitables industriellement. Des methodes pleines de promesses sont: a) Pour le cesium-137, la precipitation par l'acide phosphotungstique, l'echange sur un sel d'ammonium d'un heteropolyacide, la fixation par un phosphate de zirconium. b) Pour le strontium-90, la precipitation d'oxalate, l'extraction par l'acide di-2-ethyl-hexylphosphorique, l'echange sur des sels varies, sulfate de strontium, etc. Ces progres chimiques sont renforces par les progres realises dans le traitement industriel des effluents et permettent de considerer comme techniquement possible la solution preconisee par Glueckauf. Parallelement, le developpement de l'utilisation de grandes quantites de produits de fission, particulierement dans les programmes SNAP, justifie des investissements qui seront au moins pairtiellement recuperes par la vente des produits fabriques. Il est certain que des sources refractaires, a resistance tres elevee a tous les agents d'agression exterieurs, constituent le mode de stockage le plus satisfaisant pour des produits aussi dangereux et d'aussi longue periode. L'auteur considere done, techniquement et psychologiquement, Inverted-Exclamation-Mark /utilisation de sources concentrees a gainage riche comme le moyen de stockage presentant le plus de garanties. Une discussion comparative de cette methode avec la methode d'incorporation dans les verres meriterait un examen complet et approfondi. (author) [Spanish] En la Conferencia de Ginebra de 1955, Glueckauf formplo la hipotesis de que los problemas planteados por las soluciones de

  5. Detection de la fin de la compaction des anodes par le son

    Science.gov (United States)

    Sanogo, Bazoumana

    L'objectif de ce projet etait de developper un outil de controle en temps reel du temps de compaction en se servant du son genere par le vibrocompacteur pendant le formage des anodes crues. Ainsi, une application a ete developpee pour l'analyse des sons enregistres. Des essais ont ete realises avec differents microphones pour une meilleure qualite des mesures et un a ete choisi pour la suite du projet. De meme, differents tests ont ete realises sur des anodes de laboratoire ainsi que des anodes a l'echelle industrielle afin de mettre en place une methode pour la detection du temps optimal necessaire au formage des anodes. Les travaux au laboratoire de carbone a l'Universite du Quebec a Chicoutimi (UQAC) ont consiste a l'enregistrement de son des anodes fabriquees sur place avec differentes configurations; et a la caracterisation de certaines anodes de l'usine. Les anodes fabriquees au laboratoire sont reparties en deux groupes. Le premier regroupe les anodes pour la validation de notre methode. Ce sont des anodes produites avec des temps de compaction differents. Le laboratoire de carbone a l'UQAC est unique et il est possible de produire des anodes avec les memes proprietes que celles des anodes industrielles. Par consequent, la validation initialement prevue a l'usine a ete effectuee avec les anodes de laboratoire. Le deuxieme groupe a servi a etudier les effets des matieres premieres sur le temps de compaction. Le type de coke et le type de brai ont constitue les differentes variations dans ce deuxieme groupe. Quant aux tests et mesures a l'usine, ils ont ete realises en trois campagnes de mesure. La premiere campagne en juin 2014 a servi a standardiser et a trouver le meilleur positionnement des appareils pour les mesures, a regler le logiciel et a faire les premieres mesures. Une deuxieme campagne en mai 2015 a fait l'objet d'enregistrement de son en classant les anodes selon differents temps de compaction. La troisieme et derniere campagne en decembre 2015 a

  6. Study of identification of AIJ/RPTES sites and the prospects for vulgarization of the solar energy systems in the Boucle du Mouhoun; Etude d'identification de sites AIJ/ RPTES et des perspectives de diffusion des systemes d'energie solaire dans la Boucle du Mouhoun

    Energy Technology Data Exchange (ETDEWEB)

    Zougouri, Aboubacar; Ouedraogo, Mariam; Sawadogo, Xavier

    2000-04-15

    The energy needs of the populations in Burkina Faso are enormous and it is difficult to satisfy. The main source of energy is the heating wood. The demand for wood of heating is increasingly strong involves the environment degradation. Thus the Regional Program in the Traditional energy sector (RPTES) takes place to fight against deforestation and to promote the use of other energy sources such as photovoltaic solar systems and petroleum. The aim of this study is to determine the needs of the households, of the groupings and associations and of the institutions in energy. It is a question of determining the adequate strategy to promote the photovoltaic solar systems in rural environment in order to meet the requirements in Community lighting, lighting and conservation of the drugs in the health centres and in leisure. [French] Les besoins energetiques des populations au Burkina Faso sont enormes et difficile a satisfaire. La principale source d'energie demeure le bois de chauffe. La demande en bois de chauffe est de plus en plus forte entraine la degradation de la nature. C'est ainsi que le Programme Regional dans le secteur des Energies Traditionnelles (RPTES) intervient pour lutter contre la deforestation et promouvoir l'utilisation d'autres sources d'energie telles les systemes solaires photovoltaiques et le petrole. Cette etude vise a determiner la demande des menages, des groupements et associations ainsi que celle des institutions en matiere d'energie. Il s'agit de determiner la strategie adequate pour promouvoir les systemes solaires photovoltaiques en milieu rural afin de repondre aux besoins en eclairage communautaire, en eclairage et conservation des medicaments dans les centres de sante et en loisirs.

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

    African Journals Online (AJOL)

    SARAH

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2008-04-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

    M' garrech, Slah

    2004-09-01

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

  10. Total Counting and Spectroscopy in the Assessment of Alpha Radioactivity in Human Tissues; Determination de la Radioactivite Alpha des Tissus Humains par Dosage de l'Activite Globale et Spectroscopie; Obshchee izmerenie i spektroskopiya pri opredelenii al'fa-radioaktivnosti tkanej cheloveka; Evaluacion de la Actividad Alfa en los Tejidos Humanos por Recuento Global y Espectroscopia

    Energy Technology Data Exchange (ETDEWEB)

    Mayneord, W. V.; Hill, C. R. [Physics Department, Institute of Cancer Research, Royal Cancer Hospital, Clifton Avenue, Belmont, Surrey (United Kingdom)

    1964-10-15

    A seven-year programme of measurements of alpha radioactivity is briefly reviewed. The programme which was based initially on a sensitive and simple counting technique, using thin zinc cadmium sulphide screens, now employs in addition techniques of alpha spectroscopy developed for work with very large area low-specific-activity sources. These techniques are capable of measuring specific activities down to 10{sup -13} c/g and can in certain cases provide energy resolution of the order of 40 keV together with independent identification based on half-life measurements. Two alpha spectrometers are described which have been used on a wide variety of human and environmental materials. Particular attention has been given to the study of Po{sup 210}, now known to be present in a variety of foods and human tissues. Techniques are also described for the study of Pu{sup 239} in the atmosphere and examples given of .the results of measurements of low-level air contamination with this material. Techniques for the measurement of Pu{sup 239} in normal human tissues are described and some results given. Consideration is given to the contribution made by Po{sup 210} to the natural background radiation dose-rate in human bone and reproductive organs. It is shown that this contribution may be a significant fraction of the total dose received. (author) [French] L'auteur fait brievement le point de l'execution d'un programme septennal de mesures de la radioactivite alpha. Au debut, on procedait seulement a un dosage simple et sensible au moyen d'ecrans minces de sulfure de cadmium et de zinc; maintenant, ce procede est complete par l'emploi de methodes de spectroscopie alpha qui ont ete mises au point a l'occasion de travaux sur des sources a faible activite specifique et a tres grande surface. Ces methodes permettent de mesurer des activites specifiques aussi faibles que 10{sup -13} c/g, d'obtenir, dans certains cas, une resolution en energie de l'ordre de 40 keV et, independamment, d

  11. 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

  12. Optimization of fuel cycles: marginal loss values; Optimisation des cycles de combustibles: valeurs marginales des pertes

    Energy Technology Data Exchange (ETDEWEB)

    Gaussens, J. [Commissariat a l' Energie Atomique, 75 - Paris (France); Lasteyrie, B. de; Doumerc, J. [Compagnie pour l' Etude et la Realisation de Combustibles Atomiques, 75 - Paris (France)

    1965-07-01

    'uranium doit etre consideree comme definitivement perdue, alors que le reste pourrait etre recupere et recycle. Le cout eleve des pertes, recyclees ou non, d'autant plus eleve que l'uranium est plus enrichi, exige qu'il en soit tenu compte dans l'optimisation generale des cycles de combustible. Il importe donc de determiner leur niveau le plus souhaitable economiquement, aux diverses etapes d'elaboration du combustible nucleaire. Mais en France et dans d'autres pays, la production de matieres fissiles est geree par l'Etat, tandis que la fabrication de l'element combustible est effectuee par l'industrie privee. Les criteres d'optimisation et l'interet economique accorde aux pertes sont donc differents pour les deux parties de la chaine de fabrication. Pour tenter neanmoins d'atteindre un optimum conforme a l'interet collectif sans intervenir dans la politique de prix de l'entreprise, on peut utiliser la propriete des couts marginaux d'etre egaux entre eux a l'optimum, pour un volume de production donne. On peut donc ajuster le niveau des pertes pour realiser cette egalite des couts marginaux dont le calcul est plus facile a obtenir de la firme que la justification des prix eux-memes. On s'apercoit d'ailleurs que, bien qu'axee essentiellement sur les pertes, cette analyse globale peut conduire a une meilleure utilisation d'autres facteurs de production. On donne un expose theorique et des exemples pratiques de cette methode d'optimisation economique dans le cadre de la fabrication d'elements combustibles destines a des reacteurs du type: uranium naturel, moderes au graphite et refroidis par le gaz carbonique. (auteurs)

  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. Gestion des risques

    CERN Document Server

    Louisot, Jean-Paul

    2009-01-01

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

  15. Distribution and removal of transuranic elements and cerium deposited by the inhalation route; Distribution et elimination des transuraniens et du cerium deposes par l'intermediaire des voies respiratoires; Raspredelenie transuranovykh ehlementov i tseriya, otkladyvayushchikhsya v rezul'tate vdykhaniya i ikh udalenie; Distribucion y eliminacion de elementos transuranicos y de cerio depositados por inhalacion

    Energy Technology Data Exchange (ETDEWEB)

    Bair, W. J.; Tombropoulos, E. G.; Park, J. F. [Hanford Atomic Products Operation, General Electric Company, Richland, WA (United States)

    1963-02-15

    Tissue distribution and excretion of inhaled radioactive isotopes varied with the chemical form and the particle size of the aerosols. In dogs, 30 d after inhalation of plutonium nitrate, 70% of the body burden was in the lungs, 10% in liver, and 15% in the skeleton. After inhalation of P{sup 239} O{sub 2} aerosols with a Count Median Diameter (CMD) of 0.12{mu}m, 71% of the body burden was in the lungs, 3% in the bronchial lymph nodes, 4.4% in muscle, 1.3% in skeleton, and 20% was uniformly distributed throughout all remaining tissues. After inhalation of P{sup 239} O{sub 2} aerosols with CMD's of 0.3 to 0.6 {mu}m; the lungs contained 98%, the bronchial lymph nodes about 1% and all other tissues the remaining one per cent. These data and the analysis of urine and faeces defined the relative importance of the three routes by which inhaled radioactive isotopes were cleared from the lung, e.g. movement up the trachea by ciliary action followed by excretion in the faeces, transport across the alveolar membrane and redistribution in other tissue with gradual excretion in urine and transport to the bronchial lymph nodes which accumulate inhaled insoluble materials. Therapy agents were tested that would be expected to increase the clearance of radioactive isotopes from the lung by routes which would avoid accumulation in other, perhaps more radiosensitive tissues. These include chelating agents, wetting agents, irritants, sympathomimetic, parasympathomimetic, parasympatholytic and antihistamine drugs. Diethylenetriamine-pentaacetic acid (DTPA), a chelating agent, administered by aerosols or intraperitoneally caused rapid transport of Ce{sup 144} -Pr{sup 144} from the lung and from the body via urinary excretion. One month after exposure to Ce{sup 144} O{sub 2} treated rats and dogs retained less than 10% of the Ce{sup 144} -Pr{sup 144} levels of untreated animals. (author) [French] La distribution dans les tissus et l'excretion des radioisotopes inhales varient selon la

  16. 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

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

    African Journals Online (AJOL)

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

  18. 2002 summary of the report on studies and activities. Research on the Disposal of High-level Long-lived Radioactive Wastes; 2002 synthese du bilan des etudes et travaux. Recherches pour le stockage des dechets radioactifs haute activite et a vie longue

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-01-01

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

  19. 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)

  20. 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

  1. Photonique des Morphos

    CERN Document Server

    Berthier, Serge

    2010-01-01

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

  2. Droit des organisations internationales

    CERN Document Server

    Sorel, Jean-Marc; Ndior, Valère

    2013-01-01

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

  3. 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.

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-10-26

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

  5. Study of reactions of metals with sulphur and phosphorus compounds by pulsed temperatures; Etude des reactions entre metaux et composes du soufre et du phosphore au moyen de brusques hausses de temperature; Issledovanie reaktsii metallov s soedineniyami sery i fosfora pri regulyarnykh izmeneniyakh temperatury; Estudio de reacciones entre metales y compuestos de azufre y de fosforo empleando impulsos de temperatura

    Energy Technology Data Exchange (ETDEWEB)

    Campbell, R B; Grunberg, L [National Engineering Laboratory, East Kilbride, Glasgow (United Kingdom)

    1962-01-15

    The anti-wear action of sulphur and phosphorus compounds which are usually added to gear-oils depends on chemical reactions with the metallic surfaces of the gears. These reactions occur both at the bulk oil temperature (approx. 100 Degree-Sign C) and during high temperatures (approx. 600 Degree-Sign C) of short duration when the gearteeth come into contact under lead. The temperature flashes were simulated in an apparatus in which short pulses of electric current were used to heat metal wires immersed in mineral oil containing S{sup 35} and P{sup 32} labelled compounds in solution. The radioactivity acquired by the wires was measured. The extent of the reactions was determined as a function of temperature and time and the results were interpreted in terms of conventional kinetic laws. The modification of the reaction rates by the presence of other compounds in the solution was studied. The effect of pre-formed surface films containing sulphur phosphorus, chlorine and/or oxygen was also determined. In explaining the results, the structure of the materials used and the diffusion processes whereby the reactions occur beyond the initial stages were considered. (author) [French] Les composes du soufre et du phosphore que l'on ajoute souvent aux huiles de graissage offrent une protection contre l'usure, mais cette protection depend des reactions chimiques avec les surfaces metalliques des engrenages. Ces reactions ont lieu aussi bien a la temperature de la masse de l'huile (environ 100 Degree-Sign C) qu'au moment des brusques hausses de temperature (environ 600 Degree-Sign C) qui se produisent lorsque les dents d'engrenage viennent en contact avec pression. Les chocs thermiques ont ete simules dans un appareil a l'interieur duquel on a produit de breves impulsions de courant electrique pour chauffer des fils metalliques immerges dans une huile minerale contenant des composes marques au soufre-35 et au phosphore-32 en solution. Les auteurs ont mesure la radioactivite

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

    African Journals Online (AJOL)

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

  7. An Idea on the Maximum Permissible Concentrations of Radioactive Materials in Sea Water; Concentrations Maxima Admissibles des Substances Radioactives dans l'Eau de Mer; 041e 041c 0414 ; Concentracion Maxima Admisible de Materiales Radiactivos en las Aguas del Mar

    Energy Technology Data Exchange (ETDEWEB)

    Hiyama, Yoshio [University of Tokyo (Japan)

    1960-07-01

    The author of the present paper has tried to find a relationship between the level of sea-water contamination by several radionuclides and the level of the radiation dose-rate inside the human body caused by these radionuclides of marine origin, using the ICRP recommendation and the few data on the chemical analysis of sea water and of the human body at present available to the author. However, even if the idea of this calculation were to be recognized by scientists in the fields of oceanography, public health, nutrition, radiation biology, and others, it would still be necessary to get further data on the amounts of trace elements in sea-water, in marine products, and in the human body in order to complete a table of the maximum permissible concentrations in sea-water of various radionuclides. Here the idea is merely advanced and a few examples are described. (author) [French] L'auteur a cherche a etablir un rapport entre le degre de contamination de l'eau de mer par plusieurs radionuclides et le degre d'irradiation de l'interieur du corps humain due a ces radionuclides d'origine marine; a cet effet, il s'est fonde sur les recommandations de la CIPR et sur les quelques donnees relatives a l'analyse chimique de l'eau de mer et du corps humain qu'il avait a sa disposition. Cependant, meme si le principe de ce calcul etait reconnu par les oceanographes, les hygienistes, les bromatologistes, les radiobiologistes et d'autres specialistes, il n'en serait pas moins necessaire d'obtenir des renseignements supplementaires sur les quantites d'oligoelements existant dans l'eau de mer, les produits de la mer et le corps humain, en vue de dresser un tableau complet des concentrations maxima admissibles de divers radionuclides dans l'eau de mer. L'auteur se borne a formuler le concept et a donner quelques exemples. (author) [Spanish] El autor, teniendo en cuenta la recomendacion de la Comision Internacional de Proteccion Radiologica y los pocos datos de que actualmente dispone

  8. Dental Encounter System (DES)

    Data.gov (United States)

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

  9. Diethylstilbestrol (DES) and Cancer

    Science.gov (United States)

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

  10. Table des illustrations

    OpenAIRE

    2016-01-01

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

  11. Direction des Publications

    African Journals Online (AJOL)

    Synthese

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

  12. 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.)

  13. Planning of decontamination and bleaching of textiles in an industrial cycle; Programmation des operations de decontamination et de blanchissage du linge dans un cycle industriel

    Energy Technology Data Exchange (ETDEWEB)

    Boutot, Pierre; Schipfer, Pierre [Commissariat a l' energie atomique et aux energies alternatives - CEA, Centre de Production de Plutonium de Marcoule, Service de Protection contre les Radiations (France)

    1964-10-15

    This note describes the operational planning for the decontamination and bleaching of textiles (clothes, protections, etc.) worn by personnel, in industrial-type washing machines. Various tests have been conducted with contaminated cotton samples using different cleaning products (and quantities) and various temperature cycles. The performance of the washing cycle (soaking, pre-washing, washing, rinsing) is discussed in terms of decontamination and washing efficiency, textile wear and resistance to shrinkage, whiteness, etc. The experimental washing machine is described [French] Cette etude programme les operations de decontamination et de blanchissage du linge au sein d'un cycle de traitement tel qu'il apparait dans les machines a laver industrielles a fort indice de production. Les echantillons de cotonnade, contamines au moyen de produits de fission, sont de meme nature que le tissu des vetements de protection. En matiere de decontamination les meilleurs resultats sont obtenus apres un trempage faiblement acide et un prelavage au moyen d'un sequestrant. Dans le cadre du blanchissage, seule une lessive industrielle employee dans la phase de lavage peut conferer aux tissus la luminance que requiert leur bonne presentation. Les taches persistantes sont effacees par blanchiment au cours du rincage tiede. Une analyse terminale permet de constater que l'usure des vetements est davantage liee aux conditions d'utilisation qu'aux operations de lavage et de decontamination. (auteurs)

  14. Contribution to the study of the behaviour of silicon planar transistors exposed to the {sup 60}Co {gamma} rays; Contribution a l'etude du comportement des transistors silicium a structure plane soumis aux rayons {gamma} du {sup 60}Co

    Energy Technology Data Exchange (ETDEWEB)

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

    1967-05-15

    This report gives an account of studies carried out on bipolar silicon planar transistors irradiated by {sup 60}Co {gamma} rays. The author describes the interactions on the matter of the different types of particles and he gives a brief bibliographical recall of foreign studies. The technological structure of the planar transistors is then described in order to help the understanding of the phenomena, general comments are made about the choice of measured parameters and on the statistical interpretation of results. An automatic instrument for the measurement of the gain is described and the reproducibility of the results is stated The complexity of the problem and the difficulty to predict the behaviour of the semiconductors components are clearly shown. It is stated that the observed dispersions depend on: - the electrical bias during irradiation - the injection level in the emitter-base junction during the measurement - the manufacturer for a given type - the instantaneous dose rate - the geometry used The problem is then examined from the reliability point of view and methods are given to evaluate the reliability for a given dose - 'Worst case' method - moment method - Monte Carlo method. (author) [French] Ce rapport rend compte du travail effectue sur les transistors bipolaires au silicium irradies au rayons {gamma} du cobalt 60. On passe en revue les mecanismes d'interaction des differents rayonnements avec la matiere et on fait un bref rappel bibliographique des etudes effectuees a l'etranger. On decrit ensuite la structure technologique du transistor pour aider a la comprehension des phenomenes, puis on donne des generalites sur le choix des parametres mesures et l'interpretation statistique des resultats. On decrit l'ensemble du systeme de mesure de gain et on s'attache a montrer la reproductibilite des mesures. Les resultats experimentaux mentionnes etablissent clairement la complexite du probleme et la difficulte qu'il y a de faire des previsions. On

  15. European Program 'EVEREST'. Evaluation of the elements producing the effective doses associated to a radioactive waste disposal in deep underground geological formations. Comparative study of the results obtained by IPSN concerning the sedimentary and granite formations; Programme europeen 'EVEREST'. Evaluation des elements responsables des doses efficaces associees a un stockage de dechets radioactifs en formations geologiques profondes. Etude comparative des resultats obtenus par l'IPSN concernant les formations sedimentaire et granitique

    Energy Technology Data Exchange (ETDEWEB)

    Baudoin, Patrick; Serres, Christophe; Certes Catherine [Departement d' evaluation de surete, Inst. de Protection et de Surete Nucleaire, CEA Centre d' Etudes de Fontenay-aux-Roses, 92 (France)

    1996-09-01

    The European exercise EVEREST that was run from 1991 to 1995 was a means of training for IPSN, having in view the expertise studies of ANDRA on the safety of radioactive waste geological disposal. The exercise implied two fictitious waste disposal sites, one inside a granite massif and the other in a clay formation, and had as principal objective identification and establishing a hierarchy of the radiological risk parameters important after the disposal closing. The study has considered the most likely scenario for evolution of the geological environment. As computing tools three codes were utilized: MELODIE, assuming a continuous 2D water flow and transfer of radionuclides from waste disposal to biosphere; TRISEC, assuming a continuous 3D water flow and NEWSAM, assuming a transient water flow in a multi-shell geometry. Results for the water circulation in different geological environment as well as the flux curves of soluble radionuclides are presented. Twenty seven radionuclides were retained as important by their radiological impact in assessing the influential EVEREST parameters. The EVEREST exercise does not prove the feasibility of a given geological disposal. It only contributes to the comprehension of the mechanisms controlling the radionuclide migration and gives a hierarchy of the questions which IPSN must answer in approaching the safety demonstrations required by ANDRA.

  16. 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

  17. 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.

  18. La revolution des savants

    CERN Document Server

    Chavanne, A

    1989-01-01

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

  19. 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)

  20. Storage of plugs and experimental devices from reactors; Stockage des bouchons et dispositifs experimentaux en provenance des reacteurs (1961)

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-07-01

    - Within the general programme of storage and treatment of radioactive waste produced by the various operations carried out in an atomic center, it is useful to consider separately the problem of certain waste from reactors, which, because of its size and physical nature, has to be stored with a view to being later treated and finally evacuated. The solution which we propose for this storage problem is presented in this paper. (authors) [French] - Dans le cadre du stockage et du conditionnement des dechets radioactifs provenant des diverses manipulations effectuees dans un centre atomique, il y a lieu de considerer a part certains dechets des reacteurs qui, par leur dimension et leur nature physique doivent etre stockes en vue de leur reprise ulterieure pour un conditionnement et une evacuation definitifs. La solution que nous avons apportee a ce stockage fait l'objet de l'expose qui suit. (auteurs)

  1. 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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-01-01

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

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

    African Journals Online (AJOL)

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

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

    DEFF Research Database (Denmark)

    Valentini, Chiara

    2017-01-01

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

  5. Increased capability of Strassy: the decision making aid for the inspection of nuclear materials; Prolongement des capacites de Strassy: systeme d`aide a la decision pour le controle des matieres nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Werkoff, F [CEA Centre d` Etudes de Fontenay-aux-Roses, 92 (France). Inst. de Protection et de Surete Nucleaire; Preston, N [CEA Centre d` Etudes de Fontenay-aux-Roses, 92 (France). Inst. de Protection et de Surete Nucleaire; [CRIL-Ingenierie, 92 -Puteaux (France); Le Manchec, K [CRIL-Ingenierie, 92 - Puteaux (France); Dumas, M [CEA Centre d` Etudes de Saclay, 91 - Gif-sur-Yvette (France). Direction des Reacteurs Nucleaires

    1994-12-31

    The paper describes the latest developments in STRASSY (Strategy Assistance System), the strategy assistance system for the inspection of nuclear materials. The user can now select the fuel cycle he wishes to investigate from an initial range of 19 facilities. An inspection interface has been developed to enable the details and dates of inspections to be modified. One of the special features of the application of STRASSY in international safeguards is the taking into account of timeliness of detection; certain aspects of the time manager algorithms are presented and analysed, including the guaranteed existence of a solution. The results of a study of diversion paths in a simplified cycle consisting of our facilities are presented. Finally, the modifications necessary to enable STRASSY to be used for a posterior analysis of inspection results are discussed. (authors). 7 refs., 3 figs.

  6. Safeguards Implementation Guide for States with Small Quantities Protocols (French Edition); Guide d'application des garanties pour les Etats ayant des protocoles relatifs aux petites quantites de matieres

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-10-15

    The International Atomic Energy Agency (IAEA) works to enhance the contribution of nuclear energy for peace and prosperity around the world, while helping to ensure that nuclear material is not diverted to nuclear weapons or other nuclear explosive devices. In implementing safeguards, the IAEA plays an instrumental independent verification role, providing credible assurances that States' safeguards commitments are being respected. Most of the world's non-nuclear-weapon States (NNWSs) have concluded comprehensive safeguards agreements (CSAs) with the IAEA, pursuant to the Treaty on the Non- Proliferation of Nuclear Weapons (NPT). The IAEA and States are required to cooperate in the implementation of such agreements. Effective cooperation demonstrates a State's commitment to the peaceful use of nuclear energy and furthers the State's national interests by reducing the risk of unauthorized use of nuclear material. Over 100 NNWSs party to the NPT have very limited quantities of nuclear material and have concluded protocols to their CSAs which hold in abeyance many procedures in Part II of a CSA. These protocols are referred to as 'small quantities protocols' or 'SQPs' and remain in effect as long as the State meets certain eligibility criteria. The purpose of an SQP is to reduce the burden of safeguards implementation for States with little or no nuclear activities, while retaining the integrity of the safeguards system. States with SQPs have very important obligations they must fulfil under their CSAs. In 1997, as part of the IAEA's efforts to strengthen its safeguards system, the Model Additional Protocol to the Agreement(s) between State(s) and the International Atomic Energy Agency for the Application of Safeguards was developed to provide the IAEA with broader access to information and locations, thus significantly increasing the IAEA's ability to provide assurance of the absence of undeclared nuclear material and activities in States. Many States with SQPs have also concluded additional protocols to their CSAs. This publication is aimed at States with SQPs, and addresses obligations under CSAs, SQPs and additional protocols. It is primarily intended for State or regional authorities responsible for safeguards implementation (SRAs). Recognizing that SRAs often have responsibilities in areas other than safeguards, such as nuclear safety and security, the book highlights some possibilities for synergies among these disciplines.

  7. Adsorption of gaseous pollutants on activated carbon filters. Modelling of the coupled exchanges of heat and mass; Adsorption de polluants gazeux sur des filtres de charbon actif. Modelisation des echanges couples de matiere et de chaleur

    Energy Technology Data Exchange (ETDEWEB)

    Fiani, E.

    2000-01-27

    The aim of this work is to remove gasoline and odorous molecules vapors. Thermodynamics and kinetics studies have been carried out; they concern the fixation of representative gases on activated carbons. Hydrogen sulfide and n-butane are chosen to represent the odorous molecules. Different activated carbons are considered: only the adsorbent impregnated by KOH has satisfying performance. The adsorption of hydrocarbons on a granulated activated carbon is studied on four original devices specifically perfected for this work: gravimetry, calorimetry, thermal measurements and gaseous phase chromatography. The gravimetric measurements are coupled to thermal measurements inside the granulates. Strong temperature variations have then been observed inside a granulate during the adsorption. These experimental results have been taken into account to adapt the classical Langmuir kinetic model. This new model allows to predict all the curves: setting / internal temperature variation for the adsorption of the hydrocarbons alone. The competitive nature of the adsorption sites allows then to explain qualitatively the adsorption of binary mixtures of hydrocarbons. At last, the classical Langmuir model allows to explain correctly the thermodynamic results, for the hydrocarbons alone or in binary mixture. The proposed modelling allows then to treat both on a kinetic and thermodynamic way the case of a non isothermal adsorption at the scale of an activated carbon granulate and to predict the phenomena at the filter scale. (O.M.)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-02-15

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

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

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

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

  10. La microscopie ionique analytique des tissus biologiques

    Science.gov (United States)

    Galle, P.

    Proposed in 1960 by R. Castaing and G. Slodzian, secondary ion emission microanalysis is a microanalytical method which is now largely used for the study of inert material. The instrument called the analytical ion microscope can also be used for the study of biological spécimens ; images representing the distribution of a given stable or radioactive isotope in a tissue section are obtained with a resolution of 0.5 μm. Among the characteristics of this method, two are of particular interest in biological research : its capacity for isotopic analysis and its very high sensitivity which makes possible for the first time a chemical analysis of element at a very low or even at a trace concentration in a microvolume. Proposé en 1960 par R. Castaing et G. Slodzian, la microanalyse par émission ionique secondaire est une méthode qui permet, entre autre, d'obtenir des images représentant la distribution des isotopes présents à la surface d'un échantillon solide avec une résolution de 0,5 μm. D'intérêt très général, cette méthode a été d'abord largement utilisée pour l'étude des matériaux inertes. Elle offre en outre des possibilités entièrement nouvelles dans le domaine de la recherche biomédicale. L'instrument réalisé, le microscope ionique analytique présente deux caractéristiques particulièrement intéressantes pour la biologie : la possibilité d'analyse isotopique, et l'extrême sensibilité permettant de détecter et de localiser dans une coupe histologique des éléments à des concentrations très faibles voire à l'état de trace.

  11. La fabrique des sciences des institutions aux pratiques

    CERN Document Server

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

    2006-01-01

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

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

    African Journals Online (AJOL)

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

  13. 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

  14. Elements of a thermic method of preparing beta-sources with fused carriers, including strontium-90; Elements d'une methode thermique de preparation de sources beta avec des entraineurs fondus, y compris le strontium-90; Osnovy termicheskogo metoda prigotovleniya beta-istochnikov s plavlennymi nositelyami, vklyuchayushchimi strontsij-90; Bases de un metodo termico de preparacion de fuentes beta con portadores fundidos, incluido el estroncio-90

    Energy Technology Data Exchange (ETDEWEB)

    Bogdanov, N I; Zakharova, K P; Zimakov, P V; Kulichenko, V V

    1962-01-15

    Sources of ionizing radiation based on the radioisotope Sr{sup 90} are widely used in apparatus and systems of automatic control and regulation of industrial processes. The technology of the preparation of sources is based on dehydration of a mixture of a radioactive solution of strontium nitrate with components such as boric anhydride, silica, and alumina. Thermic treatment of the dehydrated mixture at a high temperature produces a very mobile melt. This cools to a vitreous mass containing the required quantity of the radioisotope Sr{sup 90}. The paper gives data and discusses the results of dehydration of the system SrO - B{sub 2}O{sub 3} - SiO{sub 2} within a temperature range of 100 - 1000{sup o}C and justifies the choice of the main parameters of the technological process. It summarizes a method of mounting a vitreous preparation containing the required quantity of the radioisotope Sr{sup 90} on bases of various shapes and sizes made of steel, ceramic and other materials. The authors discuss the main parameters, ensuring that various types of sources shall be reliable and safe in operation, and give data of Sr{sup 90} sources prepared by the thermic method. (author) [French] Les sources de rayonnements ionisants a base de strontium-90 trouvent une large application dans les appareils et les systemes de controle et de reglage automatique des procedes de production. Le procede de preparation des sources se fonde sur la deshydratation d'un melange compose d'une solution radioactive de nitrate de strontium et d'elements comme l'anhydride borique, la silice, l'alumine, etc. Le traitement thermique du melange deshydrate a haute temperature donne lieu a la formation d'une masse fondue tres mobile, dont le refroidissement fournit une masse vitreuse contenant la quantite requise du radioisotope {sup 59}Sr. Les auteurs citent les donnees et examinent Jes resultats d'une etude sur la deshydratation du systeme SrO - B{sub 2}O{sub 3} - SiO{sub 2} a des temperatures

  15. Charte du Conseil des Gouverneurs

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

    Office 2004 Test Drive User

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

  16. Le statut vitaminique des individus et des populations…

    Directory of Open Access Journals (Sweden)

    Icart Jean-Claude

    2000-05-01

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

  17. Les lueurs des sables

    CERN Multimedia

    Les lueurs des sables

    2013-01-01

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

  18. Liste des auteurs

    OpenAIRE

    2016-01-01

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

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

    African Journals Online (AJOL)

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

  20. Use of hydraulic and aerial mock up to study atmospheric pollution; L'utilisation des maquettes aeriennes et hydrauliques pour l'etude de la pollution atmospherique

    Energy Technology Data Exchange (ETDEWEB)

    Facy, L; Perrin De Brichambaut, C; Doury, A; Le Quinio, R

    1962-07-01

    Fundamental studies on turbulent atmospheric diffusion of finely divided particles, cannot remain on a purely theoretical basis. Further experimental studies must be considered. - In full scale, from accidental and induced releases. - On a reduced scale, in aerodynamic wind tunnels or hydraulic water tunnels. A first set of studies on reduced scale models has been worked out according to a contract between French 'Meteorologie Nationale' and French 'Commissariat a l'Energie Atomique' and with the Collaboration of Saint-Cyr 'Institut Aerotechnique'. Essentially two kinds of results have been obtained: - The mathematical model of SUTTON for the turbulent diffusion in the atmosphere, deduced from the SUTTON theory, generally used by us, has been correctly verified, qualitatively and quantitatively whenever experiments were consistent with the theory conditions. - The quantitative assays of photographic and cinematographic visualization have given precise details on the phenomena inaccessible to calculations, due to the influence of obstacles and release conditions. - Generally, it can be asserted, that the atmospheric pollution studies are worked out by mock up experimentations and that, in some cases these experiments never can be replaced by mathematically pure models. (authors) [French] Les etudes fondamentales portant sur la diffusion turbulente dans l'atmosphere de quantites de matieres finement divisees, ne peuvent se maintenir sur un plan exclusivement theorique. C'est pourquoi des etudes experimentales complementaires doivent etre obligatoirement envisagees: - en vraie grandeur, a partir d'emissions accidentelles ou provoquees; - sur modeles reduits, en soufflerie aerodynamique ou en veine hydraulique. En ce qui concerne les modeles reduits, une premiere serie d'etudes a pu etre menee a bien, dans le cadre d'un contrat passe entre la Meteorologie Nationale et le Commissariat a l'Energie Atomique, et avec la collaboration de l'Institut Aerotechnique de Saint

  1. Organization and methodology applied to the control of commissioning tests to guarantee safe operation of nuclear units; Organisation et methodologie appliquees au controle des essais de mise en service pour assurer la surete de fonctionnement des tranches electronucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Clausner, J P; Jorel, M

    1990-12-01

    ) pour chaque systeme elementaire afin de tester la fonction correspondante. Ces documents donnent les principes, les objectifs et la nature des essais devant etre menes, ainsi que les criteres qui permettent de juger la validite des resultats d'essais. La methode d'analyse du DAS est la suivante: verification de la coherence avec les notes d'etudes et avec les fonctionnements transitoires, adequation des criteres, representativite de la simulation des essais periodiques, evaluation comparative pour juger de l'homogeneite des methodes de controle entre les differents systemes. Les PPE relatifs aux systemes importants pour la surete comportent, a la demande des organismes de surete, une 'analyse d'exhaustivite' qui permet de verifier que l'ensemble des performances et des parametres fonctionnels sont testes, mesures et suivis dans toutes les configurations d'utilisation requises. Le suivi continu et 'en temps reel' des differentes phases d'essais et de leur enchainement est assure par un ingenieur du DAS detache sur le site pour la duree du demarrage. Il analyse les comptes rendus d'execution, controle leurs resultats, examine les faits notables et les incidents survenus pendant le deroulement des essais. Le DAS participe aux reunions de la commission d'essais sur site (CES) qui const