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Sample records for dechets nucleaires par

  1. 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

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    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

  2. 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

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

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

    1960-07-01

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

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

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

    1961-07-01

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

  5. Nuclear wastes; Dechets nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

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

  6. Study of the chimney produced by an underground nuclear explosion; Etude de la cheminee creee par une explosion nucleaire souterraine

    Energy Technology Data Exchange (ETDEWEB)

    Derlich, S [Commissariat a l' Energie Atomique, Bruyeres-le-Chatel (France). Centre d' Etudes

    1969-07-01

    Underground nuclear explosions lead to the formation of a cavity which is roughly of spherical shape. The roof of this cavity is unstable and collapses in most cases, leading to the formation of a chimney. The height and the diameter depend on the energy of the charge and on the nature of the surroundings. The chronology of the various stages can be determined by seismic observations. The interior of the chimney is filled, either partially or completely, with rubble earth. This phenomenon is of great importance as far as the use of nuclear explosions for industrial applications is concerned. (author) [French] Les explosions nucleaires souterraines creent une cavite de forme grossierement spherique. La voute de cette cavite est instable et s'effondre dans la plupart des cas, donnant lieu a la formation d'une cheminee. La hauteur et le diametre sont fonction de l'energie du tir et de la nature du milieu. La chronologie des evenements peut etre determinee par des observations seismiques. L'interieur des cheminees est occupe, en partie ou en totalite, par des eboulis. Ce phenomene presente un grand interet pour l'utilisation des explosions nucleaires a des fins industrielles. (auteur)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

  8. Study of some continuous spectra produced by nuclear reactions with light nuclei; Etude de quelques spectres continus produits par reactions nucleaires avec des noyaux legers

    Energy Technology Data Exchange (ETDEWEB)

    Marquez, L

    1966-07-01

    The continuous spectra coming from several nuclear reactions with light nuclei were measured. The spectra can be explained by a two-step reaction mechanism; however, the reactions produced by {sup 6}Li are different. A mechanism was proposed to explain their spectra based on the following assumptions: {sup 6}Li makes a nuclear molecule with the target which subsequently breaks up in such a way that an {alpha} particle comes out with the kinetic energy that it has in the molecule. The calculated spectra and those measured are in good agreement. (author) [French] Nous avons mesure les spectres continus produits dans plusieurs reactions nucleaires avec des noyaux legers. A l'exception des spectres produits par {sup 6}Li, on a trouve qu'on pouvait expliquer ces spectres par le mecanisme des reactions en deux etapes. Nous avons propose un mecanisme pour expliquer les spectres produits par {sup 6}Li. On suppose que {sup 6}Li forme une molecule nucleaire avec la cible qui eclate ensuite de facon telle qu'une particule alpha de la molecule sort avec l'energie cinetique de son mouvement propre dans la molecule. Les spectres calcules avec ces hypotheses et les spectres mesures sont en bon accord. (auteur)

  9. 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)

  10. Quantitative dosing by nuclear magnetic resonance; Dosages quantitatifs par resonance magnetique nucleaire

    Energy Technology Data Exchange (ETDEWEB)

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

    1958-07-01

    The measurement of the absolute concentration of a heavy water reference containing approximately 99.8 per cent of D{sub 2}O has been performed, by an original magnetic resonance method ('Adiabatic fast passage method') with a precision of 5.10{sup -5} on the D{sub 2}O concentration. (author) [French] La determination du titre absolu d'une eau lourde etalon de teneur approximative de 99,8 pour cent de D{sub 2}O a pu etre effectuee par une methode originale de resonance magnetique ('Methode de passage rapide adiabatique') a une precision de 5.10{sup -5} sur le titre de D{sub 2}O. (auteur)

  11. Quantitative dosing by nuclear magnetic resonance; Dosages quantitatifs par resonance magnetique nucleaire

    Energy Technology Data Exchange (ETDEWEB)

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

    1958-07-01

    The measurement of the absolute concentration of a heavy water reference containing approximately 99.8 per cent of D{sub 2}O has been performed, by an original magnetic resonance method ('Adiabatic fast passage method') with a precision of 5.10{sup -5} on the D{sub 2}O concentration. (author) [French] La determination du titre absolu d'une eau lourde etalon de teneur approximative de 99,8 pour cent de D{sub 2}O a pu etre effectuee par une methode originale de resonance magnetique ('Methode de passage rapide adiabatique') a une precision de 5.10{sup -5} sur le titre de D{sub 2}O. (auteur)

  12. 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)

  13. Nuclear wastes management; Gestion des dechets nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

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

  14. Contribution to the study of solid helium-3 by nuclear magnetic resonance; Contribution a l'etude de l'helium trois solide par resonance magnetique nucleaire

    Energy Technology Data Exchange (ETDEWEB)

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

    1968-07-01

    Due to the unusually large zero point motion of helium three atoms in the solid, the overlap of the atomic wave functions is very important. As a consequence, there are exchange interactions, the theoretical calculation and the experimental measurement of which are discussed. Nuclear magnetic resonance is especially well suited for the latter.A detailed theory is given for both exchange narrowing and Zeeman-exchange cross relaxation, which phenomena are used to measure the exchange interaction as a function of molar volume. The alignment temperature is thus known; it goes down when the pressure goes up and is never higher than three milli degrees. An influence of helium four impurities on the exchange interactions between helium three atoms which are neighbours of the substitutional He is shown. (author) [French] Par suite de l'amplitude exceptionnelle des mouvements de point zero dans l'helium trois solide, le recouvrement des fonctions d'onde atomiques est tres important. Il en resulte des interactions d' echange dont on discute l'evaluation theorique et la mise en evidence experimentale. Cette derniere peut se faire par resonance magnetique; on etudie theoriquement les phenomenes de retrecissement par echange et de relaxation Zeeman-echange que l'on met a profit pour determiner les interactions d'echange en fonction du volume molaire. On en deduit que la temperature d'alignement nucleaire diminue quand on comprime le solide et est au plus de 3x10{sup -3} K. L'influence des impuretes d'helium quatre sur les interactions d'echange entre atomes {sup 3}He voisins de {sup 4}He est mise en evidence. (auteur)

  15. Simulation of accelerator transmutation of long-lived nuclear wastes; Simulation de transmutation de dechets nucleaires a vie longue par accelerateur

    Energy Technology Data Exchange (ETDEWEB)

    Fabienne, Wolff-Bacha [Paris-11 Univ., 91 - Orsay (France)

    1997-07-09

    The incineration of minor actinides with a hybrid reactor (i.e. coupled with an accelerator) could reduce their radioactivity. The scientific tool used for simulations, the GEANT code implemented on a paralleled computer, has been confirmed initially on thin and thick targets and by simulation of a pressurized water reactor, a fast reactor like Superphenix, and a molten salt fast hybrid reactor `ATP`. Simulating a thermal hybrid reactor seems to indicate the non-negligible presence of neutrons which diffuse back to the accelerator. In spite of simplifications, the simulation of a molten lead fast hybrid reactor (as the CERN Fast Energy Amplifier) might indicate difficulties in the radial power distribution in the core, the life time of the window and the activated air leak risk. Finally, we propose a thermoelectric compact hybrid reactor, PRAHE - small atomic board hybrid reactor - the principle of which allows a neutron coupling between the accelerator and the reactor. (author) 270 refs., 91 figs., 31 tabs.

  16. Differential measurement of the earth's magnetic field by nuclear magnetic resonance; Mesure differentielle du champ magnetique terrestre par resonance magnetique nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Robach, F [Commissariat a l' Energie Atomique, 38 - Grenoble (France). Centre d' Etudes Nucleaires

    1967-07-01

    MNR transducers using proton dynamic polarisation allows to convert into a phase measurement any variation of the earth magnetic field. There exist several versions of the instrument corresponding to various models of MNR transducers, which the author analyses in detail, devoting an important place to influence of their alignment with respect to the earth's magnetic field. The sensibility obtained is of one hundredth of a gamma over a bandwidth of (0-0,1 Hz). - This instrument is designed for measuring field gradients in airborne magnetic surveying, for detecting nearly magnetic anomalies, and for distinguishing between nearly and distant magnetic phenomena. (author) [French] L'emploi de capteurs, bases sur la resonance magnetique nucleaire des protons en presence de polarisation dynamique, permet de traduire une difference de champ magnetique terrestre en une mesure de phase. L'appareil existe sous plusieurs versions avec des capteurs de modeles differents dont l'auteur fait une analyse detaillee en accordant une part importante a l'influence de l'orientation des capteurs par rapport au champ magnetique terrestre. La sensibilite est de 1/100 {gamma} pour une bande passante de (0 - 0,1 Hz). Cet appareil s'applique a la mesure du gradient en prospection magnetique aeroportee, a la detection d'anomalies magnetiques proches, a la differentiation d'effets magnetiques proches et lointains. (auteur)

  17. New features of nuclear excitation by {alpha} particles scattering; Nouveaux aspects de l'excitation nucleaire par diffusion de particules {alpha}

    Energy Technology Data Exchange (ETDEWEB)

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

    1962-07-01

    Inelastic scattering of medium energy a particles by nuclei is known to excite preferentially levels of collective character. We have studied the scattering of isotopically enriched targets of Ca, Fe, Ni, Cu, Zn. In part I, we discuss the theoretical features of the interaction. In part II, we describe the experimental procedure. Results are presented and analysed in part III. {alpha} particles scattering by Ca{sup 40} is showed to excite preferentially odd parity levels. In odd nuclei we have observed multiplets due to the coupling of the odd nucleon with the even-even core vibrations. For even-even nuclei, a few levels are excited with lower cross-sections between the well-known first 2{sup +} and 3{sup -} states. Some could be members of the two phonon quadrupole excitation and involve a double nuclear excitation process. (author) [French] On sait que la diffusion inelastique des particules alpha de moyenne energie excite preferentiellement des niveaux de caractere collectif. Nous avons etudie la diffusion des particules alpha de 44 MeV du cyclotron de Saclay par des isotopes separes de Ca, Fe, Ni, Cu, Zn. Dans la premiere partie nous exposons les theories de cette interaction. Dans la seconde nous decrivons le systeme experimental. Les resultats sont donnes dans la troisieme partie. Nous montrons que les niveaux excites preferentiellement pour {sup 40}Ca par diffusion ({alpha},{alpha}') sont de parite negative. Dans les noyaux pair-impair nous avons observe des multiplets dus au couplage du nucleon celibataire avec les vibrations du coeur pair-pair. Pour les noyaux pair-pair nous avons pu etudier entre le premier niveau 2{sup +} et le niveau 3{sup -} deja bien connus certains etats plus faiblement excites. Il semble qu'ils sont dus a une excitation quadrupolaire a deux phonons et impliquent un processus de double excitation nucleaire. (auteur)

  18. Is it possible to recycle nuclear wastes? Costs, risks and stakes of the plutonium industry; Peut-on recycler les dechets nucleaires? Couts, risques et enjeux de l'industrie du plutonium

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2009-07-01

    This document, published by the French association 'Sortir du nucleaire' (Get out of nuclear), gives some information on the chain reaction from uranium to plutonium, the difference between reprocessing (which does not reduce waste volumes but multiply waste types) and recycling, the high risks associated with plutonium transport, La Hague as the most dangerous nuclear site in France, reprocessing as the alibi for the French nuclear industry, Areva as an expert in propaganda, reprocessing as an absurd world strategy, plutonium as a fuel for proliferation, the myth of unlimited energy with the breeder reactors, and so on

  19. Corrosion by cooling gases in nuclear reactors; la corrosion par les gaz caloporteurs dans les reacteurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Darras, R. [Commissariat a l' energie atomique et aux energies alternatives - CEA, Centre de Saclay, Section d' etude de la corrosion par gaz et metaux liquides (France)

    1960-07-01

    This article begins with a review of the various materials which can be used and the cooling gases in which they may be heated, emphasis being placed on the importance of reaching temperatures as high as possible. This is followed by a few general remarks on the dry oxidation of metals and alloys, particularly with regard to diffusion phenomena and their various possible mechanisms, and also the methods of investigation employed. Finally, the behaviour of the chief nuclear materials heated in the various gases is studied successively. Materials used for fuel (metallic uranium, uranium oxide, carbides and silicides), canning materials (magnesium, aluminium, zirconium, beryllium, stainless and refractory steels), structural materials (ordinary or slightly alloyed steels), and finally moderators (graphite, beryllium oxide) are deal with in this way. This account is backed up both by the results obtained at the CEA and by work published outside or abroad up to the present day. In conclusion, every effort has been made to direct future research on the basis of the foregoing. Reprint of a paper published in Industries Atomiques - no. 9/10, 1959, p. 3-23 [French] Dans cet article, on passe tout d'abord en revue les divers materiaux utilisables et les gaz de refroidissement dans lesquels ils peuvent etre chauffes, en insistant sur l'interet d'atteindre des temperatures aussi elevees que possible. On rappelle ensuite quelques generalites sur l'oxydation seche des metaux et alliages, notamment en ce qui concerne les phenomenes de diffusion et leurs divers mecanismes possibles ainsi que les methodes d'etude. Enfin, le comportement des principaux materiaux nucleaires chauffes dans les divers gaz est etudie successivement. On traita ainsi des materiaux combustibles (uranium metallique, oxyde, carbures et siliciures d'uranium), des materiaux de gainage (magnesium, aluminium, zirconium, beryllium, aciers inoxydables et refractaires), des materiaux de structure (aciers ordinaires

  20. General problems arising from the analogical resolution of the kinetic equations of nuclear reactors (1961); Problemes generaux poses par la resolution analogique des equations cinetiques des reacteurs nucleaires (1961)

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-07-01

    The author reviews precisely the analogical techniques used for the resolution of the kinetic equations of nuclear reactors. Prior to this, he recalls the reasons which oblige physicians and engineers, even today, to use electronic machines in this domain. The author then considers the technological problems posed by the range of values which the various nuclear parameters adopt. In each case, he shows that a compromise is possible allowing an optimum precision. He compares the results to those obtained by arithmetic calculation and uses the examples chosen in a critical analysis of the present possibilities of the two methods of calculation. (author) [French] L'auteur cherche a faire un point aussi exact que possible des techniques analogiques utilisees pour resoudre les equations cinetiques des reacteurs nucleaires. Il rappelle auparavant les raisons pour lesquelles physiciens et ingenieurs sont obliges, encore aujourd'hui, de faire appel aux machines electroniques dans ce domaine. Puis il etudie les problemes technologiques que souleve le champ des valeurs prises par les differents parametres nucleaires. Dans chacun des cas, il montre l'existence d'un compromis qui permet d'atteindre une precision optimum. Il compare les resultats obtenus a ceux provenant de calculateurs arithmetiques et profite des exemples choisis pour faire une analyse critique des possibilites actuelles offertes par les deux modes de calcul. (auteur)

  1. A study of the fluorescence of the rare gases excited by nuclear particles. Use of the principle for the detection of nuclear radiation by scintillation; Etude de la fluorescence des gaz rares excites par des particules nucleaires. Utilisation pour la detection des rayonnements nucleaires par scintillation

    Energy Technology Data Exchange (ETDEWEB)

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

    1959-12-15

    composantes, l'une tres breve due a la desexcitation directe du gaz rare, l'autre relativement plus lente, due au transfert d'energie sur les impuretes. La mesure des durees de vie des etats excites a confirme l'hypothese precedente, la partie breve de l'impulsion est extremement courte: inferieure a 2,25.10{sup -9} s dans le cas du xenon, la partie plus lente a une duree qui depend etroitement de la concentration d'azote, l'azote etant l'impurete dont le role est preponderant dans tous les cas. L'etude des gaz rares soumis a un champ electrique a permis de montrer que la quantite de lumiere produite par une particule {alpha} peut etre multipliee (par 60 dans un champ de 600 V/cm par exemple) ce qui correspond a un rendement de luminescence superieur a celui de INa TI. Dans la deuxieme partie on a etudie les caracteristiques des gaz rares comme scintillateurs, la plus importante est l'absence de saturation de la fluorescence lorsque la densite d'excitation transmise au gaz devient tres grande. Ceci joint au temps de scintillation tres court a permis d'etudier un certain nombre d'applications a la physique nucleaire (mesure d'energie des particules lourdes, etude cinetique des reacteurs nucleaires, spectroscopie des neutrons...). (auteur)

  2. Can-rupture detection in gas-cooled nuclear reactors; La detection des ruptures de gaine dans les piles nucleaires refroidies par gaz

    Energy Technology Data Exchange (ETDEWEB)

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

    1965-07-01

    Can-rupture detection (DRG) is one important aspect of pile safety, more particularly so in the case of gas-cooled reactors. A rapid and sure detection constitutes also an improvement as far as the efficiency of electricity-producing nuclear power stations are concerned. Among the numerous can-rupture detection methods, that based on the measurement of the concentration of short-lived fission gases in the heat-carrying fluid has proved to be the most sensitive and the most rapid. A systematic study of detectors based on the electrostatic collection of the daughter products of fission gases has been undertaken with a view to equip the reactors EL 2, G 3, EDF 1, EDF 2 and EDF 3, the gas loops of PEGASE and EL 4. The different parameters are studied in detail in order to obtain a maximum sensitivity and to make it possible to construct detection devices having the maximum operational reliability and requiring the minimum maintenance. The primary applications of these devices are examined in the case of the above-mentioned reactors. (author) [French] La Detection des Ruptures de Gaines (D. R. G.) est un aspect important de la securite des piles et plus particulierement des piles refroidies par un gaz. Une detection rapide et sure constitue aussi un element d'amelioration du rendement des centrales nucleaires productrices d'energie electrique. Parmi les nombreuses methodes de detection des ruptures de gaines, la mesure de la concentration dans le fluide caloporteur des gaz de fission a vie courte s'est revelee comme la plus sensible et la plus rapide. Une etude systematique des detecteurs a collection electrostatique des descendants des gaz de fission a ete entreprise en vue d'equiper les piles EL 2, G 3, EDF 1, EDF 2 et EDF 3, les boucles a gaz de la pile Pegase et la pile EL 4. Les divers parametres sont etudies en detail pour obtenir une sensibilite maximum et permettre la realisation de dispositifs de detection ayant le maximum de securite de

  3. Can-rupture detection in gas-cooled nuclear reactors; La detection des ruptures de gaine dans les piles nucleaires refroidies par gaz

    Energy Technology Data Exchange (ETDEWEB)

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

    1965-07-01

    Can-rupture detection (DRG) is one important aspect of pile safety, more particularly so in the case of gas-cooled reactors. A rapid and sure detection constitutes also an improvement as far as the efficiency of electricity-producing nuclear power stations are concerned. Among the numerous can-rupture detection methods, that based on the measurement of the concentration of short-lived fission gases in the heat-carrying fluid has proved to be the most sensitive and the most rapid. A systematic study of detectors based on the electrostatic collection of the daughter products of fission gases has been undertaken with a view to equip the reactors EL 2, G 3, EDF 1, EDF 2 and EDF 3, the gas loops of PEGASE and EL 4. The different parameters are studied in detail in order to obtain a maximum sensitivity and to make it possible to construct detection devices having the maximum operational reliability and requiring the minimum maintenance. The primary applications of these devices are examined in the case of the above-mentioned reactors. (author) [French] La Detection des Ruptures de Gaines (D. R. G.) est un aspect important de la securite des piles et plus particulierement des piles refroidies par un gaz. Une detection rapide et sure constitue aussi un element d'amelioration du rendement des centrales nucleaires productrices d'energie electrique. Parmi les nombreuses methodes de detection des ruptures de gaines, la mesure de la concentration dans le fluide caloporteur des gaz de fission a vie courte s'est revelee comme la plus sensible et la plus rapide. Une etude systematique des detecteurs a collection electrostatique des descendants des gaz de fission a ete entreprise en vue d'equiper les piles EL 2, G 3, EDF 1, EDF 2 et EDF 3, les boucles a gaz de la pile Pegase et la pile EL 4. Les divers parametres sont etudies en detail pour obtenir une sensibilite maximum et permettre la realisation de dispositifs de detection ayant le maximum de securite de fonctionnement et le

  4. Chemical elimination of alumina in suspension in nuclear reactors heavy water; Elimination de l'alumine en suspension dans l'eau lourde des reacteurs nucleaires par voie chimique

    Energy Technology Data Exchange (ETDEWEB)

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

    1967-02-01

    Corrosion of aluminium in contact with moderating water in nuclear reactor leads to the formation of an alumina hydrosol which can have an adverse effect on the operation of the reactor. Several physical methods have been used in an attempt to counteract this effect. The method proposed here consists in the elimination of the aluminium by dissolution and subsequent fixation in the ionic form on mixed-bed ion-exchange resin. In order to do this, the parameters and the values of these parameters most favorable to the dissolution process have been determined. If the moderator is heavy water, the deuterated acid can be prepared by converting a solution in heavy water to a salt of the acid using a deuterated cationic resin. (author) [French] La corrosion de l'aluminium au contact de l'eau moderatrice des reacteurs nucleaires, donne lieu a la formation d'un hydrosol d'alumine nuisible au bon fonctionnement des reacteurs. Plusieurs methodes physiques ont ete mises en oeuvre pour pallier ces inconvenients. On propose ici d'eliminer l'alumine par solubilisation pour la fixer ensuite sous forme ionique par des resines echangeuses d'ions, en lit melange. A cette fin on determine les parametres et leurs grandeurs favorables a cette solubilisation. Si le moderateur est de l'eau lourde la preparation d'acide deutere peut etre effectuee par passage d'une solution en eau lourde a un sel de l'acide sur resine cationique deuteree.

  5. Contribution to the study of the evolution of radiation induced He in Be O; Etudes sur l'evolution de l'helium produit par reactions nucleaires dans l'oxyde de beryllium

    Energy Technology Data Exchange (ETDEWEB)

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

    1966-11-15

    The purpose of this work in-pile investigation of He formed by (n, 2n) and (n, {alpha}) nuclear reactions, released from irradiated BeO, in the temperature range 1000 - 1350 deg. C. The experimental results show that, for an instantaneous neutron fast flux of 10{sup 13} n cm{sup -2} sec{sup -1}, an equilibrium is attempted, after several days, for a part lower than 20 per cent of the quantity of He formed, theoretically calculated from the neutron cross sections of nuclear reactions, and from the analytical form of the neutron fast flux, releases from the solid. The validity of the values of calculated helium and the gas chromatographic analytical method are also verified by dissolution of the BeO pellets in cryolite. A new fast neutron flux measuring method may be so defined. The discussion of the experimental results enables to establish that the processus of He release is characterized by two phenomena: the first one which controls the release of He atoms out of the solid and the second which reveals a capture processus, connected to the irradiation and probably due to the vacancies induced in the lattice. (author) [French] On etudie en pile le degagement de l'helium forme par reactions nucleaires (n, 2 n) et (n, {alpha}) dans l'oxyde de beryllium irradie entre 1000 et 1350 deg. C. Les resultats experimentaux montrant que, pour un flux rapide instantane de 10{sup 13} n{sub r} cm{sup -2} s{sup -1}, on aboutit, au bout de quelques jours, a un etat d'equilibre pour lequel une partie, inferieure a 20 pour cent de la quantite d'helium forme, calculee theoriquement a partir des sections efficaces des reactions nucleaires et de la forme analytique du flux rapide, s'echappe du solide. On verifie egalement par dissolution des echantillons de BeO dans la cryolithe la validite du calcul de l'helium et de la methode de dosage par chromatographie en phase gazeuse. On peut ainsi definir une methode nouvelle de mesure des flux rapides. La discussion des resultats experimentaux

  6. Contribution to the study of the evolution of radiation induced He in Be O; Etudes sur l'evolution de l'helium produit par reactions nucleaires dans l'oxyde de beryllium

    Energy Technology Data Exchange (ETDEWEB)

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

    1966-11-15

    The purpose of this work in-pile investigation of He formed by (n, 2n) and (n, {alpha}) nuclear reactions, released from irradiated BeO, in the temperature range 1000 - 1350 deg. C. The experimental results show that, for an instantaneous neutron fast flux of 10{sup 13} n cm{sup -2} sec{sup -1}, an equilibrium is attempted, after several days, for a part lower than 20 per cent of the quantity of He formed, theoretically calculated from the neutron cross sections of nuclear reactions, and from the analytical form of the neutron fast flux, releases from the solid. The validity of the values of calculated helium and the gas chromatographic analytical method are also verified by dissolution of the BeO pellets in cryolite. A new fast neutron flux measuring method may be so defined. The discussion of the experimental results enables to establish that the processus of He release is characterized by two phenomena: the first one which controls the release of He atoms out of the solid and the second which reveals a capture processus, connected to the irradiation and probably due to the vacancies induced in the lattice. (author) [French] On etudie en pile le degagement de l'helium forme par reactions nucleaires (n, 2 n) et (n, {alpha}) dans l'oxyde de beryllium irradie entre 1000 et 1350 deg. C. Les resultats experimentaux montrant que, pour un flux rapide instantane de 10{sup 13} n{sub r} cm{sup -2} s{sup -1}, on aboutit, au bout de quelques jours, a un etat d'equilibre pour lequel une partie, inferieure a 20 pour cent de la quantite d'helium forme, calculee theoriquement a partir des sections efficaces des reactions nucleaires et de la forme analytique du flux rapide, s'echappe du solide. On verifie egalement par dissolution des echantillons de BeO dans la cryolithe la validite du calcul de l'helium et de la methode de dosage par chromatographie en phase gazeuse. On peut ainsi definir une methode nouvelle de mesure des flux rapides. La

  7. 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

  8. 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

  9. Nuclear waste management; La gestion des dechets nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Nifenecker, H.

    2008-07-01

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

  10. The origin of cholesterol in chyle demonstrated by nuclear indicator methods; Origines du cholesterol du chyle mises en evidence par la methode des indicateurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Vyas, M

    1962-07-01

    In order to obtain information about the mechanism of the intestinal absorption of cholesterol, rats having a lymphatic abdominal fistula are used. The animals receive either 4-{sup 14}C- cholesterol subcutaneously or orally, or the 1-{sup 14}C acetate. The study of the specific radio-activities of the cholesterol in chyle, in serum, in the lining, and in the intestinal contents makes it possible to define the roles played by the transfer cholesterol from the serum, by the cholesterol synthesised intestinally, and by the absorption cholesterol, in the formations of the lymph and of the chylomicrons. A new theory is proposed for the mechanism of cholesterol absorption. (author) [French] Pour obtenir des renseignements concernant le mecanisme de l'absorption intestinale du cholesterol, on utilise des rats porteurs d'une fistule lymphatique abdominale. Les animaux recoivent soit du cholesterol 4-{sup 14}C par voie sous-cutanee ou par voie orale, soit de l'acetate 1-{sup 14}C. L'etude des radioactivites specifiques du cholesterol du chyle, du serum, de la paroi et du contenu intestinal permet de preciser les roles joues par le cholesterol de transfert d'origine serique, par le cholesterol de synthese intestinale et par le cholesterol d'absorption, dans la formation de la lymphe et des chylomicrons. Une theorie nouvelle concernant le mecanisme de l'absorption du cholesterol est proposee. (auteur)

  11. Study of the actinide-lanthanide separation from nuclear waste by a new pyrochemical process; Etude de la separation actinides-lanthanides des dechets nucleaires par un procede pyrochimique nouveau

    Energy Technology Data Exchange (ETDEWEB)

    Lemort, F. [CEA Marcoule, Departement de Retraitement, des Dechets et du Demantelement, 30 - Bagnols-sur-Ceze (France)]|[Institut National Polytechnique, 38 - Grenoble (France)

    1997-01-01

    The theoretical extraction and separation of platinoids, actinides and lanthanides is allowed by thermodynamic using two adapted reducing agents: zinc and magnesium. Thereby, a pyrochemical method for the nuclear waste processing has been devised. The high temperature handling of the elements in fluoride forms and their processing by a reactive metallic phase required special precautions. The study of the behavior of matter in exploratory systems allowed the development of an experimental technology for the treatment and contacting of phases. The thermodynamical analysis of the experimental results shows the feasibility of the process. A model was developed to predict the distribution coefficients of zirconium, uranium and lanthanum as a function of the system composition. An estimation method was proposed in order to evaluate the distribution coefficients in diluted solution of all the actinides and lanthanides existing in the fission products between LiF CaF{sub 2} and Zn-Mg at 720 deg C. Coupled with the experimental results, the estimates results may be extrapolated to concentrated solutions allowing predictions of the separation of all actinides and lanthanides. The rapidity of element transfer is induced by a thermal effect caused by the high exothermicity of the reduction by magnesium. The kinetic coefficients have been linked with the reduction enthalpy of each element. Moreover, the kinetics seem limited by chemical reaction and not by mass transfer. (author) 66 refs.

  12. Nuclear wastes management. 1. round table - geologic disposal as questioned by the public in concern; Gestion des dechets nucleaires. 1. table ronde le stockage geologique - la mise en question par les publics concernes

    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 last round table held at Paris. This meeting gathers representatives of the different actors of the nuclear industry, ministers, public authorities, non governmental organizations who argue the questions asked by peoples from the audience. The topics concern various aspects of waste management, like the quantity of wastes in concern, the reversibility of storages, the monitoring of waste facilities once closed down, the related costs, and the general safety questions about the suitability of the clay formation near the Bure site for the disposal of high-level and long-lived radioactive wastes. A second part of the meeting addresses some remarks about the information of the general public and the decision making process. Finally, five presentations (slides) are attached to these proceedings and treat of: the safety of the disposal in deep geologic formation; the management of spent fuels in Canada; the nuclear wastes R and D in Sweden; the researches and projects in Belgium for the geologic disposal of long-lived radioactive wastes; the results of ANDRA's researches on deep geologic disposal. (J.S.)

  13. Nuclear wastes management. 1. round table - geologic disposal as questioned by the public in concern; Gestion des dechets nucleaires. 1. table ronde le stockage geologique - la mise en question par les publics concernes

    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 last round table held at Paris. This meeting gathers representatives of the different actors of the nuclear industry, ministers, public authorities, non governmental organizations who argue the questions asked by peoples from the audience. The topics concern various aspects of waste management, like the quantity of wastes in concern, the reversibility of storages, the monitoring of waste facilities once closed down, the related costs, and the general safety questions about the suitability of the clay formation near the Bure site for the disposal of high-level and long-lived radioactive wastes. A second part of the meeting addresses some remarks about the information of the general public and the decision making process. Finally, five presentations (slides) are attached to these proceedings and treat of: the safety of the disposal in deep geologic formation; the management of spent fuels in Canada; the nuclear wastes R and D in Sweden; the researches and projects in Belgium for the geologic disposal of long-lived radioactive wastes; the results of ANDRA's researches on deep geologic disposal. (J.S.)

  14. Gamma irradiation-induced modifications of resins found in nuclear waste embedding processes; Modifications induites par irradiation gamma dans les differentes resines rencontrees dans le traitement des dechets nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Allali, H [Faculte des Science et Techniques, Settat (Morocco); Debre, O; Lambert, M; Nsouli, B; Thomas, J P [Inst. de Physique Nucleaire, Lyon-1 Univ., 69 - Villeurbanne (France); Collaboration: IPN-Lyon, Laboratoire d` Etude des Materiaux Plastiques et des Biomateriaux, URA 507, UCBL, Agence Nationale pour la Gestion des Dechets Radiactifs

    1999-12-31

    The various resins involved in nuclear waste disposal are subject to gamma irradiation-induced modifications. From Time-of-Flight Mass Spectrometry of Secondary ions emitted under High Energy Projectiles bombardment (HSF-SIMS) of such materials the following results are obtained: the embedding epoxy resin DGEBA-DDM does not exhibit significant bulk changes in chemical structure, whatever the dose rate and irradiation medium (air or water), at least up to 2 MGy. However, oxidation processes are well observed at the very surface. Under the same conditions Ion exchange resins to be embedded are subjected to scissions of their functional sites, leading to fixed ion release. Dehydration under irradiation is observed pointing out the crucial role of water in ion transport outside of the material. (authors)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

  16. 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)

  17. 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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

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

  19. 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)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-02-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

  4. Contribution to the study of molecular movements in cyclohexane by electron spin resonance and electron-nuclear double resonance using a radical probe; Contribution a l'etude des mouvements moleculaires dans le cyclohexane par resonance paramagnetique electronique et double resonance electronique-nucleaire a l'aide d'une sonde radicalaire

    Energy Technology Data Exchange (ETDEWEB)

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

    1969-07-01

    Solutions of stable free radicals of the nitroxide type have been studied as a function of temperature. In the plastic or globular state, the cyclohexane molecules have rapid rotational and diffusional movements. They transmit this movement to dissolved free radicals. Conversely, measurements by electron spin resonance of the absolute movement of the radicals, and by electron nuclear double resonance of their movement relative to the cyclohexane molecules give very precise methods for local analyses of the movement present in the cyclohexane matrix. The principle of these techniques makes up the 'radical probe method'. (author) [French] Des solutions de radicaux libres stables, du type nitroxyde dans le cyclohexane ont ete etudiees, en fonction de la temperature. Les molecules de cyclohexane, dans l'etat plastique ou globulaire, sont animees de mouvements rapides de rotation sur elles-memes et de diffusion. Elles transmettent leur mobilite aux radicaux libres dissous. Reciproquement, la mesure du mouvement absolu des radicaux, a l'aide de la resonance paramagnetique electronique, et celle du mouvement relatif des radicaux et des molecules de cyclohexane par double resonance electronique-nucleaire, constituent des methodes tres precises pour analyser localement les mouvements presents dans la matrice de cyclohexane. Ce principe et ces techniques constituent la 'methode de la sonde radicalaire'. (auteur)

  5. Contribution to the study of molecular movements in cyclohexane by electron spin resonance and electron-nuclear double resonance using a radical probe; Contribution a l'etude des mouvements moleculaires dans le cyclohexane par resonance paramagnetique electronique et double resonance electronique-nucleaire a l'aide d'une sonde radicalaire

    Energy Technology Data Exchange (ETDEWEB)

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

    1969-07-01

    Solutions of stable free radicals of the nitroxide type have been studied as a function of temperature. In the plastic or globular state, the cyclohexane molecules have rapid rotational and diffusional movements. They transmit this movement to dissolved free radicals. Conversely, measurements by electron spin resonance of the absolute movement of the radicals, and by electron nuclear double resonance of their movement relative to the cyclohexane molecules give very precise methods for local analyses of the movement present in the cyclohexane matrix. The principle of these techniques makes up the 'radical probe method'. (author) [French] Des solutions de radicaux libres stables, du type nitroxyde dans le cyclohexane ont ete etudiees, en fonction de la temperature. Les molecules de cyclohexane, dans l'etat plastique ou globulaire, sont animees de mouvements rapides de rotation sur elles-memes et de diffusion. Elles transmettent leur mobilite aux radicaux libres dissous. Reciproquement, la mesure du mouvement absolu des radicaux, a l'aide de la resonance paramagnetique electronique, et celle du mouvement relatif des radicaux et des molecules de cyclohexane par double resonance electronique-nucleaire, constituent des methodes tres precises pour analyser localement les mouvements presents dans la matrice de cyclohexane. Ce principe et ces techniques constituent la 'methode de la sonde radicalaire'. (auteur)

  6. 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)

  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. 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

    molecule by the nuclear recoil and the resulting excitation. The hypothesis is put forward that the kind and quantity of certain new radioactive species produced in connection with nuclear events is less a function of the nature and concentration of primary recoil fragments than are the ions, radicals and lattice defects imparted to the irradiated materials by secondary recoil effects (elastic and inelastic interactions) , including the peculiar influence of oxygen. (author) [French] Les auteurs ont etudie les effets chimiques provoques par les atomes chaud de recul resultant des reactions nucleaires dans les solides et dans les liquides en se fondant sur une vaste comparaison des produits des processus (n,{gamma}) et (n,2n) dans les composes phenyles du germanium, de l'etain, du plomb, de l'arsenic et de l'antimoine. En outre, ils ont compare les produits de recul radioactifs formes apres capture K dans le tetraphenyl- germanium-{sup 68}Ge avec les resultats du processus (n,{gamma}) dans le triphenylgalliumet du processus (n,p) sur le tetraphenylgermanium. Enfin, ils ont etudie la transition {beta}{sup -} dans laquelle {sup 77}Ge est remplace par {sup 77}As dans le compose. En appliquant differentes methodes de separation, par exemple la chromatographie d'adsorption sur alumine, l'echange d'ions et l'electrophorese, ils ont separe les divers produits de recul radioactifs et determine les rendements individuels. Ils ont constate que, dans les reactions nucleaires, les composes des metaux cites ayant des coordinats identiques forment pratiquement les memes classes.de produits de recul. Toutefois, pour la distribution des rendements, il y a des differences caracteristiques entre la reaction (n,{gamma}) et la reaction (n,2n). L'influence sur les rendements est a peine perceptible lorsque les irradiations ont lieu dans des liquides ou des solutions. Mais les differences trouvees pour les nouveaux composes formes par des transformations nucleaires sont frappantes, en ce qui

  9. Health physics problems in the context of the development of industrial uses of nuclear energy; Les problemes de radioprotection devant le developpement de l'utilisation industrielle de l'energie nucleaire

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

    ou les moyens technologiques de protection sont multiples et complexes. Les etudes de surete des sites permettent de preciser les parametres de diffusion ou de reconcentration dans les divers milieux naturels de facon a permettre de prevoir le sort des effluents radioactifs depuis les installations qui en sont la source jusqu'a l'homme qui peut y etre expose. L'organisation de la surveillance de la radioactivite sur les sites nucleaires est liee tres etroitement aux etudes de surete. Parmi les nombreuses etudes a mener, on insistera plus particulierement sur les experiences de diffusion atmospherique dont le but est de preciser la valeur des parametres introduits par la theorie tout en permettant de tenir compte de facteurs complementaires. - les etudes hydrologiques, hydrogeologiques et oceanographiques, qui permettent de preciser le sort des ions radioactifs dans l'hydrosphere. - les experiences et etudes liees aux possibilites de rejet ou de stockage des dechets dans le sol. L'ensemble de ces travaux constitue un moyen complementaire, la radioprotection, qui etablit une liaison necessaire entre la surete nucleaire proprement dite laquelle concerne le fonctionnement meme des installations nucleaires, et la surveillance medicale laquelle concerne directement la sante de l'individu et de la population. En meme temps,la radioprotection donne a chacune de ces disciplines une independance qui accroit leur efficacite sur le plan de la securite. (auteurs)

  10. Health physics problems in the context of the development of industrial uses of nuclear energy; Les problemes de radioprotection devant le developpement de l'utilisation industrielle de l'energie nucleaire

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

    surete des sites permettent de preciser les parametres de diffusion ou de reconcentration dans les divers milieux naturels de facon a permettre de prevoir le sort des effluents radioactifs depuis les installations qui en sont la source jusqu'a l'homme qui peut y etre expose. L'organisation de la surveillance de la radioactivite sur les sites nucleaires est liee tres etroitement aux etudes de surete. Parmi les nombreuses etudes a mener, on insistera plus particulierement sur les experiences de diffusion atmospherique dont le but est de preciser la valeur des parametres introduits par la theorie tout en permettant de tenir compte de facteurs complementaires. - les etudes hydrologiques, hydrogeologiques et oceanographiques, qui permettent de preciser le sort des ions radioactifs dans l'hydrosphere. - les experiences et etudes liees aux possibilites de rejet ou de stockage des dechets dans le sol. L'ensemble de ces travaux constitue un moyen complementaire, la radioprotection, qui etablit une liaison necessaire entre la surete nucleaire proprement dite laquelle concerne le fonctionnement meme des installations nucleaires, et la surveillance medicale laquelle concerne directement la sante de l'individu et de la population. En meme temps,la radioprotection donne a chacune de ces disciplines une independance qui accroit leur efficacite sur le plan de la securite. (auteurs)

  11. 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

  12. Use of 14 MeV neutrons in activation analysis. Experiments carried out at the Grenoble nuclear research Centre (1963); Utilisation de neutrons de 14 MeV en analyse par activation. Experience realisee au Centre d'etudes nucleaires de Grenoble (1963)

    Energy Technology Data Exchange (ETDEWEB)

    Auboin, G; Guazzoni, P; Laverlochere, J [Commisariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

    1963-07-01

    The use of 14 MeV neutron irradiation makes it possible to extend the field of application of activation analysis to elements which cannot be activated in nuclear reactors (oxygen, boron, for example) or else to consider the possibility of 'portable' measurement units for routine analyses. With this aim, tests have been carried out for studying the sensitivity and interferences in the case of the dosing of oxygen in eleven different matrices using 150 and 300 kV SAMES accelerators producing 14 MeV neutrons by the reaction {sup 3}H (d, n) {sup 4}He. The sensitivity of the dosage methods for six writer elements has also been studied. The results obtained show that, for a neutron flux of 10{sup 10} n/4{pi}, the sensitivities vary from 100 {mu}g and 1 mg for oxygen in nine matrices (Be, Ta, Nb, Ti, Zr, Fe, Al, Sb, Si) and that it is possible to dose the six elements F, B, Y, Si, N, Al with sensitivities of between 1 an 1000 micrograms. (authors) [French] L'irradiation au moyen de neutrons de 14 MeV permet d'etendre le domaine d'application de l'analyse par activation a des elements non activables en reacteur nucleaire (oxygene, bore, par exemple) ou encore d'envisager des unites de dosage ''portables'' pour des analyses de routine. Dans ce but, des essais ont ete effectues pour etudier les sensibilites et les interferences dans le cas du dosage de l'oxygene dans onze matrices differentes, au moyen d'accelerateurs SAMES 150 et 300 kV. produisant les neutrons de 14 MeV par la reaction {sup 3}H (d, n) {sup 4}He. Des sensibilites de dosage ont egalement ete etudiees pour six autres elements. Les resultats obtenus montrent que, pour un flux de neutrons de 10{sup 10} n /4{pi}, les sensibilites varient entre 100 {mu}g et 1 mg, pour l'oxygene dans neuf matrices (Be, Ta, Nb, Ti, Zr, Fe, Al, Sb, Si) et qu'il est possible de doser les six elements F, B, Y, Si, N, Al avec des sensibilites se situant entre 1 et 1000 microgrammes. (auteurs)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

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

  14. Application of neutron activation analysis to the study of impurities in molybdenum, tungsten and nuclear graphite; Application de l'analyse par activation neutronique a l'etude des impuretes dans le molybdene, le tungstene et le graphite nucleaire

    Energy Technology Data Exchange (ETDEWEB)

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

    1967-10-15

    A neutron activation method is described for the analysis of a maximum number of foreign elements in molybdenum, tungsten and graphite. The various elements are isolated using a systematic separation programme; the elements are subsequently analysed qualitatively and quantitatively using {gamma}-spectrometry. By this method are dosed 27 elements in molybdenum and tungsten, and 20 elements in graphite to which can be added those elements which are already the object of routine analysis: V, Mn, Si, P, S, Cl and 14 rare earths. (author) [French] On decrit une methode d'analyse par activation neutronique permettant de doser un maximum d'elements etrangers dans le molybdene, le tungstene et le graphite. En suivant un schema de separation systematique, on isole les differents elements dont les analyses qualitatives et quantitatives sont ensuite effectuees par spectrometrie {gamma}. Par cette methode, on dose 27 elements dans le molybdene et le tungstene, 20 elements dans le graphite, auxquels on peut encore ajouter les elements doses couramment: V, Mn, Si, P, S, Cl et 14 Terres Rares. (auteur)

  15. 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

  16. The radioactive wastes management; Le dossier: les dechets nucleaires et leur gestion

    Energy Technology Data Exchange (ETDEWEB)

    Rigny, P. [Actualite Chimique, 75 - Paris (France); Bonin, B. [CEA Saclay, Dir. de l' Energie Nucleaire, 91 - Gif sur Yvette (France); Gras, J.M. [Electricite de France (EDF-RD), Recherche et Developpement, 78 - Chatou (France)

    2010-11-15

    The different types of radioactive waste are presented in this paper in the frame of the official categories which take into account their dangerousness and the lifetimes of their radioactivity. It is indicated how the less dangerous of them are handled in France. The ways of protecting the environment from the more dangerous ones (high activity and long lifetimes) are object of studies. Scientific questions, in the field of chemistry and physical chemistry, related to the implementation of deep underground repository facilities with full respect of nuclear safety are presented. (authors)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2011-07-01

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

  18. French people and nuclear wastes; Les francais et les dechets nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    D' Iribarne, Ph [Centre National de la Recherche Scientifique (CNRS), 75 - Paris (France)

    2005-07-01

    On March 21, 2005, the French minister of industry gave to the author of this document, the mission to shade a sociological light on the radioactive wastes perception by French people. The objective of this study was to supply an additional information before the laying down in 2006 of the decisions about the management of high-level and long-lived radioactive wastes. This inquiry, carried out between April 2004 and March 2005, stresses on the knowledge and doubts of the questioned people, on the vision they have of radioactive wastes and of their hazards, and on their opinion about the actors in concern (experts, nuclear companies, government, anti-nuclear groups, public). The last two parts of the report consider the different ways of waste management under study today, and the differences between the opinion of people living close to the Bure site and the opinion of people living in other regions. (J.S.)

  19. Radioactive wastes: a world problem. Les dechets nucleaires: un probleme mondial

    Energy Technology Data Exchange (ETDEWEB)

    Schapira, J P [Centre National de la Recherche Scientifique (CNRS), 75 - Paris (FR)

    1991-02-01

    In all countries endowed with nuclear program, radioactive wastes disposal asks scientific and public acceptance problems. This paper describes several aspects: technical problem; ethic problem and responsibility towards future generations at very long-term; political problem. Different politics followed by concerned countries and recent controversy in France is also entered upon radioactive wastes underground site selection, in deep geological formations.

  20. The wastes of nuclear fission; Les dechets de la fission nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Doubre, H. [Paris-11 Univ., Centre de Spectrometrie Nucleaire et de Spectrometrie de Masse, IN2P3/CNRS, 91 - Orsay (France)

    2005-07-01

    In this paper the author presents the problems of the radioactive wastes generated by the nuclear fission. The first part devoted to the fission phenomenon explains the incident neutron energy and the target nuclei role. The second part devoted to the nuclear wastes sources presents the production of wastes upstream of the reactors, in the reactors and why these wastes are dangerous. The third part discusses the radioactive wastes management in France (classification, laws). The last part details the associated research programs: the radionuclides separation, the disposal, the underground storage, the transmutation and the thorium cycle. (A.L.B.)

  1. Plutonium, nuclear fuel; Le plutonium, combustible nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Grison, E [Commissariat a l' Energie Atomique, Fontenay aux Roses (France). Centre d' Etudes Nucleaires, Saclay

    1960-07-01

    A review of the physical properties of metallic plutonium, its preparation, and the alloys which it forms with the main nuclear metals. Appreciation of its future as a nuclear fuel. (author) [French] Apercu sur les proprietes physiques du plutonium metallique, sa preparation, ses alliages avec les principaux metaux nucleaires. Consideration sur son avenir en tant que combustible nucleaire. (auteur)

  2. Problems related with the power regulation of reactors by physico-chemical methods, and the behaviour of water and heavy water in nuclear reactors; Comportement de l'eau et de l'eau lourde dans les reacteurs nucleaires et problemes de la regulation de puissance par voie physico-chimique

    Energy Technology Data Exchange (ETDEWEB)

    Dolle, L; Conan, D; Dirian, G [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1964-07-01

    Experience of the CEA heavy water reactors and a systematic study of the radiolytic decomposition of water in the core of swimming-pool reactors are described. Setting up of reactivity control by physico-chemical methods. Reactivity control by homogeneous poisoning of the reactor A comparison of the evolution of xenon poisoning with the residual anti reactivity of the poison in solution during its nuclear consumption establishes the programme which must govern the variation in its concentration if the exact compensation is to be produced The behaviour of the poison towards the reactor materials under the particular operational conditions must be taken into account. Radiolytic decomposition of water in the reactors in the presence of soluble poisons: A study of the effect of certain chemically inert salts, present in small concentrations in the water, on its radiolytic decomposition rate, has led to some new results which are discussed. The choice of a soluble poison is justified on the basis of the above results. Reactivity control by the use of a gaseous absorbent The use of a gas control rod circuit for compensation purposes, in place of solid control rods is described. The use of soluble poisons in the moderator to compensate the xenon effect, and of a gaseous absorbent in a circuit known as a gas control rod form original aspects of the reactivity control in the reactor EL 4. (authors) [French] L'observation du comportement de l'eau et de l'eau lourde dans les reacteurs en exploitation, contribue au fonctionnement sur de ceux-ci et oriente certaines etudes relatives aux techniques de controle de la reactivite par mise en oeuvre de poisons solubles. L'utilisation de poisons nucleaires dissous dans l'eau du reacteur entraine une pollution chimique de celle-ci. Les conditions d'emploi permettant d'eviter les effets indesirables de cette pollution sont etudiees. Les problemes analytiques - bien qu'importants - ne sont pas abordes dans le cadre de la communication

  3. 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)

  4. 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)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

  6. Exit this way; Par ici la sortie du nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    This paper aims to inform the public on the nuclear power phaseout necessity. The fist part presents the hazards bound the nuclear activities, from the uranium mines to the radioactive wastes disposal and the reasons of a necessary phaseout. The second part recalls the historical aspects of the nuclear power implementation in the french energy policy and the today government attitude to value its choice. The last part presents the advantages of other energies sources and scenario of nuclear power phaseout. (A.L.B.)

  7. Limits to the Recognizability of Flaws in Non-Destructive Testing Steam-Generator Tubes for Nuclear-Power Plants; Limitations de l'Efficacite de la Detection des Defauts par Essais Non Destructifs de Tubes de Bouilleurs pour Centrales Nucleaires; Predely ehffektivnosti nedestruktivnoj defektoskopii trub parogeneratorov yadernykh ehlektrostantsij; Limites para Distinguir los Defectos en el Ensayo No Destructivo de Tubo para Generadores de Vapor Destinados a Centrales Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Kuhlmann, A.; Adamsky, F. -J. [Technischer Ueberwachungs-Verein Reinland e.V., Cologne (Germany)

    1965-10-15

    -Verein' de Rhenanie qui a ete charge de surveiller et de controler la fabrication et le montage des bouilleurs, pour garantir que cet element de la centrale soit aussi exempt que possible de defauts. L'experience acquise dans l'execution de ces travaux peut etre tres utile pour la fabrication et le montage des bouilleurs de n'importe quel type de centrale nucleaire. Le memoire traite des limitations de l'efficacite des essais non destructifs de tubes de bouilleurs. Les auteurs discutent plus particulierement les essais ci-apres: a) Controle automatique par ultrasons de tubes droits dans l'usine de production; b) Controle combine, par ultrasons et par radiographie, de tubes coudes et de soudures; c) Autres controles non destructifs. (author) [Spanish] En la Republica Federal de Alemania se estan construyendo reactores nucleares con generadores de vapor situados en el interior del tanque de presion. Las caracteristicas de este modelo dificultan considerablemente la reparacion de los tubos del generador que puede llegar a paralizar la central nuclear por largos periodos. Como es bien sabido, muchas de las dificultades para mantener en funcionamiento las centrales nucleares de tipo clasico provienen de averias en los tubos del generador de vapor. Por ello, y teniendo tambien en cuenta como razon no menos importante el elevado costo total de esos reactores, es preciso construir los generadores de vapor de tal manera que el factor carga de la central sea lo mas elevado posible. El Technischer Ueberwachungs-Verein Rheinland se encarga de dirigir e inspeccionar la fabricacion y la construccion de generadores de vapor para que esa parte de las instalaciones carezca en lo posible de defectos. La experiencia adquirida a ese respecto ofrece ademas interes para la fabricacion y construccion de los generadores de vapor que se destinan a las centrales nucleares en general. En la presente memoria se examinan los limites de rendimiento del ensayo no destructivo de los tubos para generadores

  8. The formation of scientists and technicians at the 'Centre d'Etudes Nucleaires' at Saclay; Formation des scientifiques et des techniciens au Centre d'Etudes Nucleaires de Saclay

    Energy Technology Data Exchange (ETDEWEB)

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

    1958-07-01

    The considerable needs in research workers and scientists which are asked by the nuclear energy obliged the Commissariat a l'Energie atomique to deal with a particular effort to increase the quantitative and qualitative formation of scientists. Most various ways have been used. 1- A National Institute of Nuclear Sciences and Nuclear Techniques was created, by a joint decree of the Prime Minister and the Minister for National Education (june 18, 1957). This Institute of Higher Teaching (250 students) indulges in the following matters: atomic engineering, quantum mechanics, theory and technic of particle accelerators, special metallurgy, radiobiology, thermic and mechanics of fluids. 2- An associated centre of the 'Conservatoire National des Arts et Metiers' waeated (200 students) for technical assistants, drawers, etc. 3- In contribution with both electronic industry and Ministry of Work, the Centre d'Etudes Nucleaires contributes to an accelerated formation of technical assistants into Professional Centres. Conclusion: Training of scientists and research workers is one of the most important activities of the Centre d'Etudes Nucleaires de Saclay. Without losing its technical efficiency, it has supplied and varied means adapted to the various purposes that we shall reach. (author)Fren. [French] Les besoins considerables actuels et previsibles en chercheurs et scientifiques necessites par l'avevement de l'energie nucleaire imposaient au Commissariat a I'Energie atomique un effort particulier pour augmenter la formation quantitative et qualitative des scientifiques. Les moyens les plus divers ont ete mis en oeuvre: 1- Creation de l'Institut National des Sciences et Techniques Nucleaires par decret de la Presidence du Conseil et de l'Education Nationale en date du 18.6.57. Cet Institut d'Enseignement Superieur (250 etudiants) donne des cours en: genie atomique, mecanique quantique, theorie et technique des Accelerateurs de particules, metallurgie speciale, radiobiologie

  9. 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

  10. The study of some thiazinic and indaminic dye syntheses induced by ionising radiation; Etude de quelques syntheses de colorants thianziniques et indaminiques amorcees par les rayonnements ionisants

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-03-15

    With a view to finding some radiochemical reactions applicable on an industrial scale for evaluating the radioactive waste from nuclear reactors, a systematic study was made of the radiochemical synthesis of thiazinic dyes such as methylene blue and Lauths' violet, on which the first tests were carried out in 1954. The first part of the study concerned the identification and the dosage, during radiolysis, of dyes by means of their absorption spectra after separation from the reaction medium by adsorption chromatography or ion-exchange; other radiolysis products such as ammonium chloride and hydrogen peroxide were also identified. During a later stage by systematically varying the physico-chemical parameters it was possible to determine the most favourable conditions for radio-synthesis; the maximum radiochemical yields obtained had the following values: G (Lauths' violet) 1,65; G (Methylene blue) = 1,75. Furthermore, the study of the influence of variously substituted aminated products on the radiochemical yield showed the possibility of synthesising Bindsehedlers green and Wursters blue by radiochemical methods. Finally the discovery of a fundamental intermediate product, Wursters red, together with the kinetic study of the chemical synthesis of methylene blue made it possible to determine the main stages of the reaction mechanism and to decide which of these stages could be attributed to ionising radiations in the case of the radiochemical synthesis. (author) [French] Dans le but de trouver des reactions radiochimiques susceptibles d'une application industrielle pour valoriser les dechets radioactifs provenant des reacteurs nucleaires, il a ete entrepris une etude systematique de la synthese radiochimique des colorants thiazimiques tels que le Bleu de Methylene et le Violet de Lauth dont les premiers essais ont ete effectues par Loiseleur en 1954. La premiere partie de l'etude a porte sur l'identification et le dosage des colorants formes au cours de la radiolyse

  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. 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

  13. Nuclear explosion and internal contamination; Explosion nucleaire et contamination interne

    Energy Technology Data Exchange (ETDEWEB)

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

    1956-07-01

    By the study of the conditions of internal contamination due to the radioactive mixture produced by a nuclear explosion, the parts played by the relative weights of the different elements and the mode of expression of the doses are considered. Only the knowledge of the weight composition of the contamination mixture and of its evolution as a function of time can provide the required basis for the study of its metabolism in the organism. The curves which give the composition of the fission product mixture - in number of nuclei - - as a function of time - have been established. These curves are applied to some practical examples, particularly relative to the nature of contamination, radiotoxicity of some elements and assessment of hazards. (author) [French] Etudiant les modalites de la contamination interne par les elements radioactifs apparus lors d'une explosion nucleaire, le role de la 'masse' et le mode d'expression des doses sont envisages. La connaissance de la composition en 'masse' du melange contaminant et de son evolution en fonction du temps peut seule apporter les bases necessaires a l'etude de son comportement dans l'organisme. Les courbes donnant la composition du melange de produits de fission - en nombre de noyaux - - en fonction du temps - ont ete etablies. Quelques applications pratiques, relatives en particulier a la nature de la contamination, a la radiotoxicite de certains elements et a l'evaluation de risque, sont envisagees a titre d'exemple. (auteur)

  14. Contribution to the study of nuclear resonance in magnetic media (1963); Contribution a l'etude de la resonance nucleaire dans les milieux magnetique (1963)

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-06-15

    An attempt is made to interpret the results of nuclear magnetic resonance experiments made by various workers on ferro and ferrimagnetic compounds of the iron group. The problems encountered are the following: effects of the dipolar fields and the hyperfine structure anisotropy; signal intensity; frequency pulling due to the Suhl-Nakamura interaction between nuclear spins ; nuclear relaxation and ferrimagnetic resonance in single domain samples of impure YIG; nuclear relaxation in the Bloch walls of insulators. The results of our calculations are generally in good agreement with experiment. (author) [French] On se propose d'interpreter les resultats d'experiences de resonance magnetique nucleaire fates par divers auteurs sur des composes ferro et ferrimagnetiques du groupe du fer. Les problemes abordes sont les suivants: effets des champs dipolaires et de l'anisotropie de structure hyperfine; intensite des signaux; deplacement de frequence du a l'interaction de Suhl-Nakamura entre spins nucleaires; relaxation nucleaire et resonance ferrimagnetique dans les echantillons monodomaines de grenat de fer et d'yttrium impur; relaxation nucleaire dans les parois de Bloch des isolants. Les resultats des calculs sont generalement en bon accord avec l'experience. (auteur)

  15. Contribution to the study of nuclear resonance in magnetic media (1963); Contribution a l'etude de la resonance nucleaire dans les milieux magnetique (1963)

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-06-15

    An attempt is made to interpret the results of nuclear magnetic resonance experiments made by various workers on ferro and ferrimagnetic compounds of the iron group. The problems encountered are the following: effects of the dipolar fields and the hyperfine structure anisotropy; signal intensity; frequency pulling due to the Suhl-Nakamura interaction between nuclear spins ; nuclear relaxation and ferrimagnetic resonance in single domain samples of impure YIG; nuclear relaxation in the Bloch walls of insulators. The results of our calculations are generally in good agreement with experiment. (author) [French] On se propose d'interpreter les resultats d'experiences de resonance magnetique nucleaire fates par divers auteurs sur des composes ferro et ferrimagnetiques du groupe du fer. Les problemes abordes sont les suivants: effets des champs dipolaires et de l'anisotropie de structure hyperfine; intensite des signaux; deplacement de frequence du a l'interaction de Suhl-Nakamura entre spins nucleaires; relaxation nucleaire et resonance ferrimagnetique dans les echantillons monodomaines de grenat de fer et d'yttrium impur; relaxation nucleaire dans les parois de Bloch des isolants. Les resultats des calculs sont generalement en bon accord avec l'experience. (auteur)

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1990-11-03

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

  17. An absolute nuclear magnetic resonance magnetometer; Magnetometre absolu a resonance magnetique nucleaire

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-10-15

    After an introduction in which the various work undertaken since the discovery of nuclear magnetic resonance is rapidly reviewed, the author describes briefly In the first chapter three types of NMR magnetometers, giving the advantages and disadvantages of each of them and deducing from this the design of the apparatus having the greatest number of qualities Chapter II is devoted to the crossed coil nuclear oscillator which operates continuously over a wide range (800 gamma). To avoid an error due to a carrying over the frequency, the measurement is carried out using bands of 1000 {gamma}. Chapter III deals with frequency measurements. The author describes an original arrangement which makes possible the frequency-field conversion with an accuracy of {+-} 5 x 10{sup -6}, and the differential measurement between two nuclear oscillators. The report finishes with a conclusion and a few recordings. (author) [French] Apres une introduction rappelant les divers travaux effectues en resonance magnetique nucleaire depuis sa mise en evidence, l'auteur decrit sommairement dans le premier chapitre trois types de magnetometre a R.M.N. enumerant les avantages et les inconvenients de chacun a partir desquels il projet, l'appareillage reunissant le maximum de qualites. Le chapitre II est consacre a l'oscillateur nucleaire a bobines croisees permettant un fonctionnement continu dons une large plage (800 gamma). Pour eviter une erreur due a l'entrainement de frequence, la mesure s'effectue par bandes de 1000 {gamma} chacune. Le chapitre III traite la mesure de frequence. L'auteur expose un montage original permettant la traduction frequence-champ avec une precision egale a {+-} 5.10{sup -6}, et la mesure differentielle entre deux oscillateurs nucleaires. Une conclusion et quelques enregistrements terminent ce travail. (auteur)

  18. Radioactive waste and its impact on the environment; Les dechets nucleaires: quel impact sur l'environnement?

    Energy Technology Data Exchange (ETDEWEB)

    Bonin, B. [Institut de Radioprotection et de Surete Nucleaire en Detachement a Cogema, Dir. de la Recherche et du Developpement, 78 - Velizy (France)

    2002-07-01

    What impact will radioactive waste have on the environment and mankind ultimately? If category B waste and all or some of category C waste is disposed of in a deep geological facility, after an interim storage period which presents its own risks, scientists can now predict that its worst case impact will be minimal and localized. While they cannot strictly demonstrate the safety of disposal over the time scales in question, they can nevertheless vouch for sound, well-engineered design. They can furnish a whole host of convergent evidence to demonstrate that they really have thought of all the events that could affect radioactive packages disposed of in a given environment, separated from the biosphere by barriers with well-defined properties. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2011-02-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Lelievre, F

    1998-12-11

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Prunier, C; Pacton, L

    1994-12-31

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

  3. A study of filtering problems of background noise in nuclear spectrometry, improvement of signal-to-noise ratio, and of pulse characteristics produced by the optimum predictor device; Etude de problemes de filtrage de bruit de fond en spectrometrie nucleaire, amelioration du rapport signal sur bruit et des caracteristiques de l'impulsion mise en forme par le dispositif du predicteur optimum

    Energy Technology Data Exchange (ETDEWEB)

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

    1967-05-01

    The purpose of nuclear spectrometry is the precise measurement of particles energy. The resolving power of a spectrometer design is an important factor. Two main phenomena are involved in the limitation of this resolving power: The statistical fluctuations of the detector itself, and the background noise. For a given noise, the theory of filters enables the calculation of networks specially designed for the improvement of signal to noise ratio. The proposed system should lead to an improvement of 10.5 per cent of this ratio. Experiments have confirmed this theoretical estimation. The predictor device also makes possible the obtaining of shortened pulses. (author) [French] Les mesures en spectrometrie nucleaire ont pour but la determination precise de l'energie des particules. Le pouvoir de resolution d'une chaine de spectrometrie est une caracteristique importante. Deux phenomenes principaux concourent a limiter ce pouvoir de resolution: les fluctuations statistiques du detecteur et le bruit de fond. Pour un bruit de fond donne, la theorie des filtres permet de calculer des reseaux susceptibles de modifier le rapport signal sur bruit. Le systeme propose permet d'ameliorer de 10.5 pour cent ce rapport lorsqu'on se place dans les conditions optimales. Les resultats experimentaux confirment les previsions. Le dispositif predicteur permet aussi un raccourcissement de l'impulsion dans le temps. (auteur)

  4. Statistical pulses generator. Application to nuclear instrumentation (1962); Generateur d'impulsions aleatoires. Application a l'instrumentation nucleaire (1962)

    Energy Technology Data Exchange (ETDEWEB)

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

    1962-07-01

    This report describes a random pulses generator adapted to nuclear instrumentation. After a short survey on the statistical nature of electronic signals, the different ways for generating pulses with a Poisson's time-distribution are studied. The final generator built from a gaseous thyratron in a magnetic field is then described. Several tests are indicated : counting-rate stability, Pearson's criterion, distribution of time-intervals. Applications of the generator in 'whole testing' of nuclear instrumentation are then indicated for sealers, dead time measurements, time analyzers. In this application, pulse-height spectrums have been made by Poissonian sampling of a recurrent or random low-frequency signal. (author) [French] Cette etude decrit un generateur d'impulsions aleatoires et ses applications a l'instrumentation nucleaire. Apres un bref rappel sur la nature statistique des signaux en electronique nucleaire, sont passes en revue les principaux moyens d'obtenir des impulsions distribuees en temps suivant une loi de Poisson. Le generateur utilisant un thyratron a gaz dans un champ magnetique est ensuite decrit; diverses methodes de test sont appliquees (stabilite du taux de comptage, criterium de Pearson, spectre des intervalles ds temps). Les applications du generateur a l'electronique nucleaire dans le domaine des 'essais globaux' sont indiques: test des echelles de comptage et mesure des temps morts, test des analyseurs en temps apres division du taux de comptage par une puissance de deux, test des analyseurs multicanaux en amplitude. Pour cette derniere application, on a realise des spectres d'amplitudes suivant une loi connue, par echantillonnage poissonien d'un signal basse frequence recurrent ou aleatoire. (auteur)

  5. Evolution of nuclear chemical industry in France; Evolution de l'industrie chimique nucleaire en France

    Energy Technology Data Exchange (ETDEWEB)

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

    1959-07-01

    'impulsion du CEA, mais aussi de maitres d'oeuvres tels qu'Electricite de France et la Marine Marchande, l'effort nucleaire fran is atteint pour les annees 1957-1961, environ 600 milliards de francs: plus de la moitie de cette somme sera depensee par l'industrie chimique en recherches, installations pilotes, constructions d'usines et livraisons. Faire bien, vite et rentable sont les buts recherches. Ces objectifs sont atteints grace a une collaboration intime des grands services de l'etat et de l'industrie privee. Ce gros effort s'exerce principalement dans les voies suivantes: - Un traitement chimique pousse de tonnages croissants des minerais de l'Union fran ise, visant a produire un uranium pur, abondant et bon marche. - Une preparation soigneuse de combustibles nucleaires economiques et parfaitement adaptes aux divers types de reacteurs en fonctionnement ou en construction. - Un retraitement des combustibles irradies pour en extraire le plutonium de facon complete ainsi que l'uranium et certains produits de fission. - Une fabrication industrielle des materiaux nucleairement purs ou resistants a la corrosion exiges par la technologie des reacteurs producteurs d'energie et de recherches. - La fourniture aux multiples utilisateurs etrangers et fran is d'isotopes et de traceurs radioactifs reclames par la medecine, l'industrie et l'agriculture en nombre toujours croissant. - Un traitement chimique meticuleux des effluents gazeux ou liquides dans des stations au controle rigoureux afin de rendre les reacteurs et leurs annexes parfaitement surs d'emploi. Cet expose aura montre l'ampleur de l'effort deploye par une industrie chimique nucleaire jeune, dynamique et en plein essor. Ayant assure ses techniques, realise de nombreuses installations, elle est largement en etat de faire face au programme atomique fran is. En outre, elle est capable et desireuse d'etre associee aux developpements de l'industrie atomique etrangere notamment dans te cadre de l'Euratom et d

  6. Direct interaction in nuclear reactions: a theory; L'interaction directe dans les reactions nucleaires: theorie

    Energy Technology Data Exchange (ETDEWEB)

    Dominicis, C.T. de [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1959-07-01

    General treatment of the foundations of direct interaction in nuclear reactions; representation of the instantaneous elastic scattering amplitude by the scattering amplitude due to a complex potential; expansion of the instantaneous inelastic scattering amplitude and discussion of the 1. Bohr approximation (distorted waves) contribution to individual and collective states of excitation. (author) [French] Expose general sur les fondements de l'interaction directe dans les reactions nucleaires; representation de l'amplitude de diffusion instantanee elastique par celle due a un potentiel complexe; developpement de l'amplitude de diffusion instantanee inelastique et discussion de la contribution de la premiere approximation de Bohr (sur des distendues) a l'excitation d'etats individuels et collectifs. (auteur)

  7. French research in the field of nuclear agronomy; Les recherches francaises en agronomie nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Guerin De Montgareuil, P. [Commissariat a l' Energie Atomique, Cadarache (France). Centre d' Etudes Nucleaires

    1964-07-01

    , industrial firms, university laboratories scientific institutes. The role of the Commissariat a l'Energie Atomique is defined: on the one hand it supplies information and support, and on the other hand it takes charge of specifically nuclear aspects of the work. Its part in the field has recently found expression in the creation, within the Biology Department, of a Radio-agronomy Section; its objective are described,, as well as the, means placed att its disposal at the Centre d'etudes Nucleaires, Cadarache. (author) [French] On propose un bilan des travaux les plus significatifs effectues en France depuis la deuxieme conference internationale en matiere d'agronomie nucleaire et qui vont d'une recherche apparemment desinteressee a l'application la plus directe. Une telle differenciation recouvre de moins en moins, au fur et a mesure de l'evolution des programmes, la distinction qui est faite dans l'expose entre l'action biologique des rayonnements et les autres emplois des techniques nucleaires. C'est ainsi que les recherches do radiogenetique agricole sont poursuivies dans deux directions: d'un point de vue theorique et methodologique avec l'etude comparative de l'action des divers types de rayonnements, l'influence du debit de dose et de la temperature, l'action des agents mutagenes chimiques, la production de chimeres sous irradiation gamma; et d'autre part, sous un aspect pratique aboutissant a la creation de varietes nouvelles plus resistantes ou plus precoces (riz, mil, arachide). Les problemes de destruction des insectes (eradication) et de conservation des denrees sous irradiation se trouvent egalement abordes par des voies et avec des objectifs tres divers. A la demarche globale representee par une irradiation pure et simple (grains humides, pommes de terre...) sont parfois associees des etudes souvent originales, d'ordre biochimique ou microbiologique (par exemple: alteration de l

  8. French research in the field of nuclear agronomy; Les recherches francaises en agronomie nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Guerin De Montgareuil, P [Commissariat a l' Energie Atomique, Cadarache (France). Centre d' Etudes Nucleaires

    1964-07-01

    , industrial firms, university laboratories scientific institutes. The role of the Commissariat a l'Energie Atomique is defined: on the one hand it supplies information and support, and on the other hand it takes charge of specifically nuclear aspects of the work. Its part in the field has recently found expression in the creation, within the Biology Department, of a Radio-agronomy Section; its objective are described,, as well as the, means placed att its disposal at the Centre d'etudes Nucleaires, Cadarache. (author) [French] On propose un bilan des travaux les plus significatifs effectues en France depuis la deuxieme conference internationale en matiere d'agronomie nucleaire et qui vont d'une recherche apparemment desinteressee a l'application la plus directe. Une telle differenciation recouvre de moins en moins, au fur et a mesure de l'evolution des programmes, la distinction qui est faite dans l'expose entre l'action biologique des rayonnements et les autres emplois des techniques nucleaires. C'est ainsi que les recherches do radiogenetique agricole sont poursuivies dans deux directions: d'un point de vue theorique et methodologique avec l'etude comparative de l'action des divers types de rayonnements, l'influence du debit de dose et de la temperature, l'action des agents mutagenes chimiques, la production de chimeres sous irradiation gamma; et d'autre part, sous un aspect pratique aboutissant a la creation de varietes nouvelles plus resistantes ou plus precoces (riz, mil, arachide). Les problemes de destruction des insectes (eradication) et de conservation des denrees sous irradiation se trouvent egalement abordes par des voies et avec des objectifs tres divers. A la demarche globale representee par une irradiation pure et simple (grains humides, pommes de terre...) sont parfois associees des etudes souvent originales, d'ordre biochimique ou microbiologique (par exemple: alteration de l'amidon, metabolisme glucidique des tubercules irradies, radioresistance des levures

  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. 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)

  11. 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

    diverses periodes geologiques ; 2. L'impermeabilite du sel a l'ecoulement d'eau; 3. La vaste repartition geographique du sel; 4. Les enormes quantites de sel existantes ; 5. La solidite structurale du sel; 6. La conductivite thermique relativement elevee du sel par rapport a d'autres formations geologiques generales; 7. La recuperation eventuelle de precieux produits de fission dans les dechets injectes dans le sel; 8. La facilite relative d'obtenir des excavations dans le sel par voie d'extraction, ainsi que la facilite encore plus grande et le cout reduit de la preparation dans le sol de cavites par voie de solution; 9. La faible seismicite constatee dans les zones des principaux gisements de sel. Les dechets radioactifs liquides peuvent etre emmagasines dans les cavites des formations de sel naturel, a condition que les proprietes structurales/du sel ne soient pas defavorablement influencees par les interactions chimiques, la pression, la temperature et les rayonnements. Il ressort d'etudes analytiques qu'on peut emmagasiner 3.200 litres (800 gallons) par tonne de dechets d'uranium irradie a 10.000 MWj/t, vieux de deux ans, dans une sphere de 3 metres (dix pieds) de diametre sans depasser une temperature de 93 Degree-Sign C (200 Degree-Sign F). Des essais de laboratoire montrent que les proprietes structurales et la conductivite thermique du sel gemme ne sont pas sensiblement transformees par des doses de rayonnements intenses, bien que les temperatures elevees augmentent le taux de fluage des echantillons irradies et non irradies. Les interactions chimiques de dechets liquides avec du sel donnent naissance a du chlore et a des composes gazeux du chlore, mais les volumes n'en sont pas excessifs. Les migrations des nuclides a travers le sel ainsi que la deformation de la cavite ne peuvent etre etudiees que sur place dans le sel vierge. Des maquettes a l'echelle de 1/5 ont ete essayees a Hutchinson (Kansas) dans un gisement de sel; des essais d'une certaine importance

  12. Production of nuclear graphite in France; Production de graphite nucleaire en France

    Energy Technology Data Exchange (ETDEWEB)

    Legendre, P; Mondet, L [Societe Pechiney, 74 - Chedde (France); Arragon, Ph; Cornuault, P; Gueron, J; Hering, H [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1955-07-01

    The graphite intended for the construction of the reactors is obtained by the usual process: confection of a cake from coke of oil and tar, cooked (in a electric oven) then the product of cook is graphitized, also by electric heating. The use of the air transportation and the control of conditions cooking and graphitization have permitted to increase the nuclear graphite production as well as to better control their physical and mechanical properties and to reduce to the minimum the unwanted stains. (M.B.) [French] Le graphite destine a la construction des reacteurs est obtenu par le procede usuel: confection d'une pate a partir de coke de petrole et de brai, cuisson de cette pate (au four electrique) puis graphitation du produit cuit, egalement par chauffage electrique. L'usage du transport pneumatique et le controle des conditions cuisson et de graphitation ont permit d'augmenter la production de graphite nucleaire ainsi que de mieux controler ses proprietes physiques et mecaniques et de reduire au minimum les souillures accidentelles. (M.B.)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

  14. France's nuclear power programme; Le programme nucleaire francais

    Energy Technology Data Exchange (ETDEWEB)

    Cabanius, J [Electricite de France (EDF), 75 - Paris (France); Horowitz, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1964-07-01

    -increasing importance, by using the country's resources of natural uranium, and later plutonium, to the best ends. (authors) [French] Les perspectives d'evolution de la consommation d'energie electrique francaise confirment l'aggravation du deficit des ressources energetiques metropolitaines. Les centrales nucleaires doivent permettre de diminuer ce deficit si un certain nombre d'incertitudes actuelles sont levees. Le premier programme presente par MM AILLERET et TARANGER a la Conference de Geneve en 1955 visait la mise en service pour 1965 de 850 MWe; il a ete consacre au developpement de la filiere uranium naturel - graphite - gaz et s'acheve avec la realisation d'EDF 3, premiere unite capable de 500 MWe engagee dans le monde. Avant de passer du stade des prototypes a celui des duplications, ELECTRICITE DE FRANCE a decide, en accord avec le COMMISSARIAT A L'ENERGIE ATOMIQUE, la realisation d'EDF 4 qui, en reprenant la partie reacteur d'EDF 3 ainsi que l'appareil de chargement et de dechargement, l'ensemble de controle et divers materiels, apporte une innovation importante en incorporant les echangeurs et les soufflantes a l'interieur du caisson en beton precontraint contenant le coeur. En meme temps, les etudes se poursuivent dans cette meme filiere et laissent entrevoir les possibilites d'utiliser un nouvel element combustible annulaire dont l'emploi ameliorerait notablement les performances d'EDF 5. Dans la filiere eau lourde, la realisation d'EL 4 a Brennilis par le COMMISSARIAT A L'ENERGIE ATOMIQUE et ELECTRICITE DE FRANCE se poursuit. Les etudes d'un reacteur de 500 MWe de cette filiere ont deja commence. Dans la filiere a eau pressurisee, la centrale de CHOOZ est realisee en association par ELECTRICITE DE FRANCE et les Producteurs Belges. Enfin, le COMMISSARIAT A L'ENERGIE ATOMIQUE poursuit a Cadarache la realisation du surgenerateur 'Rapsodie' et les etudes d'un reacteur de puissance plus important. Ainsi, les connaissances techniques et economiques acquises dans ces diverses

  15. Siloette, Siloe mock-up; Siloette, modele nucleaire de siloe

    Energy Technology Data Exchange (ETDEWEB)

    Delcroix, V; Jeanne, G; Mitault, G; Schulhof, P [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

    1964-07-01

    Siloette is the Siloe mock-up. The main installations are described: various tanks, building, auxiliaries, control systems... Precis ions are given about precautions taken for using spent fuel elements. (authors) [French] Siloette est le modele nucleaire de SILOE. On decrit ses diverses installations: bassins, batiments, auxiliaires, controle... Des precisions sont donnees sur les precautions prises pour y utiliser des elements uses. (auteurs)

  16. Contribution to the study of nuclear structure using neutron total cross-section measurements between 400 and 1200 keV: isolated resonances and intermediate structure; Contribution a l'etude de la structure nucleaire par des mesures de sections efficaces neutroniques entre 400 keV et 1200 keV. Resonances isolees et structure intermediaire

    Energy Technology Data Exchange (ETDEWEB)

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

    1967-06-15

    The neutron total cross sections have been measured over the energy range 400 keV - 1200 keV for fluorine, aluminium, silicon, phosphorus, vanadium, chromium, manganese, iron, nickel, cobalt and lead with an energy spread of 3 keV. The neutrons were produced by the T (p,n) {sup 3}He reaction, the proton beam was supplied by a 2 MeV Van de Graaff. The structure in {sup 56}Fe has been studied in a more detailed way by measuring six angular distributions in the above range and the elastic scattering excitation curves at four angles. The measurements have made it possible to show the existence of the compound nucleus, as well as the presence of an intermediate structure in certain nuclei. (author) [French] Nous avons mesure les sections efficaces totales neutroniques entre 400 keV et 1200 keV du fluor, de l'aluminium, du silicium, du phosphore, du vanadium, du chrome, du manganese, du fer, du nickel, du cobalt et du plomb avec une dispersion en energie de 3 keV. Les neutrons etaient produits a l'aide de la reaction T (p,n) {sup 3}He, les protons etant acceleres par un Van de Graaff 2 MeV. Nous presentons de plus quatre courbes d'excitation de la diffusion elastique des neutrons sur le fer ainsi que six distributions angulaires. Ces mesures ont permis de mettre en evidence un certain nombres de resonances du noyau compose, ainsi que la presence d'une structure intermediaire dans. certains noyaux. (auteur)

  17. Primary Distributions of Nuclear Charge for Fission-Fragment Masses 132, 134, 136 and 137 from Thermal Fission of U{sup 235}; Repartition Primaire de la Charge Nucleaire pour les Fragments de Masse 132, 134, 136 et 137, Provenant de la Fission de {sup 235}U par Neutrons Thermiques; 041f 0415 0420 0414 ; Distribuciones Primarias de las Cargas Nucleares de los Fragmentos de Masa 132, 134, 136 y 137, Resultantes de la Fision del {sup 235}U por Neutrones Termicos

    Energy Technology Data Exchange (ETDEWEB)

    Konecny, E.; Opower, H.; Guenther, H.; Goebel, H. [Physik-Department der Technischen Hochschule Muenchen, Munich and II. Physikalisches Institut der Justus Liebig-Universitaet Giessen, Federal Republic of Germany (Germany)

    1965-07-15

    the statistical error arising from the transformation from 2{pi}- to 4{pi}-distribution, and for various kinetic energies as parameters, are in preparation. (author) [French] A l'aide d'un spectrometre de masse, on separe avec precision les fragments de la fission thermique de {sup 235}U d'apres leur masse et leur energie cinetique dans la microseconde qui suit la fission. Les fragments separes sont retenus dans une emulsion Ilford G 5 sensible aux particules {beta}, qui est placee dans le plan focal du spectrometre. Les emulsions irradiees sont developpees, dans la mesure du possible, apres un delai relativement long par rapport a la periode la plus longue de la serie radioactive consideree. Les periodes de l'ordre de plusieurs jours ou plus longues encoxe ne sont pas prises en consideration, mais il est facile d'appliquer un facteur de correction approprie. Apres avoir developpe les emulsions, on peut observer au microscope toutes les traces {beta} qui prolongent chacune des traces de fragments de fission. La possibilite d'etablir une correlation entre une trace {beta} et une trace de fragment de fission permet d'evaluer le nombre n(x) de fragments de fission possedant un nombre x de traces {beta}, ce qui indique non seulement la longueur moyenne de la serie mais aussi la distribution des particules {beta}. Le nucleide stable de chaque serie etant connu, la distribution des particules {beta} constitue une image exacte de la repartition primaire des charges nucleaires. Au cours des mesures effectuees jusqu'a present, on n'a en-' registre que les particules {beta} emises dans le demi-angle solide forme par la plaque d'emulsion, mais un calcul statistique simple permet d'evaluer la distribution. 4{pi} voulue. Grace a cette methode, on obtient la distribution des particules 0 a des energies cinetiques determinees proches de l'energie cinetique moyenne de chaque fragment pour les masses 132, 134, 136 et 137. Pour les masses 132 et 134, c'est a la couche de neutrons N

  18. Study of thick, nuclear-compensated silicon detectors; Etude des detecteurs epais au silicium compense nucleairement

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-09-01

    A study is made here, from the point of view of the realization and the performance, of thick nuclear-compensated silicon detectors. After recalling the need for compensation and reviewing the existing methods, the author describes in detail the controlled realization of thick detectors by nuclear compensation from the theoretical and experimental points of view. The practical precautions which should be observed are given: control of the homogeneity of the starting material, control of the evolution of the compensation, elimination of parasitic processes. The performances of the detectors obtained are then studied: electrical characteristics (current, life-time) on the one hand, detection and spectrometry of penetrating radiations on the other hand. The results show, that the compensated diodes having an effective thickness of two millimeters operate satisfactorily as detectors for applied voltages of about 500 volts. The resolutions observed are then about 2 per cent for mono-energetic electrons and about 4 per cent for the gamma; they can be improved by the use of a pre-amplifier of very low background noise. (author) [French] Les detecteurs epais au silicium compense nucleairement sont etudies ici du double point de vue realisation et performances. Apres un rappel sur la necessite de la compensation et les procedes existants, la realisation controlee des detecteurs epais par compensation nucleaire est decrite en detail sous l'aspect theorique et l'aspect experimental. On met en evidence les precautions a prendre dans la pratique: controle de l'homogeneite du materiau de base, controle de l'evolution de la compensation, elimination des processus parasites. On etudie ensuite les performances de detecteurs obtenus : caracteristiques electriques (courant, duree de vie) d'une part, d'autre part detection et spectrometrie des rayonnements penetrants. Les resultats montrent que les diodes compensees ayant une epaisseur utile de deux

  19. Neutron noise in nuclear reactors; Le bruit neutronique des reacteurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Blaquiere, A. [Institut National des Sciences et Techniques Nucleaires (France); Pachowska, R. [Universite Technique de Varsovie (Poland)

    1961-06-15

    The power of a nuclear reactor, in the operating conditions, presents fluctuations due to various causes. This random behaviour can be included in the study of 'noises'. Among other sources of noise, we analyse hereafter the fluctuations due: a) to the discontinuous emissions of neutrons from an independent source; b) to the multiplication of neutrons inside the reactor. The method which we present makes use of the analogies between the rules governing a nuclear reactor in operation and a number of radio-electrical systems, in particular the feed-back loops. The reactor can be characterized by its 'passing band' and is described as a system submitted to a sequence of random pulses. In non linear operating condition, the effect of neutron noise is defined by means of a non-linear functional, this theory is thus related to previous works the references of which are given at the end of the present report. This leads us in particular in the case of nuclear reactors to some results given by A. Blaquiere in the case of radio-electrical loops. (author) [French] La puissance d'un reacteur nucleaire, dans les conditions du regime, est affectee de fluctuations dont les causes sont tres diverses. Ce comportement aleatoire rentre dans le cadre general de l'etude des 'bruits'. Entre autres sources ce bruit, nous analysons ici les fluctuations dues: a) a l'emission discontinue des neutrons provenant d'une source autonome; b) a la multiplication des neutrons au sein du reacteur. La methode que nous introduisons exploite les analogies entre les lois qui regissent un reacteur nucleaire au regime et certains systemes radioelectriques, en particulier les circuits a boucle de reaction. Le reacteur est caracterise par sa 'bande passante' et est decrit comme un systeme soumis a une succession d'impulsions aleatoires. Dans les conditions de fonctionnement non lineaires, l'effet du bruit neutronique est precise en utilisant une fonctionnelle non lineaire, ce qui relie cette theorie a

  20. Study of thick, nuclear-compensated silicon detectors; Etude des detecteurs epais au silicium compense nucleairement

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-09-01

    A study is made here, from the point of view of the realization and the performance, of thick nuclear-compensated silicon detectors. After recalling the need for compensation and reviewing the existing methods, the author describes in detail the controlled realization of thick detectors by nuclear compensation from the theoretical and experimental points of view. The practical precautions which should be observed are given: control of the homogeneity of the starting material, control of the evolution of the compensation, elimination of parasitic processes. The performances of the detectors obtained are then studied: electrical characteristics (current, life-time) on the one hand, detection and spectrometry of penetrating radiations on the other hand. The results show, that the compensated diodes having an effective thickness of two millimeters operate satisfactorily as detectors for applied voltages of about 500 volts. The resolutions observed are then about 2 per cent for mono-energetic electrons and about 4 per cent for the gamma; they can be improved by the use of a pre-amplifier of very low background noise. (author) [French] Les detecteurs epais au silicium compense nucleairement sont etudies ici du double point de vue realisation et performances. Apres un rappel sur la necessite de la compensation et les procedes existants, la realisation controlee des detecteurs epais par compensation nucleaire est decrite en detail sous l'aspect theorique et l'aspect experimental. On met en evidence les precautions a prendre dans la pratique: controle de l'homogeneite du materiau de base, controle de l'evolution de la compensation, elimination des processus parasites. On etudie ensuite les performances de detecteurs obtenus : caracteristiques electriques (courant, duree de vie) d'une part, d'autre part detection et spectrometrie des rayonnements penetrants. Les resultats montrent que les diodes compensees ayant une epaisseur utile de deux millimetres fonctionnent

  1. Possibilities and limitations of analogue methods for studying the dynamics of nuclear power stations; Possibilites et limitations du calcul analogique pour les etudes dynamiques de centrales nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Caillet, C; Deat, M [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    1. Introduction: the present paper is devoted to analog simulation of problems related to nuclear reactors other than the simulation of the kinetic equations which is well known. 2. Thermodynamic problems: various problems relative to temperature evolution in a reactor, in a pipe, in an exchanger, in a turbine, are studied, and simulation techniques used by earlier authors are critically reviewed. 3. Pipe simulators: it is shown that this problem can be solved by the use of specialized simulators which will be described and analysed. 4. Rotating machine simulators: the particular aspect of rotating machine calculations introducing frequent use of diagrams is emphasized. A simulator requiring both digital and analogue methods is described. 5. The study of a nuclear power station: as an example it is proposed to discuss problems a rising in connection with the preceding elements (a, b, c, d) when simulating the behaviour of large nuclear plants. The part played by ordinary computing elements for the simulation of the different servomechanism transfer functions is considered and process of regulation is outlined. 6. Conclusion: the necessity of the use of high quality simulators and computers is underlined and the accuracy of the solutions is discussed. (author)Fren. [French] 1. Cinetique des reacteurs: la simulation des equations cinetiques d'un reacteur nucleaire ne pose desormais plus de probleme. II est donc possible de faire le point des differentes applications de la technique analogique dans ce domaine. 2. Les problemes thermodynamiques: on discute les differents problemes poses par l'evolution des temperatures dans un reacteur, dans une tuyauterie, dans un echangeur, dans une turbine, et on passe en revue les techniques de simulation proposees jusqu'a ce jour. 3s simulateurs de tuyauteries: on montre comment les differents problemes poses ci-dessus peuvent etre resolus, pour une classe tres vaste de reacteurs par l'emploi de simulateurs speciaux que l

  2. Molten salts in nuclear reactors; Les sels fondus dans les reacteurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Dirian, J; Saint-James, [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1959-07-01

    Collection of references dealing with the physicochemical studies of fused salts, in particular the alkali and alkali earth halides. Numerous binary, ternary and quaternary systems of these halides with those of uranium and thorium are examined, and the physical properties, density, viscosity, vapour pressure etc... going from the halides to the mixtures are also considered. References relating to the corrosion of materials by these salts are included and the treatment of the salts with a view to recuperation after irradiation in a nuclear reactor is discussed. (author) [French] Bibliographie regroupant l'etude physico-chimique des sels fondus, en particulier des halogenures alcalins et alcalino-terreux. On etudie de nombreux systemes binaires, ternaires et quaternaires de ces halogenures avec des halogenures d'uranium, et de thorium. On etudie egalement les proprietes physiques des halogenures ou des melanges d'halogenures (densite, viscosite, tension de vapeur, etc...). On donne egalement des references quant a la corrosion des materiaux par ces sels, et le traitement de ceux-ci en vue de recuperation, apres irradiation dans un reacteur nucleaire. (auteur)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-08-15

    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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

  6. Calculation of the shock-wave in the region close to an underground nuclear explosion (method Cades); Calcul de l'onde de choc en zone proche d'une explosion nucleaire souterraine (methode cades)

    Energy Technology Data Exchange (ETDEWEB)

    Supiot, F; Brugies, J [Commissariat a l' Energie Atomique, Bruyeres-le-Chatel (France). Centre d' Etudes

    1969-07-01

    The outline of a method is presented for calculating the characteristics of a shock wave produced by an underground nuclear explosion (pressure, wave velocity, velocity of the medium, energy left in the medium by the shock, etc.). By means of an application to a granitic medium and of a comparison with results obtained during French nuclear explosions, it has been possible to show the good agreement existing between the calculations and the experimental results. The advantages of such a method for studying the industrial applications of underground nuclear explosions are stressed. (authors) [French] On expose les grandes lignes d'une methode de calcul des caracteristiques de l'onde de choc issue d'une explosion nucleaire souterraine (pression, vitesse de l'onde, vitesse du milieu, energie deposee par le choc dans le milieu...). Une application a un milieu granitique et une comparaison aux resultats obtenus au cours d'explosions nucleaires francaises permet de montrer la bonne concordance entre le calcul et les resultats experimentaux. On souligne l'interet d'une telle, methode pour l'etude d'applications industrielles des explosions nucleaires souterraines. (auteurs)

  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. The dangers of irradiate uranium in nuclear reactors; Les dangers de l'uranium irradie dans les reacteurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

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

    1955-07-01

    The danger of the uranium cans sur-activated by the use in the nuclear reactors is triple: - Irradiation from afar, during manipulations of the cans. - Contamination of air when decladding. - Contamination of air by fire of uranium in a reactor in function The first two dangers are usual and can be treated thanks to the rules of security in use in the atomic industry. The third has an accidental character and claimed for the use of special and exceptional rules, overflowing the industrial setting, to reach the surrounding populations. (authors) [French] Le danger des cartouches d'uranium suractive par utilisation dans les reacteurs nucleaires est triple: - Irradiation a distance, lors des manipulations des cartouches. - Contamination de l'air au moment de leur degainage. - Contamination de l'air par incendie d'uranium dans un reacteur en fonctionnement. Les deux premiers dangers sont habituels et peuvent etre traites grace aux regles de securite en usage dans l'industrie atomique. Le troisieme revet un caractere accidentel et reclame l'emploi de regles speciales et exceptionnelles, debordant le cadre industriel, pour atteindre celui des populations environnantes. (auteurs)

  9. Fatigue damage of nuclear facilities; Endommagement par fatigue des installations nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    The conference on the fatigue damage of nuclear facilities, organized by the SFEN (french society of nuclear energy), took place at Paris the 23. of november 2000. Eleven papers were presented, showing the state of the art and the research programs in the domain of the sizing rules, safety, installations damage, examination and maintenance. (A.L.B.)

  10. Particles identification using nuclear emulsion in OPERA; Identification des particules par les emulsions nucleaires dans OPERA

    Energy Technology Data Exchange (ETDEWEB)

    Manai, K

    2007-10-15

    The Opera experiment will try to confirm the {nu}{sub {mu}} {yields} {nu}{sub {tau}} oscillations by the appearance of the {nu}{sub {tau}} in a pure {nu}{sub {mu}} beam. Indeed, a neutrino beam almost pure is produced at CERN (CNGS Beam) and sent to the Opera detector. The detector is composed of two muons spectrometers and a target formed by walls of bricks. Each brick is an alternation of lead plates and emulsions. This modular structure allows to reconstruct the kink topology of the {tau} lepton decay with a high spatial resolution. The great challenge of the Opera experiment is to detect the {nu}{sub {tau}} interactions with the less uncertainty. To reduce this uncertainty it is essential to identify with the greatest efficiency any background event not including a tau particle. My work permits to reduce background. My principal contribution concerns the selection development, the reconstruction and the muons identification at low energy. This work is based on the setting of variables related to the deposit energy and the multiple scattering. Previously, only deposit energy was used in the analyses of pion/muon separation. This study allows doubling the muon identification efficiency at low energy. This leads to increase the background events rejection in Opera and to decrease the contamination by 30%. I also studied the nuclear emulsions capacity to identify charged particles through the analysis of a test beam carried out by the Nagoya group. This test contains protons and pions with different energies. My work proves that the European scan system gives comparable results with those obtained by the Japanese scan system. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

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

  12. 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.)

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    The law from December 30, 1991, precisely defines 3 axes of researches for the management of high level and long-lived radioactive wastes: separation/transmutation, surface storage and underground disposal. A global evaluation report about these researches is to be supplied in 2006 by the French government to the Parliament. A first synthesis of the knowledge gained after 14 years of research has led the national commission of the public debate (CNDP) to organize a national debate about the general options of management of high-level and long-lived radioactive wastes before the 2006 date line. The debate comprises 4 public hearings (September 2005: Bar-le-Duc, Saint-Dizier, Pont-du-Gard, Cherbourg), 12 round-tables (October and November 2005: Paris, Joinville, Caen, Nancy, Marseille), a synthesis meeting (December 2005, Dunkerque) and a closing meeting (January 2006, Lyon). This document is the proceedings of the synthesis meeting of Dunkerque. It comprises an introduction which recalls the stakes and modalities of the debate, followed by a talk from the president of the national association of local commissions for nuclear activities information (ANCLI), and three synthesis talks from the particular commission of the public debate, the ministry of industry, and the committee of experts and counter-experts. These proceedings end with some questions and answers with the public. A slide presentation by B. Dessus about the progresses made in the debate on nuclear wastes management is attached to the document. (J.S.)

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

    Energy Technology Data Exchange (ETDEWEB)

    Petit, L

    2007-10-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Lelievre, F

    1998-12-11

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

  16. Spent fuel, plutonium and nuclear waste: long-term management; Le combustible use et le plutonium en tant que dechets nucleaires: gestion a long terme

    Energy Technology Data Exchange (ETDEWEB)

    Collard, G

    1998-11-01

    Different options for the management of nuclear waste arising from the nuclear fuel cycle are discussed. Special emphasis is on reprocessing followed by geological disposal, geological disposal of reprocessing waste, direct geological disposal of spent nuclear fuel, long term storage. Particular emphasis is on the management of plutonium including recycling, immobilisation and disposal, partitioning and transmutation.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1997-07-01

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

  18. Researches on nuclear wastes. Knowledge gained and perspectives at the 2006 date line; Recherches sur les dechets nucleaires acquis et perspectives a l'echeance 2006

    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. The responsibility of these researches is given to the French atomic energy commission (CEA) and to the national agency for radioactive wastes (ANDRA) who have to coordinate their works with other research organizations and industrialists. The aim of this colloquium is to make a status of the scientific knowledge gained before the implementation of the public and parliamentary debates on nuclear wastes management. This document gathers the presentations (slides) given at the colloquium and dealing with: separation/transmutation, storage and conditioning of waste packages; geologic disposal, the inter-disciplinary PACE program of the CNRS; synthesis of the researches evaluation process; general principles for a sustainable management of radioactive wastes; technical experience implemented by industrialists since 15 years; point of view of the nuclear safety authority; international context of nuclear waste management and related researches; a sociological enlightening: researches advance as seen by the public. (J.S.)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1995-05-01

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

  20. Activation analysis using {gamma} photons; Analyse par activation aux photons {gamma}

    Energy Technology Data Exchange (ETDEWEB)

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

    1967-07-01

    This report summarizes all the data required for using photonuclear reactions in the field of analysis. After a brief review of the elementary properties of nuclear reactions induced by photon irradiation, the main characteristics are given of high energy (E > 20 MeV) Bremsstrahlung sources. The principle of activation analysis based on the use of photons is given. Actual examples of the analytic possibilities are described in detail, in particular in the case of the determination of very small quantities (< 10{sup -6}) of C, N, O and F. The influence of interfering nuclear reactions is discussed. (author) [French] Ce rapport se propose de resumer l'ensemble des connaissances indispensables pour l'utilisation des reactions photonucleaires a des fins analytiques. Apres quelques rappels concernant les proprietes elementaires des reactions nucleaires induites par irradiation dans les photons, les principales caracteristiques des sources de rayonnement de freinage de haute energie (E > 20 MeV)| sont donnees. Le principe de l'analyse par activation aux photons est rappele. Des exemples concrets sur les possibilites analytiques sont developpes, particulierement en ce qui concerne la determination de quantites tres faibles (< 10{sup -6}) de C, N, O et F. L'influence des reactions nucleaires parasites est discutee. (auteur)

  1. 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

  2. Nuclear reactor (1960); Reacteurs nucleaires (1960)

    Energy Technology Data Exchange (ETDEWEB)

    Maillard, M L [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires; Leo, M B [Electricite de France (EDF), 75 - Paris (France)

    1960-07-01

    The first French plutonium-making reactors G1, G2 and G3 built at Marcoule research center are linked to a power plant. The G1 electrical output does not offset the energy needed for operating this reactor. On the contrary, reactors G2 and G3 will each generate a net power of 25 to 30 MW, which will go into the EDF grid. This power is relatively small, but the information obtained from operation is great and will be helpful for starting up the power reactor EDF1, EDF2 and EDF3. The paper describes how, previous to any starting-up operation, the tests performed, especially those concerned with the power plant and the pressure vessel, have helped to bring the commissioning date closer. (author) [French] Les premiers reacteurs industriels plutonigenes francais G1 - G2 - G3 du Centre de Marcoule comportent une installation de recuperation d'energie. La production d'electricite de G1 ne compense pas l'energie depensee par ailleurs pour le fonctionnement de l'ensemble, par contre, G2 et G3 doivent fournir chacun une puissance de 25 a 30 MW au reseau national d'Electricite de France. Cette puissance est modeste, mais l'experience acquise grace a ces reacteurs est tres grande et c'est grace a elle qu'il nous sera possible de mettre en exploitation les reacteurs energetiques EDF1 - EDF2 - EDF3. Le memoire decrit comment, avant tout demarrage du reacteur, les essais effectues, en particulier ceux concernant l'installation de recuperation d'energie et le caisson, ont permis d'abreger la phase de montee en puissance. (auteur)

  3. 1. contribution of the dynamics on the reactions mechanisms in the heavy ions collisions at the intermediary energies (20-100 MeV/A) for the light systems. 2. management of radioactive wastes by new options: nuclear data measurement programme between 20 and 150 MeV; 1. role de la dynamique sur les mecanismes de reactions dans les collisions d'ions lourds aux energies intermediaires (20-100 MeV/A) pour des systemes legers. 2. gestion des dechets radioactifs par des options nouvelles: programme de mesures de donnees nucleaires entre 20 et 150 MeV

    Energy Technology Data Exchange (ETDEWEB)

    Eudes, Ph

    2000-09-22

    The first part concerns the features of emitted charged particles in heavy ions reactions that have been studied in the framework of the semi classical Landau-Vlasov approach for the light system Ar + Al at 65 MeV/nucleon incident energy. The second part is devoted to the radioactive waste management (transmutation), but it was necessary to increase the data banks evaluated in neutrons up to 150-200 MeV and to create a data bank in protons. In the European framework it was decide to focus on three representative elements: lead (spallation target), iron (structure material) and uranium (actinide). (N.C.)

  4. 1. contribution of the dynamics on the reactions mechanisms in the heavy ions collisions at the intermediary energies (20-100 MeV/A) for the light systems. 2. management of radioactive wastes by new options: nuclear data measurement programme between 20 and 150 MeV; 1. role de la dynamique sur les mecanismes de reactions dans les collisions d'ions lourds aux energies intermediaires (20-100 MeV/A) pour des systemes legers. 2. gestion des dechets radioactifs par des options nouvelles: programme de mesures de donnees nucleaires entre 20 et 150 MeV

    Energy Technology Data Exchange (ETDEWEB)

    Eudes, Ph

    2000-09-22

    The first part concerns the features of emitted charged particles in heavy ions reactions that have been studied in the framework of the semi classical Landau-Vlasov approach for the light system Ar + Al at 65 MeV/nucleon incident energy. The second part is devoted to the radioactive waste management (transmutation), but it was necessary to increase the data banks evaluated in neutrons up to 150-200 MeV and to create a data bank in protons. In the European framework it was decide to focus on three representative elements: lead (spallation target), iron (structure material) and uranium (actinide). (N.C.)

  5. suPAR

    DEFF Research Database (Denmark)

    Hodges, Gethin W; Bang, Casper N; Wachtell, Kristian

    2015-01-01

    The fundamental role of inflammation in cardiovascular disease (CVD) has prompted interest in numerous biomarkers that detect subclinical levels of inflammation. Soluble urokinase plasminogen activator receptor (suPAR) is a novel biomarker that correlates significantly with cardiovascular events ...... comprehensive review of suPAR in CVD and explore its function and usefulness in predicting cardiovascular events....

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

  7. 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

    a securite inherente. Toutefois, les systemes a securite non inherente restent nombreux dans les installations nucleaires et le recours a l'une ou l'autre des deux premieres methodes devient necessaire. Ces methodes sont liees a la gestion des matieres nucleaires. Dans les installations ou sont manipulees de petites quantites de matieres fissiles, il est souvent possible d'assurer la securite nucleaire en admettant dans chaque salle une masse de matiere fissile inferieure a la masse ciritique minimale. Pour des installations plus importantes, un tel controle, qui repose entierement sur la gestion des matieres, devient impossible. L'auteur examine, dans le cas particulier d'une usine oe traitement de combustibles irradies par voie aqueuse (les combustibles sont a base d'uranium naturel), comment se presente la liaison entre gestion et securite nucleaire. Une telle usine comprend grossierement trois parties au point de vue du controle de la criticite: Dans la premiere partie, traitant des solutions assez diluees, le controle qui s'impose est celui de la concentration. Si ce controle est aise (analyse et compteurs neutrons), il est difficile de s'assurer qu'il ne se forme pas de depots: bien que l'experience ait montre qu'ils n'etaient pas tellement a craindre, le fait bien connu d'un bilan matieres deficitaire reste un souci en matiere de criticite. Dans cette partie, la gestion des matieres, encore imparfaitement realisee, est de premiere importance pour la securite. La deuxieme partie traite des solutions concentrees et des precipites humides. C'est le domaine de la geometrie sure. La gestion des matieres l'interesse moins directement mais reste un facteur de securite important (en cas d'intervention, de nettoyage des appareils, etc.). Un controle par la masse s'impose dans la troisieme partie qui traite des produits secs. La gestion ne presente pas de difficulte particuliere. A ce schema se superpose une partie moins spectaculaire mais qui sur le plan surete est de

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

    Energy Technology Data Exchange (ETDEWEB)

    Millard-Pinard, N

    2003-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Millard-Pinard, N

    2003-07-01

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

  10. Par Pond water balance

    International Nuclear Information System (INIS)

    Hiergesell, R.A.; Dixon, K.L.

    1996-06-01

    A water budget for the Par Pond hydrologic system was established in order to estimate the rate of groundwater influx to Par Pond. This estimate will be used in modeling exercises to predict Par Pond reservoir elevation and spillway discharge in the scenario where Savannah River water is no longer pumped and discharged into Par Pond. The principal of conservation of mass was used to develop the water budget, where water inflow was set equal to water outflow. Components of the water budget were identified, and the flux associated with each was determined. The water budget was considered balanced when inflow and outflow summed to zero. The results of this study suggest that Par Pond gains water from the groundwater system in the upper reaches of the reservoir, but looses water to the groundwater system near the dam. The rate of flux of groundwater from the water table aquifer into Par Pond was determined to be 13 cfs. The rate of flux from Par Pond to the water table aquifer near the dam was determined to be 7 cfs

  11. FooPar

    DEFF Research Database (Denmark)

    Hargreaves, F. P.; Merkle, D.

    2013-01-01

    We present FooPar, an extension for highly efficient Parallel Computing in the multi-paradigm programming language Scala. Scala offers concise and clean syntax and integrates functional programming features. Our framework FooPar combines these features with parallel computing techniques. Foo......, results based on a empirical analysis on two supercomputers are given. We achieve close-to-optimal performance wrt. theoretical peak performance. Based on this result we conclude that FooPar allows programmers to fully access Scalas design features without suffering from performance drops when compared...

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

    onereuses ; en outre, ou bien elles ne permettent pas une decontamination suffisante, ou bien elles donnent de grandes quantites de dechets semi-solides qui doivent etre entreposes d'une facon permanente. On croit qu'en pareils cas les dechets peuvent etre enfouis d'une maniere sure et a peu de frais dans les profondeurs des formations sous-jacentes du sol. De grandes quantites de dechets peuvent etre entreposees avec une tres forte probabilite d'isolement parfait dans les formations greseuses. Les vides interstitiels et les proprietes d'echange d'ions permettent de disposer d'une grande capacite d'entreposage. Les installations d'elimination qui permettent d'utiliser les formations profondes du sol comprennent des puits d'injection par lesquels on introduit les dechets et des puits de surete qui servent a reduire la pression a l'orifice des puits, a exercer un controle radiologique des operations et a diriger les effluents de maniere a utiliser la formation au maximum. Pour etablir le projet d'une telle installation, on a besoin de renseignements comprenant des donnees sur les proprietes de dispersion de la formation, les caracteristiques d'echange d'ions de la couche et les proprietes chimiques et radiochimiques des dechets. Le prototype d'une installation d'injection a deux puits fonctionne depuis deux ans a l'Engineering Field Station de l'Universite. (author) [Spanish] Por lo comun, el volumen de los desechos radiactivos de actividad baja e intermedia producidos en las instalaciones de tratamiento quimico es tan considerable que el coste de su almacenamiento permanente resulta prohibitivo. En muchos casos el tratamiento quimico permite alcanzar un grado de descontaminacion suficiente para permitir la evacuacion de los efluentes en estuarios o corrientes de agua superficiales. No obstante, en determinadas circunstancias estos metodos son demasiado costosos, y no permiten lograr un grado suficiente de descontaminacion o dan lugar a la formacion de enormes cantidades de

  13. 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

  14. French achievements in the field of nuclear electronics; Realisations francaises dans le domaine de l'electronique nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Doireau, M; Fabre, R; Guillon, H; Guyot, C [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    Nuclear electronic equipment used by the french Atomic Energy Commission has been developed, with an increasing participation of the radioelectric industry (manufacture under AEC license, contracts for prototypes). The equipment for general use has been standardized and satis the technical specification sheets in which are specified more particularly, the conditions for construction, the choice of the spare parts and the conditions for acceptance by the french AEC at factory. The electronic equipment is classified in nine classes, and a brief description of the principal instruments is given in each class. The reliability of the equipment in use is satisfactory, as it is shown by the mean frequency of faults per 1000 hours operation. (author)Fren. [French] L'appareillage d'electronique nucleaire utilise au Commissariat a l'Energie atomique fran is a ete developpe en demandant un concours de plus en plus important a l'industrie radioelectrique (fabrications sous licence CEA, marches de prototypes, etc...). Le materiel d'emploi courant a ete standardise et repond aux specifications de cahiers des charges ou sont precises en particulier les conditions de realisation du materiel, le choix des pieces detachees et les conditions de recette en usine. L'appareillage electronique est classe en neuf rubriques et une description sommaire des principaux appareils est donnee dans chacune des rubriques. La tenue en service du materiel est satisfaisante, ainsi que le montre la frequence moyenne des pannes observees par 1000 heures de fonctionnement. (auteur)

  15. The nuclear power stations of the French atomic energy programme (1960); Les centrales nucleaires de puissance du programme francais (1960)

    Energy Technology Data Exchange (ETDEWEB)

    Leduc, C [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires; Roux, J P [Electricite de France (EDF), 75 - Paris (France)

    1960-07-01

    After recalling the entry of nuclear energy into energy production in France, the paper emphasizes the evolution of techniques applied in the designing of French nuclear power plants and describes the means employed for reducing costs per kWh of EDF2 and EDF3 compared with EDF1: the electric power per ton of uranium varies from 493 kW/t for EDF1 to 970 kW/t for EDF3. For this purpose the thermal power and electric power of units are changed respectively from 290 MWt for EDF1 to 1200 or 1600 MWt for EDF3 and from 28 to 250 MW. The results are obtained by an improvement in neutronic characteristics, developments in nuclear fuel technology, and simplification of the system of charging the reactor, whose means of maintenance are increased; the EDF2 heat-exchangers have been so designed as to increase the unit power of the elements, which will attain 9 MWt, as against 3 for EDF1. For EDF3 an advance project forecasts a thermodynamic layout with only one pressure stage. The paper ends with a description of the burst-slug detection systems, and an appendix gives a detailed comparative table of EDF1, EDF2 and EDF3 plant characteristics. (author) [French] Apres avoir rappele l'integration de l'energie nucleaire parmi les moyens de production de l'energie en France, les auteurs se penchent surtout sur l'evolution des techniques appliquees dans l'equipement des centrales nucleaires francaises et decrivent les moyens mis en oeuvre pour reduire les prix de revient du kWh d'EDF2 et d'EDF3 par rapport a EDF1: la puissance electrique par tonne d'uranium varie de 493 kW/t pour EDF1 a 970 kW/t pour EDF3. C'est dans ce but que les puissances thermiques et la puissance unitaire des groupes turbo-alternateurs passent respectivement de 290 MWt pour EDF1 a 1200 ou 1600 MWt pour EDF3 et de 82 a 250 MW. Les resultats sont obtenus par une amelioration des caracteristiques neutroniques, des progres realises sur la technologie des elements combustibles, une simplification du systeme de

  16. Shippingport Atomic Power Station Operating Experience, Developments and Future Plans; La centrale nucleaire de Shippingport, experience de son fonctionnement et plans pour l'avenir; Shippingportskaya atomnaya ehlektrostantsij, opyt ehkspluatatsii, usovershenstvovaniya i plany na budushchee; Central nucleoelectrica de Shippingport; experiencia adquirida con su explotacton y programa de desarrollo

    Energy Technology Data Exchange (ETDEWEB)

    Feinroth, H. [Division of Reactor Development, United States Atomic Energy Commission, Washington, DC (United States); Oldham, G. M. [Shippingport Atomic Power Station, Duquesne Light Company, Pittsburgh, PA (United States); Stiefel, J. T. [Bettis Atomic Power.Labora Tory, Westinghouse Electric Corporation, Pittsburgh, PA (United States)

    1963-10-15

    design rating of 150 MW(e) gross and a first seed life of 10.000 effective full power hours (EFPH), Core 2 will have five and a half times the design energy output and twice the power density of Core 1. The Core 2 design is described and associated major developments in reactor physics, metallurgy, heat transfer and fluid flow, and fuel element manufacture, are summarized. Plans for decontamination of the reactor plant and for performing modifications to the plant in connection with the installation of the higher rated Core 2 are described. (author) [French] Les auteurs font le bilan des cinq annees de fonctionnement et d'essai de la centrale nucleaire de Shippingport; ils examinent les progres techniques actuels et l'avenir du programme de Shippingport. Ce programme vise a mettre au point la technologie fondamentale des reacteurs a eau legere pour permettre une reduction du prix de revient de l'energie d'origine nucleaire. La centrale nucleaire de Shippingport fonctionne depuis plus de 5 ans et s'est integree facilement dans un reseau d'interconnexion comme centrale de base ou comme centrale d'appoint. Les divers elements de la centrale se sont reveles d'un fonctionnement sur. Il n'y a pas eu de probleme de contamination ni d'elimination des dechets. On peut acceder facilement aux elements du circuit primaire de refroidissement pour l'entretien et, ce faisant, on a constate que les cartouches de combustible etaient intactes. Chacune des trois operations de rechargement effectuees depuis le demarrage de la centrale a pris moins de temps que la precedente. Recemment, la troisieme charge de combustible enrichi a ete mise en place en 32 journees de travail, soit environ le quart du temps necessaire pour le premier rechargement. Les auteurs exposent les conditions auxquelles doit satisfaire la formation du personnel et donnent un apercu des instructions ecrites en matiere d'administration, d'exploitation, etc., qui sont autant de facteurs essentiels du succes du programme de

  17. Neutron detection in an atomic reactor core using semi-conductors; Detection des neutrons par semi-conducteur dans un coeur de reacteur atomique

    Energy Technology Data Exchange (ETDEWEB)

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

    1968-07-01

    In this paper, the first part describes the principle of nuclear particle detection by means of semiconductor diodes and the general application of these. The second part describes fabrication of the device used to estimate thermic neutron fluxes in core of a swimming pool type reactor. The useful volume (2.9 mm thickness) is in the light water moderator, between combustible elements plates. The results, principally obtained in the core of Siloette reactor at the 'Centre d'Etudes Nucleaires de Grenoble' at low power, are mentioned in the third part. Flux maps have been set and comparison between converter's products: Bore 10, Lithium 6, Uranium 235 is made. (author) [French] Dans ce rapport, une premiere partie porte sur la description du principe de detection des particules nucleaires par diodes a semi-conducteur et sur l'application generale de celles-ci. Une deuxieme partie s'attache a decrire la fabrication du materiel utilise pour evaluer les flux de neutrons thermiques dans un coeur de reacteur type pile piscine. L'espace de mesure (2,9 mm d'epaisseur) se situe entre les plaques des elements combustibles, dans le moderateur eau legere. Les resultats, obtenus principalement dans le coeur du reacteur Siloette du Centre d'Etudes Nucleaires de Grenoble aux basses puissances de fonctionnement, sont rapportes dans la troisieme partie. Des cartes de flux ont ete dressees et une comparaison est faite entre les produits 'convertisseurs' suivants: Bore 10, Lithium 6, Uranium 235. (auteur)

  18. The 'Pole Nucleaire Bourgogne' for developing the nuclear components industry

    International Nuclear Information System (INIS)

    Kottmann, G.

    2012-01-01

    The 'Pole Nucleaire Bourgogne' (PNB) is a high-technology and heavy industries cluster in Burgundy with an international calling. It aims at innovating, educating and federating in order to place the French nuclear industry in a leading position. PNB gathers 76 small-, and medium-sized enterprises, most of them operating in the metal sector, in design and in the control/measuring sector. The aim of PNB is to make enterprises work and cooperate on specific topics according to their sectors of activities and their skills. PNB has identified 3 domains of strategical innovations: -) ecological manufacturing and durability of heavy components, -) controls for high performance components, and -) maintenance and dismantling techniques in hostile environments. The various industry sectors represented in PNB allows a cross-fertilization between high-tech industries (aeronautics, energy, transportation)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

  20. Nuclear developments at the international inter govern mental level (1961); Developpements nucleaires sur le plan international intergouvernemental (1961)

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-07-01

    The United Nations organisation and nuclear energy rose simultaneously, in 1945, to occupy an important place in the public eye. The spiritual succession of the League of Nations which had foundered during the war was taken up by the new organisation which sought to implant its political ideal in a more tangible reality, so that it might thereby be inspired by concrete and substantial objectives. This is one of the reasons for the existence of the dozen specialized agencies created by the family of the United Nations and dealing with Health, Culture, Agriculture, Finance, etc. Nuclear energy is one of these techniques. Becoming suddenly an important power factor and exploiting for itself the prestige of Science, it became the favorite domain for the growth of this new spirit, as much in its universal form in 1945 as in its more regional form which it was later to adopt. The achievements are numerous and of varying importance; they deserve te be studied carefully. (author) [French] L'organisation des Nations Unies et le nucleaire ont ete places simultanement, en 1945, au premier plan de la scene mondiale. La Societe des Nations ayant sombre pendant la guerre, son heritage spirituel fut recueilli par la nouvelle organisation qui chercha a enraciner son ideal politique dans une realite plus materielle, de facon a y puiser une nourriture concrete et substantielle. C'est une des raisons d'existence de la douzaine d'institutions specialisees gravitant dans la famille des Nations Unies et s'occupant de Sante, de Culture, d'Agriculture, de Finances, etc. Le nucleaire est l'une de ces techniques. Devenu soudainement un facteur primordial de puissance, Cristallisant a son benefice le prestige de la Science, c'etait un terrain de predilection pour le developpement du nouvel esprit, aussi bien sous la forme universelle de 1945, que sous les formes regionales qui ont vu le jour ensuite. Les travaux realises que nombreux, d'importance tres inegale. Ils meritent qu'on les examine

  1. Nuclear developments at the international inter govern mental level (1961); Developpements nucleaires sur le plan international intergouvernemental (1961)

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-07-01

    The United Nations organisation and nuclear energy rose simultaneously, in 1945, to occupy an important place in the public eye. The spiritual succession of the League of Nations which had foundered during the war was taken up by the new organisation which sought to implant its political ideal in a more tangible reality, so that it might thereby be inspired by concrete and substantial objectives. This is one of the reasons for the existence of the dozen specialized agencies created by the family of the United Nations and dealing with Health, Culture, Agriculture, Finance, etc. Nuclear energy is one of these techniques. Becoming suddenly an important power factor and exploiting for itself the prestige of Science, it became the favorite domain for the growth of this new spirit, as much in its universal form in 1945 as in its more regional form which it was later to adopt. The achievements are numerous and of varying importance; they deserve te be studied carefully. (author) [French] L'organisation des Nations Unies et le nucleaire ont ete places simultanement, en 1945, au premier plan de la scene mondiale. La Societe des Nations ayant sombre pendant la guerre, son heritage spirituel fut recueilli par la nouvelle organisation qui chercha a enraciner son ideal politique dans une realite plus materielle, de facon a y puiser une nourriture concrete et substantielle. C'est une des raisons d'existence de la douzaine d'institutions specialisees gravitant dans la famille des Nations Unies et s'occupant de Sante, de Culture, d'Agriculture, de Finances, etc. Le nucleaire est l'une de ces techniques. Devenu soudainement un facteur primordial de puissance, Cristallisant a son benefice le prestige de la Science, c'etait un terrain de predilection pour le developpement du nouvel esprit, aussi bien sous la forme universelle de 1945, que sous les formes regionales qui ont vu le jour ensuite. Les travaux realises que nombreux, d

  2. 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

    'impuretes fertiles (appliquant un procede calcium-fer-phosphate) et de bassins de retenue. Le memoire examine les diverses methodes de concentration des impuretes et de traitement secondaire qui sont actuellement a l'etude. Les auteurs etudient la formule d'evacuation et la dilution probable dans le Woronora, et decrivent un essai de dilution qui a ete effectue dans les eaux touchees par la maree. On se propose d'enfouir, le cas echeant apres empaquetage, tous les dechets solidesi de faible activite. Les auteurs etudient le choix et l'emplacement de la zone d'elimination. Ils font un expose sur la construction d'une installation destinee au stockage et a l'elimination de dechets solides a activite elevee. On envisage l'e vaporation et le stockage des dechets liquides a activite moyenne et elevee. Le memoire donne des renseignements detailles sur les depenses d'equipement et d'exploitation afferentes a l'usine de traitement des effluents et a d'autres installations pour le traitement des dechets. (author) [Spanish] La memoria describe las instalaciones previstas para la recogida, tratamiento y evacuacion de los desechos radiactivos en Lucas Heights, en relacion con las cantidades que se produciran segun los calculos. Los efluentes de baja actividad se dividen en tres tipos: a) Aguas de las cloacas, b) Desechos de funcionamiento, provenientes de la torre de refrigeracion del reactor, de los talleres mecanicos y otras zonas no activas, c) Efluentes de los laboratorios y otras zonas activas. La planta de tratamiento para los efluentes del ultimo tipo consiste en principio en tanques de mezcla y dosificacion de alcali, un clarificador de lodos (que emplea un sistema a base de calcio - herro - fosfato) y tanques receptores. Se estan estudiando metodos para concentrar los lodos y metodos de tratamiento secundario, que se discuten en la memoria. La memoria estudia la forma de descarga y el grado de dilucion que se espera obtener en el rio Woronora, asi como un experimento de dilucion que se

  3. Irradiation and development of the nuclear emulsions exposed to intense fluxes of thermal neutrons with {gamma} rays; Irradiation et developpement des emulsions nucleaires exposees a des flux intenses de neutrons thermiques, accompagnes de rayons {gamma}

    Energy Technology Data Exchange (ETDEWEB)

    Faraggi, H; Bonnet, A; Cohen, J [Commissariat a l' Energie Atomique, Lab. du Fort de Chatillon, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1952-07-01

    The thermal neutron fluxes provided by nuclear reactors permit the survey of relatively rare phenomenons, and dosage of very weak quantities of some elements. One of the most favorable detection technique are constituted by the use of the nuclear emulsions. one can mention: - the dosage of uranium by counting in the emulsion the number of traces due to fission fragments after irradiation. - The dosage of the lithium and the boron as trace amounts with the help of nuclear reactions (n, {alpha}) and thermal neutrons. - The research of reactions (n, {alpha}) or (n, p) of very weak cross section for middle or heavy elements. These different applications require however important neutrons fluxes. It had therefore obliged us to search for the most favorable irradiation and development of the emulsions conditions, to get the best visibility of the trajectories and decrease the phenomena of fog on the emulsion, which prevents any observation. (M.B.) [French] Les flux de neutrons thermiques fournis par les reacteurs nucleaires permettent l'etude de phenomenes relativement rares, et le dosage de tres faibles quantites de certains elements. Un des moyens de detection les plus favorables est constitue par l'utilisation des emulsions nucleaires. on peut citer: - le dosage de l'uranium par comptage dans l'emulsion du nombre de traces dues aux fragments de fission apres irradiation. - Le dosage du lithium et du bore a l'etat de traces a l'aide des reactions (n, {alpha}) sous l'action des neutrons thermiques. - La recherche de reactions (n,{alpha}) ou (n,p) de tres faible section efficace pour des elements moyens ou lourds. Ces differentes applications necessite cependant des flux de neutrons important. On a donc ete amene a rechercher les conditions les plus favorables d'irradiation et de developpement des emulsions, de maniere a obtenir la meilleure visibilite des trajectoires et diminuer les phenomenes de voile de l'emulsion, qui empeche toute observation. (M.B.)

  4. Some results on the fluorescence of gases excited by high-energy charged particles; Quelques resultats concernant la fluorescence de gaz excites par des particules chargees de grande energie

    Energy Technology Data Exchange (ETDEWEB)

    Koch, L; Lesureur, R [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    The essential characteristics of rare gases for use as scintillators are as follows: a very brief period of luminescence, generally less than 10{sup -8} s; a linear response as a function of the energy lost by the nuclear particle in the gas, even in the case of strongly ionising particles (fission fragments). In the gaseous or condensed state therefore, they are of great interest in nuclear physics. (author) [French] Les caracteristiques essentielles des gaz rares en tant que scintillateurs sont: une duree de luminescence tres breve, inferieure a 10{sup -8} s en general; une reponse lineaire en fonction de l'energie perdue par la particule nucleaire dans le gaz, meme dans le cas de particules fortement ionisantes (fragments de fission). A l'etat gazeux ou condense, ils presentent donc un grand interet en physique nucleaire. (auteur)

  5. Contribution to the study of nuclear fuel materials with a metallic uranium base; Contribution a l'etude des materiaux combustibles nucleaires a base d'uranium metallique

    Energy Technology Data Exchange (ETDEWEB)

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

    1957-11-15

    In a power reactor destined to supply industrially recoverable thermal energy, the most economical source of heat still consists of natural metallic uranium. However, the nuclear fuel material, most often employed in the form of rods of 20 to 40 mm diameter, is subjected to a series of stresses which lead to irreversible distortions usually incompatible with the substructure of the reactor. As a result the fuel material must possess at the outset a certain number of qualities which must be determined. Investigations have therefore been carried out, first on the technological characters peculiar to each of the three allotropic phases of pure uranium metal, and on their interactions on the stabilisation of the material which consists of either cast uranium or uranium pile-treated in the {gamma} phase. (author) [French] Dans un reacteur de puissance destine a fournir de l'energie thermique industriellement recuperable, la source de chaleur la plus economique reste constituee par de l'uranium metallique naturel. Or, le materiau combustible nucleaire, employe le plus souvent sous forme de barreaux de 20 a 40 mm de diametre, se trouve soumis a un ensemble de contraintes qui provoque des deformations irreversibles, le plus souvent incompatibles avec l'infrastructure du reacteur. Par consequent, le materiau combustible doit presenter a l'origine un certain nombre de qualites qu'il est necessaire de determiner. Aussi a-t-on d'abord etudie les caracteres technologiques propres a chacune des trois phases allotropiques de l'uranium-metal pur et leurs interactions sur la stabilisation du materiau constitue soit par de l'uranium coule, soit par de l'uranium traite en pile en phase {gamma}. (auteur)

  6. Optimal sizes and siting of nuclear fuel reprocessing plants; Tailles et localisations optimales des usines de retraitement des combustibles nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Thiriet, L; Deledicq, A [Commissariat a l' Energie Atomique, Siege (France). Centre d' Etudes Nucleaires

    1967-07-01

    The expansion of a nuclear economy entails the development of fuel process and reprocessing plant programmes. The model proposed makes it possible to select the size, the site and the start-up schedule of the plants in such a way as to minimize the total freight and reprocessing costs. As an illustration, we have approached the problem of burnt natural uranium processing plants related to natural uranium-graphite as nuclear power stations. The sites and annual output of the reactors, the possible plant sites and cost functions (freight and reprocessing) are supposed to be known. The method consists in first approaching the process plant problem as a Dynamic Programming problem, increasing programme slices (total reactor output) being explored sequentially. When the quantities of burnt natural uranium to be reprocessed are fixed, the minimization of the transport cost is then also carried out as a dynamic programming problem. The neighbourhood of the optimum process cost is explored in order to find the minimum summation of a suboptimal processing cost and corresponding optimal transport cost. As the reprocessing problem can be represented on a sequential graph, in order to compute the sub-optima, we developed and used a 'reflexion algorithm'. The method can be interpreted as a general mechanism for determining the optimum when to a sequential dynamic problem (for example an equipment programme) is added a complementary problem (transport, for instance). It also makes it possible to estimate the economic losses which result from the choice of a non optimal policy for other than economic reasons. (author) [French] L'expansion de l'economie nucleaire se traduit par un developpement des programmes d'usines d'elaboration et de retraitement des combustibles. Le modele propose permet de choisir la taille, la localisation et la cadence de mise en service des usines de maniere a minimiser le total des frais de transport et de retraitement. A titre d'exemple nous avons

  7. It's quicker "Par Avignon"!

    CERN Multimedia

    2005-01-01

    For a few years, the CERN Library has been receiving books from the University of Hanover sent via Avignon, at least that's what it says on the envelope. Such a detour would mean that parcels were travelling 720 km more than the distance separating Geneva and Hanover, which would be a very strange state of affairs. The explanation lies in a spelling mistake. The sender has been stamping parcels with a stamp that says "Par Avignon prioritaire" (first-class via Avignon) instead of "Par Avion prioritaire" (First Class Air Mail), a source of much amusement to the librarians!

  8. The pulsed neutron method applied to the determination of the nuclear constants of graphite (1961); La methode des neutrons pulses appliquee a la determination des constantes nucleaires du graphite (1961)

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-07-01

    A method for determining the nuclear constants {sigma}{sub a} and {lambda}{sub t} of a moderator is described. The disappearance of a burst of neutrons introduced into a finite medium is studied as a function of time. This decrease in the thermal neutron density is the product of two exponentials; one representing the absorption, the other the leakage. By varying one or other of these factors, the constants of the factor left unvaried can be determined, and from this the nuclear constant values are deduced. (author) [French] On decrit une methode permettant de determiner les constantes nucleaires {sigma}{sub a} et {lambda}{sub t} d'un moderateur. On etudie la decroissance dans le temps d'une bouffee de neutrons introduite dans un milieu fini. Cette decroissance de la densite en neutrons thermiques est le produit de deux exponentielles; l'une represente l'absorption, l'autre les fuites. Par variation de l'un ou l'autre de ces facteurs, on determine les constantes du facteur laisse invariant dont on deduit les valeurs des constantes nucleaires. (auteur)

  9. Some aspects of the nuclear fission process; Quelques aspects du processus de fission nucleaire

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-07-01

    In the following report one can find first a short general view on the present situation of our knowledge concerning the nuclear fission process, namely on the nucleus going through the saddle-point. Then there are some aspects connected with the excitation energy of the fissioning nucleus. The measurements made at Saclay on the fast neutron fission cross-section of U{sup 233}, U{sup 235}, Pu{sup 239}, U{sup 238} are described at the beginning of this work. It appears that for U{sup 233} there is some characteristic shape modulation of the cross-section curve, in relation with the collective excited state of the deformed nucleus at the saddle-point. Good evidence of this is also given by the study of the relative fission rate with emission of long-range particles; it appears also that this ternary fission rate does not change substantially for neutron between thermal energy and 2 MeV, but that is very lower for the compound nucleus U{sup 239} than for even-even compound nuclei. At the end there are some experiments on the strong 4,5 MeV gamma-ray originated by slow neutron absorption in U{sup 235}. Time-of-flight device is used to establish that this 4,5 MeV gamma-ray seems mostly connected with radiative capture. (author) [French] Le present travail debute par un apercu de l'etat actuel de nos connaissances sur le processus de fission nucleaire, notamment sur le passage par le point-seuil. Puis sont evoques des aspects lies au niveau d'energie d'excitation auquel est porte le noyau qui subit la fission. Les mesures de sections efficaces de fission induite dans {sup 233}U, {sup 235}U, {sup 239}Pu et {sup 238}U par des neutrons rapides effectuees a Saclay sont decrites en premier lieu; elles font apparaitre pour {sup 233}U une ondulation caracteristique du role des etats collectifs d'excitation du noyau deforme au point-seuil. Des experiences sur la fission avec emission de particules de long parcours confirment cet aspect tout en demontrant que la frequence

  10. Factors and uncertainties in the profitability of using nuclear energy in desalination of water; Facteurs et incertitudes de la rentabilite du recours a l'energie nucleaire dans le dessalement des eaux

    Energy Technology Data Exchange (ETDEWEB)

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

    1969-07-01

    One of the economic advantages of nuclear energy consists of the small proportional element in its cost structure. Economies of scale favour the nuclear station as compared with the conventional thermal one, and when the demand for electricity and heat, in particular for desalination, are sufficient, nuclear energy may, subject to certain conditions, prove advantageous. The object of this paper is to discuss the validity of the conclusions reached according to the hypotheses adopted. In the first part, the different kind of uncertainties connected with technical, economic and financial data (the various transmission coefficients, the life of equipment according to the choice of materials, changes in prices, the form of price functions and interest rates), and with the various constraints, are examined and discussed. In the second part the uncertainties connected with the method of optimisation used and the criterion of selection adopted are examined and discussed. It is shown thereby that it is usually extremely difficult to assume absolutely the competitiveness, or conversely the non-competitiveness, of using nuclear energy in the desalination of water, and that a large number of aspects have to be carefully examined. (author) [French] On sait que l'un des avantages economiques de l'energie nucleaire reside dans la faible part proportionnelle dans la structure de son cout. Les economies d'echelle favorisent le nucleaire par rapport au thermique classique, et lorsque les demandes d'electricite et de chaleur, notamment pour le dessalement, sont suffisantes on peut envisager favorablement, sous certaines hypotheses, le recours a l'energie nucleaire. L'objet de cette communication est de discuter la validite des conclusions auxquelles on parvient selon les hypotheses envisagees. Dans une premiere partie, on etudie et on discute les differentes sortes d'incertitudes, liees aux donnees techniques, economiques et financieres (les divers coefficients de transmission, les

  11. 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

  12. La pelade par plaques

    Science.gov (United States)

    Spano, Frank; Donovan, Jeff C.

    2015-01-01

    Résumé Objectif Présenter aux médecins de famille des renseignements de base pour faire comprendre l’épidémiologie, la pathogenèse, l’histologie et l’approche clinique au diagnostic de la pelade par plaques. Sources des données Une recension a été effectuée dans PubMed pour trouver des articles pertinents concernant la pathogenèse, le diagnostic et le pronostic de la pelade par plaques. Message principal La pelade par plaques est une forme de perte pileuse auto-immune dont la prévalence durant une vie est d’environ 2 %. Des antécédents personnels ou familiaux de troubles auto-immuns concomitants, comme le vitiligo ou une maladie de la thyroïde, peuvent être observés dans un petit sous-groupe de patients. Le diagnostic peut souvent être posé de manière clinique en se fondant sur la perte de cheveux non cicatricielle et circulaire caractéristique, accompagnée de cheveux en « point d’exclamation » en périphérie chez ceux dont le problème en est aux premiers stades. Le diagnostic des cas plus complexes ou des présentations inhabituelles peut être facilité par une biopsie et un examen histologique. Le pronostic varie largement et de mauvais résultats sont associés à une apparition à un âge précoce, une perte importante, la variante ophiasis, des changements aux ongles, des antécédents familiaux ou des troubles auto-immuns concomitants. Conclusion La pelade par plaques est une forme auto-immune de perte de cheveux périodiquement observée en soins primaires. Les médecins de famille sont bien placés pour identifier la pelade par plaques, déterminer la gravité de la maladie et poser le diagnostic différentiel approprié. De plus, ils sont en mesure de renseigner leurs patients à propos de l’évolution clinique de la maladie ainsi que du pronostic général selon le sous-type de patients.

  13. Use of particles other than neutrons in activation analysis; Emploi de particules autres que les neutrons en analyse par actuation

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-15

    Nuclear reactions obtained by irradiation in {gamma} Bremsstrahlung, {alpha} particles and protons are particularly suitable for dosing very small traces of light elements. We consider the possibilities presented by activation in {gamma} radiation of 28 MeV maximum energy, mainly for the measurement of C, F, N, O, P and S. Non-destructive methods of analysis for beryllium are described. Under certain conditions they may also be used for other elements such as B, Ca, Li and Na. We give also the results of our first experiments carried out in an attempt to find a method for dosing carbon and oxygen by irradiation in {alpha} particles and protons. For each type of activation the possible types of interference with other nuclear refections are considered. (author) [French] Des reactions nucleaires obtenues par irradiation dans des rayons {gamma} de freinage, des particules {alpha} et des protons, sont particulierement indiquees pour les dosages de traces ultimes de certains elements legers. Nous etudions les possibilites offertes par les activations en rayons {alpha} d'energie maximum 28 MeV, principalement pour les dosages de C, F, N, O, P et S. Des methodes d'analyse non destructives appliquees au beryllium sont decrites. Sous certaines conditions, elles peuvent egalement etre utilisees pour d'autres materiaux comme B, Ca, Li et Na. Nous donnons d'autre part les resultats de nos premieres experiences effectuees pour la mise au point des methodes de dosage du carbone et de l'oxygene par irradiation dans les particules {alpha} et les protons. Pour chaque type d'activation, les possibilites d'interferences avec d'autres reactions nucleaires sont examinees. (auteur)

  14. Nuclear study of Melusine; Etude nucleaire de Melusine

    Energy Technology Data Exchange (ETDEWEB)

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

    1959-07-01

    In this report are reviewed - with respect to starting of experiments - the main nuclear characteristics of a 20 per cent enriched uranium lattice, with light water as moderator and reflector. The reactor is to operate at 1 MW. 1) Study of various critical masses. 2) Control. Effectiveness of cadmium. Control rods and of a stainless steel regulating rod. 3) Study of the effect on reactivity of disturbances in the core center. 4) Study of xenon and samarium poisoning. 5) Temperature factor. 6) Heat exchanges in a fuel element. (author) [French] On etudie, dans ce rapport, les principales proprietes nucleaires d'un reseau a uranium enrichi (20 pour cent), dont le moderateur et le reflecteur sont l'eau legere en vue des experiences de demarrage. Ce reacteur devra fonctionner a 1 MW. 1) Etude de diverses masses critiques. 2) Controle. Efficacite des barres de controle en cadmium et d'une barre de reglage en acier inoxydable. 3) Etude de l'effet sur la reactivite de perturbation au centre du coeur. 4) Etude de l'empoisonnement xenon et samarium. 5) Coefficient de temperature. 6) Echanges thermiques dans un element. (auteur)

  15. Development of mercury porosimeter. Application to nuclear graphite studies (1961); Mise au point d'un porosimetre a mercure. Application a l'etude des graphites nucleaires (1961)

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-07-01

    A mercury porosimeter, model IFP-CEA, has been developed for application to nuclear graphite studies. The apparatus is based on the capillary depression phenomenon. The relationship between the radius of a pore and the pressure at which mercury fills it is pr = -2 {sigma} cos {theta} ( {sigma} is the surface tension, {theta} the angle of contact of the mercury). After some theoretical consideration, the apparatus is described. The mercury pressure is increased step-wise from 0 to 1000 kg/cm{sup 2} thus yielding the complete distribution of pores from 92 {mu} to 75 A. Results are, then presented concerning nuclear graphites which show the evolution of the porous structure under the effect of bitumen impregnation. In general, the volume of the large pores decreases while that of the small pores increases. The structure of impregnated products appears to depend to a certain extent on that of the starting materials. It has also been possible to study other products with this porosimeter; the range of measurements possible is such that it may be used for the study of the majority of porous materials. (authors) [French] Un porosimetre a mercure modele IFP-CEA a ete mis au point en vue de son application a l'etude de graphites nucleaires. Le fonctionnement de l'appareil repose sur le phenomene de depression capillaire. On etablit la relation existant entre le rayon r d'un pore et la pression p pour laquelle le mercure peut y penetrer: pr = -2 {sigma} cos {theta} ( {sigma} tension superficielle, {theta} angle de contact du mercure). Apres quelques considerations theoriques, l'appareil utilise est decrit. Il permet de faire varier par palier la pression du mercure entre 0 et 1000 kg/cm{sup 2} et d'etablir ainsi la distribution complete des rayons de pores compris entre 92 {mu} et 75 A. Les resultats d'une etude faite sur des graphites nucleaires sont alors presentes faisant apparaitre l'evolution de la structure poreuse sous l'effet des impregnations au brai. D'une facon

  16. Spectral content of seismic movements produced by underground nuclear explosions; Contenu spectral des mouvements seismiques dus aux explosions nucleaires souterraines

    Energy Technology Data Exchange (ETDEWEB)

    Albaret, A; Duclaux, F [Commissariat a l' Energie Atomique, Bruyeres-le-Chatel (France). Centre d' Etudes

    1969-07-01

    After a summary of available data, both theoretical and experimental, concerning the spectral content of seismic movements, a description is given of the experiments carried out during the French nuclear explosions in the Sahara, and of the results obtained on the volume waves. A comparison is then made with certain American results. A new method is described for studying the amplitude spectra; it has made it possible to show that the amount of low frequencies in the spectrum increases with the power of the explosion, and decreases with the distance to the zero point and with the filtering effect of the weathered zone. A calculation is then made of the low cut-off ground filter, this giving a better representation of the initial seismic phenomenon. (authors) [French] Apres avoir resume les connaissances disponibles, aussi bien theoriques qu'experimentales, sur le contenu spectral des mouvements seismiques, on decrit les experiences effectuees a l'occasion des explosions nucleaires francaises du Sahara et les resultats obtenus sur les ondes de volume. Puis on les compare avec certains resultats americains. On decrit une nouvelle methode d'etude des spectres d'amplitudes qui montre que le spectre est d'autant plus riche en basses frequences que la puissance de l'explosion est grande, que la distance au point zero est faible et qu'il est moins filtre par la zone alteree superficielle. Puis on calcule le filtre terrain coupe-bas qui permet de donner une representation plus fidele du phenomene seismique initial. (auteurs)

  17. suPAR

    DEFF Research Database (Denmark)

    Eugen-Olsen, Jesper; Giamarellos-Bourboulis, Evangelos J

    2015-01-01

    Investigation of biomarkers that can promptly predict unfavourable outcome of critically illness is an emerging necessity taking into consideration the need for early intervention, the shortage of available beds in intensive care units and the considerable cost of hospitalisation. The most...... promising biomarker is soluble urokinase-type plasminogen activator receptor (suPAR). Three studies in large populations of critically ill patients and patients admitted to the emergency department have shown that concentrations >12ng/mL can safely predict unfavourable outcome. This review presents...

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

    Energy Technology Data Exchange (ETDEWEB)

    Lombard, J; Hubert, P; Pages, P

    1987-07-01

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

  19. Relationship between the nuclear resonance of cobalt metal and its ferromagnetic properties; Relations entre la resonance nucleaire du cobalt metallique et ses proprietes ferromagnetiques

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-05-15

    resulte du couplage intense existant entre les noyaux et les electrons porteurs du magnetisme. Ces derniers excitent les noyaux et, dans les parois de Bloch, les soumettent a un champ radio-frequence bien plus intense que le champ RF applique. Les parametres de la resonance se determinent alors a partir du mouvement des parois, et dependent donc des constantes ferromagnetiques. La theorie permet de prevoir quantitativement certains effets particuliers, notamment par action d'un champ magnetique continu ou de la temperature. L'etude expeimentale a porte sur des poudres de cobalt et est en bon accord avec la theorie. Toutefois il faut tenir compte de l'effet de peau et reviser la theorie en consequence. Ceci permet d'expliquer certaines divergences observees, ainsi que l'influence de la taille des grains et celle du champ magnetique sur la forme de raie. Des renseignements originaux ont ete obtenus sur certaines proprietes purement ferromagnetiques du cobalt, en etudiant l'effet d'un champ magnetique et cette methode a pu etre appliquee a d'autres corps ferromagnetiques. En raison du caractere particulier de cette resonance nucleaire, qui se produit en l'absence de champ directeur et possede une importante largeur de raie, des spectrographes de type nouveau ont ete realises qui ont rendu possible des mesures precises de la forme de raie. La faible intensite des signaux obtenus dans certains cas a conduit a la mise au point d'une methode originale d'extraction dont la theorie et les applications pratiques sont donnees ici. L'ensemble de ces experiences fait apparaitre la resonance nucleaire comme un puissant moyen d'etude du ferromagnetique permettant de deceler des phenomenes microscopiques difficilement accessibles par les methodes classiques. (auteur)

  20. Relationship between the nuclear resonance of cobalt metal and its ferromagnetic properties; Relations entre la resonance nucleaire du cobalt metallique et ses proprietes ferromagnetiques

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-05-15

    couplage intense existant entre les noyaux et les electrons porteurs du magnetisme. Ces derniers excitent les noyaux et, dans les parois de Bloch, les soumettent a un champ radio-frequence bien plus intense que le champ RF applique. Les parametres de la resonance se determinent alors a partir du mouvement des parois, et dependent donc des constantes ferromagnetiques. La theorie permet de prevoir quantitativement certains effets particuliers, notamment par action d'un champ magnetique continu ou de la temperature. L'etude expeimentale a porte sur des poudres de cobalt et est en bon accord avec la theorie. Toutefois il faut tenir compte de l'effet de peau et reviser la theorie en consequence. Ceci permet d'expliquer certaines divergences observees, ainsi que l'influence de la taille des grains et celle du champ magnetique sur la forme de raie. Des renseignements originaux ont ete obtenus sur certaines proprietes purement ferromagnetiques du cobalt, en etudiant l'effet d'un champ magnetique et cette methode a pu etre appliquee a d'autres corps ferromagnetiques. En raison du caractere particulier de cette resonance nucleaire, qui se produit en l'absence de champ directeur et possede une importante largeur de raie, des spectrographes de type nouveau ont ete realises qui ont rendu possible des mesures precises de la forme de raie. La faible intensite des signaux obtenus dans certains cas a conduit a la mise au point d'une methode originale d'extraction dont la theorie et les applications pratiques sont donnees ici. L'ensemble de ces experiences fait apparaitre la resonance nucleaire comme un puissant moyen d'etude du ferromagnetique permettant de deceler des phenomenes microscopiques difficilement accessibles par les methodes classiques. (auteur)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

  2. Parálisis cerebral :

    OpenAIRE

    Cabrero Izquierdo, María del Carmen

    2012-01-01

    Se aborda el tema de la parálisis cerebral definiendo qué es, clasificando los tipos de parálisis dependiendo de la afectación y las características principales. Se explican algunos de sus tratamientos, se dan sistemas alternativos y/o aumentativos de comunicación para un alumno con PC (parálisis cerebral).

  3. The atomic energy course of the 'Institut National des Sciences et Techniques nucleaires' at the centre d'Etudes Nucleaires at Saclay; L'enseignement de genie atomique de l'Institut national des Sciences et Techniques nucleaires au Centre d'Etudes nucleaires de Saclay

    Energy Technology Data Exchange (ETDEWEB)

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

    1958-07-01

    foreign students. 8- Annexe: list of courses, practical work, pile projects drawn up by the 1957 students. (author)Fren. [French] 1- Les raisons de sa creation. L'electricite de France et l'industrie interessee par le developpement de l'Energie atomique ont demande au Commissariat a l'Energie atomique de former des ingenieurs capables d'etudier des projets de piles et de diriger leur construction. 2- Recrutement et Droits d'inscription. Les demandes d'inscription ont toujours depasse les possibilites. Cette annee, les cours sont suivis par 74 eleves permanents, dont 20 etrangers, et une centaine d'auditeurs libres. Tous les elevont deja ingenieurs ou nantis de grades universitaires eleves. Droit d'inscription: 250 000 F pour les eleves, 125 000 F pour les auditeurs. 3- Organisation de l'Enseignement. II comprend deux options: physique et chimie et dans chaque option: une centaine de conferences, une trentaine de travaux pratiques, des stages dans les services, l'etude d'un projet de reacteur par un groupe de 4 ou 5 eleves. L'ensemble occupe l'annee universitaire du 1 novembre au 14 juillet. 4- Sanction. Un examen final combinant les notes de deux epreuves theoriques, des travaux pratiques, du stage, et du projet conduit a un diplome d'ingenieur en genie atomique. Il n'est pas cree en realite de nouveaux ingenieurs; une mention nouvelle est seulement ajoutee a un diplome deja acquis. Les resultats ont toujours ete excellents. Le pourcentage des echecs est tres faible. 5- Placement des Diplomes. Ils reviennent tous dans leurs industries d'origine qui ont paye leurs salaires et les droits d'inscription en se privant de leurs services pendant les neuf mois de duree des cours. 6- Creations analogues. Un cours analogue a ete cree au Centre d'Etudes Nucleaires de Grenoble. Tandis que celui de SACLAY s'adresse plus specialement aux ingenieurs deja en fonctions, celui de Grenoble est, en principe, destine aux jeunes ingenieurs sortant des ecoles. 7- Conclusion. L

  4. Damage caused to houses and equipment by underground nuclear explosions; Degats dus aux explosions nucleaires souterraines sur les habitations et les equipements

    Energy Technology Data Exchange (ETDEWEB)

    Delort, F; Guerrini, C [Commissariat a l' Energie Atomique, Bruyeres-le-Chatel (France). Centre d' Etudes

    1969-07-01

    A description is given of the damaged caused to various structures, buildings, houses, mechanical equipment and electrical equipment by underground nuclear explosions in granite. For each type of equipment or building are given the limiting distances for a given degree of damage. These distances have been related to a parameter characterizing the movement of the medium; it is thus possible to generalize the results obtained in granite, for different media. The problem of estimating the damage caused at a greater distance from the explosion is considered. (authors) [French] Les degats sur diverses structures, constructions, habitations, equipements mecaniques et materiels electriques provoques par des explosions nucleaires souterraines dans le granite sont decrits. On a indique pour chaque type de materiel ou de construction, les distances limites correspondant a un degre de gravite de dommage observe. Ces distances ont ete reliees a un parametre caracterisant le mouvement du milieu, permettant ainsi de generaliser les resultats obtenus dans le granite, a differents milieux. Le probleme de la prevision des degats en zone lointaine a ete aborde. (auteurs)

  5. Contribution to the Study of Nuclear Magnetic Resonance in Ferromagnets; Contribution a l'etude de la resonance nucleaire dans les corps ferromagnetiques

    Energy Technology Data Exchange (ETDEWEB)

    Robert, C. [Commissariat a l' Energie Atomique, Centre d' Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France)

    1962-07-01

    Properties of nuclear magnetic resonance in the field acting on the nucleus in a ferromagnet were studied. Nuclei were {sup 57}Fe in iron and yttrium iron garnet. Static properties of resonance (frequency, line-width, dipolar structure) were investigated and compared with magnetic behavior and magnetic structure of the materials. Relaxation in garnet points out importance of long range fluctuations induced by impurities in a ferromagnetic lattice. (author) [French] Nous avons etudie les proprietes de la resonance nucleaire dans le champ existant a remplacement d'un noyau dans un corps ferromagnetique (champ local). Les noyaux etaient ceux de {sup 57}Fe dans le fer et dans le grenat d'yttrium et de fer. Les proprietes statiques de la resonance (frequence de resonance, largeur de la raie, structures dues a l'interaction dipolaire) ont ete etudiees et reliees aux caracteristiques magnetiques et a la structure de ces corps. La relaxation dans le grenat a mis en evidence les fluctuations a longue distance induites par des impuretes dans un reseau ferromagnetique. (auteur)

  6. Contribution to the Study of Nuclear Magnetic Resonance in Ferromagnets; Contribution a l'etude de la resonance nucleaire dans les corps ferromagnetiques

    Energy Technology Data Exchange (ETDEWEB)

    Robert, C [Commissariat a l' Energie Atomique, Centre d' Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France)

    1962-07-01

    Properties of nuclear magnetic resonance in the field acting on the nucleus in a ferromagnet were studied. Nuclei were {sup 57}Fe in iron and yttrium iron garnet. Static properties of resonance (frequency, line-width, dipolar structure) were investigated and compared with magnetic behavior and magnetic structure of the materials. Relaxation in garnet points out importance of long range fluctuations induced by impurities in a ferromagnetic lattice. (author) [French] Nous avons etudie les proprietes de la resonance nucleaire dans le champ existant a remplacement d'un noyau dans un corps ferromagnetique (champ local). Les noyaux etaient ceux de {sup 57}Fe dans le fer et dans le grenat d'yttrium et de fer. Les proprietes statiques de la resonance (frequence de resonance, largeur de la raie, structures dues a l'interaction dipolaire) ont ete etudiees et reliees aux caracteristiques magnetiques et a la structure de ces corps. La relaxation dans le grenat a mis en evidence les fluctuations a longue distance induites par des impuretes dans un reseau ferromagnetique. (auteur)

  7. Thermal energy of nuclear origin produced in non-fissile materials (1962); Energie calorifique d'origine nucleaire degagee dans les materiaux non fissiles (1962)

    Energy Technology Data Exchange (ETDEWEB)

    Naudet, G [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires; Millies, P; Berger, J [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

    1962-07-01

    A first part is devoted to the description of the interaction phenomena between elementary particles and material that may be observed during the irradiation process in a nuclear reactor: nuclear reactions due to neutrons, production of gamma rays and absorption of those gamma rays through various processes. In a second part the phenomena producing calorific energy in irradiated material are quantitatively examined. In the third part results are summed up in a formulary. The fourth part presents tables and figures giving to the reader all the numerical values necessary for practical calculations. (authors) [French] Une premiere partie est consacree a l'examen des principaux phenomenes d'interaction des particules avec la matiere qui interviennent lors d'une irradiation dans un reacteur: reactions nucleaires dues aux neutrons, production des rayons gamma et absorption de ces derniers par les divers processus. Une deuxieme partie etudie quantitativement les phenomenes qui conduisent a l'apparition d'energie calorifique dans le materiau irradie. En troisieme partie, un formulaire resume les resultats etablis. Dans une quatrieme partie, des tableaux et des courbes fournissent a l'experimentateur toutes les valeurs numeriques necessaires aux calculs pratiques. (auteurs)

  8. 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

  9. Examples of analysis by activation; Exemples d'analyse par activation

    Energy Technology Data Exchange (ETDEWEB)

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

    1955-07-01

    We were used various nuclear reactions to do some analysis by neutron or by X-ray activation. We used the french reactor core Zoe as neutrons sources and an Allis-Chalmers betatron as X-rays sources for the dosage of the light elements. The described processes were revealed fast and particularly useful for determination of traces. The fact that most of them don't require any chemical operations, is especially substantial when the solubilization of the sample is difficult. (M.B.) [French] Nous avons utilise des reactions nucleaires diverses pour effectuer des analyses par activation neutronique ou par rayon X. Nous avons utilise la pile francaise Zoe comme sources de neutrons et un betatron Allis-Chalmers comme sources de rayons X pour le dosage des elements legers. Les procedes decrits se sont reveles rapides et particulierement utiles dans la determination des traces. Le fait que, pour la plupart, ils n'exigent pas d'operations chimiques, est particulierement appreciable lorsque la solubilisation des echantillons est difficile. (M.B.)

  10. Nuclear program of Iran. Towards de-escalation of a nuclear crisis. Advisory letter; Nucleair programma van Iran. Naar de-escalatie van een nucleaire crisis. Briefadvies

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-04-15

    The Dutch government, partly at the request of the House of Representatives (Second Chamber), the AIV asked to give an opinion about the position of Iran in the region and the role of the nuclear program of Iran in the geopolitical relations, in view of the most recent developments [Dutch] De Nederlandse regering heeft, mede op verzoek van de Tweede Kamer der Staten-Generaal, de AIV gevraagd advies uit te brengen over de positie van Iran in de regio en de rol van het nucleaire programma van Iran in de geopolitieke verhoudingen hierin, mede gelet op de meest recente ontwikkelingen.

  11. Balance between automation and human actions in nuclear power plant operation. Results of international cooperation; Equilibre entre automatisation et action humaine dans la conduite des centrale nucleaires, resultats de la cooperation internationale

    Energy Technology Data Exchange (ETDEWEB)

    Sun, B [CEA Centre d' Etudes Nucleaires de Fontenay-aux-Roses, 92 (France). Dept. d' Analyse de Surete; Bastl, W [Gesellschaft fuer Reaktorsicherheit m.b.H. (GRS), Garching (Germany); Olmstead, R [Atomic Energy of Canada Ltd, Mississauga (Canada); Oudiz, A [Electric Power Research Inst., Palo Alto, CA (United States); Jenkinson, J [Nuclear Electric PLC, Gloucester (United Kingdom); Kossilov, A [International Atomic Energy Agency, Vienna (Austria)

    1990-07-01

    Automation has long been an established feature of power plants. In some applications, the use of automation has been the significant factor which has enabled plant technology to progress to its current state. Societal demands for increased levels of safety have led to greater use of redundancy and diversity and this, in turn, has increased levels of automation. However, possibly the greatest contributory factor in increased automation has resulted from improvements in information technology. Much recent attention has been focused on the concept of inherently safe reactors, which may simplify safety system requirements and information and control system complexity. The allocation of tasks between man and machine may be one of the most critical activity in the design of new nuclear plants and major retro-fits and it therefore warrants a design approach which is commensurate in quality with the high levels of safety and production performance sought from nuclear plants. Facing this climate, in 1989 the International Atomic Energy Agency (IAEA) formed an advisory group from member countries with extensive experience in nuclear power plant automation. The task of this group was to advise on the appropriate balance between manual and automatic actions in plant operation. (author) [French] L'automatisation a longtemps ete une caracteristique bien etablie des centrales nucleaires. Dans certaines applications, l'utilisation de l'automatisation a ete le facteur decisif qui a permis a la technologie des centrales de progresser jusqu'a son etat actuel. Les exigences de l'opinion publique en matiere de securite renforcee ont conduit a l'utilisation d'une plus grande redondance et a une plus grande diversification et ceci, en retour, a encore accru le niveau d'automatisation. Toutefois, il est possible que le facteur preponderant de cet accroissement de l'automatisation soit constitue par les progres effectues dans la technologie de l'information. Plus recemment, l'attention s

  12. Irradiation and development of the nuclear emulsions exposed to intense fluxes of thermal neutrons with {gamma} rays; Irradiation et developpement des emulsions nucleaires exposees a des flux intenses de neutrons thermiques, accompagnes de rayons {gamma}

    Energy Technology Data Exchange (ETDEWEB)

    Faraggi, H.; Bonnet, A.; Cohen, J. [Commissariat a l' Energie Atomique, Lab. du Fort de Chatillon, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1952-07-01

    The thermal neutron fluxes provided by nuclear reactors permit the survey of relatively rare phenomenons, and dosage of very weak quantities of some elements. One of the most favorable detection technique are constituted by the use of the nuclear emulsions. one can mention: - the dosage of uranium by counting in the emulsion the number of traces due to fission fragments after irradiation. - The dosage of the lithium and the boron as trace amounts with the help of nuclear reactions (n, {alpha}) and thermal neutrons. - The research of reactions (n, {alpha}) or (n, p) of very weak cross section for middle or heavy elements. These different applications require however important neutrons fluxes. It had therefore obliged us to search for the most favorable irradiation and development of the emulsions conditions, to get the best visibility of the trajectories and decrease the phenomena of fog on the emulsion, which prevents any observation. (M.B.) [French] Les flux de neutrons thermiques fournis par les reacteurs nucleaires permettent l'etude de phenomenes relativement rares, et le dosage de tres faibles quantites de certains elements. Un des moyens de detection les plus favorables est constitue par l'utilisation des emulsions nucleaires. on peut citer: - le dosage de l'uranium par comptage dans l'emulsion du nombre de traces dues aux fragments de fission apres irradiation. - Le dosage du lithium et du bore a l'etat de traces a l'aide des reactions (n, {alpha}) sous l'action des neutrons thermiques. - La recherche de reactions (n,{alpha}) ou (n,p) de tres faible section efficace pour des elements moyens ou lourds. Ces differentes applications necessite cependant des flux de neutrons important. On a donc ete amene a rechercher les conditions les plus favorables d'irradiation et de developpement des emulsions, de maniere a obtenir la meilleure visibilite des trajectoires et diminuer les phenomenes de voile de l'emulsion, qui

  13. Contribution to the study of nuclear fuel materials with a metallic uranium base; Contribution a l'etude des materiaux combustibles nucleaires a base d'uranium metallique

    Energy Technology Data Exchange (ETDEWEB)

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

    1957-11-15

    In a power reactor destined to supply industrially recoverable thermal energy, the most economical source of heat still consists of natural metallic uranium. However, the nuclear fuel material, most often employed in the form of rods of 20 to 40 mm diameter, is subjected to a series of stresses which lead to irreversible distortions usually incompatible with the substructure of the reactor. As a result the fuel material must possess at the outset a certain number of qualities which must be determined. Investigations have therefore been carried out, first on the technological characters peculiar to each of the three allotropic phases of pure uranium metal, and on their interactions on the stabilisation of the material which consists of either cast uranium or uranium pile-treated in the {gamma} phase. (author) [French] Dans un reacteur de puissance destine a fournir de l'energie thermique industriellement recuperable, la source de chaleur la plus economique reste constituee par de l'uranium metallique naturel. Or, le materiau combustible nucleaire, employe le plus souvent sous forme de barreaux de 20 a 40 mm de diametre, se trouve soumis a un ensemble de contraintes qui provoque des deformations irreversibles, le plus souvent incompatibles avec l'infrastructure du reacteur. Par consequent, le materiau combustible doit presenter a l'origine un certain nombre de qualites qu'il est necessaire de determiner. Aussi a-t-on d'abord etudie les caracteres technologiques propres a chacune des trois phases allotropiques de l'uranium-metal pur et leurs interactions sur la stabilisation du materiau constitue soit par de l'uranium coule, soit par de l'uranium traite en pile en phase {gamma}. (auteur)

  14. 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

  15. Contribution to the study of radio toxicity of aromatic and medicinal plants using solid state nuclear track detectors; Contribution a l etude de la radio toxicite des plantes aromatiques et medicinales au moyen des detecteurs solides de traces nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Mortassim, A; Misdaq, M A; Naaman, A

    2009-07-01

    The concentrations of uranium (238 U), thorium (232 Th), radon (222 Rn) and thoron (220 Rn) were measured in twenty aromatic and medicinal plants in {sup f}ind a new method based on using solid state nuclear track detectors type Cr-39 and Rs-115. He emerges from this study that the verbena and salvia have higher levels of uranium (radon) higher than that of other plants while the leaves of olive and saturja have concentrations of thorium (thoron) higher than other plants therefore radio toxicity of these plants is higher than that of others and may pose a radiological hazard if the masses are incorporated by consumers high. [French] Les concentrations en uranium (238U), thorium (232Th), radon (222Rn), et thoron (220Rn) ont ete mesurees dans vingt plantes aromatiques et medicinales en utilsant une nouvelle methode basee sur l utilisation des detecteurs solides de traces nucleaires de types CR-39 et LR-115. Il en sort de cette etude que la verveine et la salvia presentent des teneurs en uranium (radon) superieurs a celle des autres plantes alors que les feuilles d olivier et la saturja presentent des concentrations en thorium (thoron) plus elevee que celles des autres plantes par consequent la radio toxicite de ces plantes est superieure a celles des autres et peuvent presenter un risque radiologique si les masses incorporees par les consommateurs sont elevees.

  16. Contribution to the study of the action of electromagnetic fields on the angular correlations of nuclear radiation (1960); Contribution a l'etude de l'action des champs electromagnetiques sur les correlations angulaires des rayonnements nucleaires (1960)

    Energy Technology Data Exchange (ETDEWEB)

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

    1959-01-15

    This work deals with the study of interaction of E.M. fields with nuclear moments of nuclei emitting gamma rays. We describe first experiments on delayed angular correlation showing the role played by statistic quadrupole interaction. We have measured the magnetic moment of the second excited state of {sup 19}F using an external magnetic field. In the case of {sup 19}O, experiments of angular distributions and angular correlations of gamma -rays taking into account the possibility of perturbations, allow us to determine the spin and parities of the three first levels. (author) [French] Le present travail concerne l'etude de l'interaction des champs electromagnetiques et des moments nucleaires de noyaux emettant des rayonnements gamma. Nous decrivons des experiences de correlation angulaire differee dont l'interpretation met en coincidence le role joue par les interactions quadrupolaires statiques. Nous avons mesure le moment magnetique de {sup 19}F dans un etat excite en utilisant un champ magnetique exterieur a la source radioactive. Enfin, dans le cas de {sup 19}O, nous montrons l'utilite d'un examen des possibilites de perturbations dans l'interpretation des resultats fournis par des correlations ou des distributions angulaires. (auteur)

  17. Study relating to the physico-chemical behaviour of heavy water in nuclear reactors; Etudes relatives au comportement physico-chimique de l'eau lourde dans les reacteurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Chenouard, J; Dirian, G; Roth, E; Vignet, P; Platzer, R [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

    1959-07-01

    Chemical and isotope pollution, and radiolytic decomposition are the two most important ways in which heavy water becomes degraded in nuclear reactors. Chemical pollution has led to the creation of ion exchange purification loops specially designed for reactors: the report contains a description in detail of the application of this purification method in CEA research reactors, including the analysis required, results obtained, and their interpretation. The intelligence obtained on radiolytic decomposition with the same facilities is also discussed, as well as the recombination apparatus and control equipment utilized. Finally, investigation to date in the CEA on recombination circuits for power reactors is also discussed. (author) [French] Parmi les degradations subies par l'eau lourde dans les reacteurs nucleaires, les deux plus importantes sont la pollution chimique et isotopique et la decomposition radiolytique. La pollution chimique a conduit a mettre au point pour le cas particulier des reacteurs, des circuits d'epuration par echange d'ions. On decrit ici en detail la mise en oeuvre de cette methode dans les reacteurs de recherche du CEA; les controles qu'elle necessite, les resultats obtenus et leur interpretation. En ce qui concerne la dissociation radiolytique de l'eau, les renseignements obtenus sur ces memes reacteurs sont communiques, ainsi que les details des dispositifs de recombinaison et des moyens de controle. Enfin, on fait le point des etudes poursuivies au CEA sur ces memes problemes de recombinaison dans le cas des reacteurs de puissance. (auteur)

  18. Study relating to the physico-chemical behaviour of heavy water in nuclear reactors; Etudes relatives au comportement physico-chimique de l'eau lourde dans les reacteurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Chenouard, J.; Dirian, G.; Roth, E.; Vignet, P.; Platzer, R. [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

    1959-07-01

    Chemical and isotope pollution, and radiolytic decomposition are the two most important ways in which heavy water becomes degraded in nuclear reactors. Chemical pollution has led to the creation of ion exchange purification loops specially designed for reactors: the report contains a description in detail of the application of this purification method in CEA research reactors, including the analysis required, results obtained, and their interpretation. The intelligence obtained on radiolytic decomposition with the same facilities is also discussed, as well as the recombination apparatus and control equipment utilized. Finally, investigation to date in the CEA on recombination circuits for power reactors is also discussed. (author) [French] Parmi les degradations subies par l'eau lourde dans les reacteurs nucleaires, les deux plus importantes sont la pollution chimique et isotopique et la decomposition radiolytique. La pollution chimique a conduit a mettre au point pour le cas particulier des reacteurs, des circuits d'epuration par echange d'ions. On decrit ici en detail la mise en oeuvre de cette methode dans les reacteurs de recherche du CEA; les controles qu'elle necessite, les resultats obtenus et leur interpretation. En ce qui concerne la dissociation radiolytique de l'eau, les renseignements obtenus sur ces memes reacteurs sont communiques, ainsi que les details des dispositifs de recombinaison et des moyens de controle. Enfin, on fait le point des etudes poursuivies au CEA sur ces memes problemes de recombinaison dans le cas des reacteurs de puissance. (auteur)

  19. Contribution to the study of the action of electromagnetic fields on the angular correlations of nuclear radiation (1960); Contribution a l'etude de l'action des champs electromagnetiques sur les correlations angulaires des rayonnements nucleaires (1960)

    Energy Technology Data Exchange (ETDEWEB)

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

    1959-01-15

    This work deals with the study of interaction of E.M. fields with nuclear moments of nuclei emitting gamma rays. We describe first experiments on delayed angular correlation showing the role played by statistic quadrupole interaction. We have measured the magnetic moment of the second excited state of {sup 19}F using an external magnetic field. In the case of {sup 19}O, experiments of angular distributions and angular correlations of gamma -rays taking into account the possibility of perturbations, allow us to determine the spin and parities of the three first levels. (author) [French] Le present travail concerne l'etude de l'interaction des champs electromagnetiques et des moments nucleaires de noyaux emettant des rayonnements gamma. Nous decrivons des experiences de correlation angulaire differee dont l'interpretation met en coincidence le role joue par les interactions quadrupolaires statiques. Nous avons mesure le moment magnetique de {sup 19}F dans un etat excite en utilisant un champ magnetique exterieur a la source radioactive. Enfin, dans le cas de {sup 19}O, nous montrons l'utilite d'un examen des possibilites de perturbations dans l'interpretation des resultats fournis par des correlations ou des distributions angulaires. (auteur)

  20. Elusloom lennukiga puhkusele / Inge Parring

    Index Scriptorium Estoniae

    Parring, Inge

    2003-01-01

    Ilmunud ka: Delovõje Vedomosti 1. okt. lk. 13. Air Cargo Estonia/ACE Logisticsi müügijuht Inge Parring tutvustab elusloomade transpordivõimalusi. Vt. samas: Loomade transportimiseks vajalikud dokumendid

  1. Par Pond vegetation status 1996

    International Nuclear Information System (INIS)

    Mackey, H.E. Jr.; Riley, R.S.

    1996-12-01

    The water level of Par Pond was lowered approximately 20 feet in mid-1991 in order to protect downstream residents from possible dam failure suggested by subsidence on the downstream slope of the dam and to repair the dam. This lowering exposed both emergent and nonemergent macrophyte beds to drying conditions resulting in extensive losses. A survey of the newly emergent, shoreline aquatic plant communities of Par Pond began in June 1995, three months after the refilling of Par Pond to approximately 200 feet above mean sea level. These surveys continued in July, September, and late October, 1995, and into the early spring and late summer of 1996. Communities similar to the pre-drawdown, Par Pond aquatic plant communities continue to become re-established. Emergent beds of maidencane, lotus, waterlily, watershield, and Pontederia are extensive and well developed. Measures of percent cover, width of beds, and estimates of area of coverage with satellite data indicate regrowth within two years of from 40 to 60% of levels prior to the draw down. Cattail occurrence continued to increase during the summer of 1996, especially in the former warm arm of Par Pond, but large beds common to Par Pond prior to the draw down still have not formed. Lotus has invaded and occupies many of the areas formerly dominated by cattail beds. To track the continued development of macrophytes in Par Pond, future surveys through the summer and early fall of 1997, along with the evaluation of satellite data to map the extent of the macrophyte beds of Par Pond, are planned

  2. 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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-02-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Imyim, A.

    2000-12-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Ganster, P

    2004-10-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-02-15

    . Comme on considere cette operation comme une mesure provisoire, on s'occupe activement de mettre au point une methode permettant de reduire la mobilite des matieres stockees, afin d'etre plus certain de leur confinement a long terme. Dans les reservoirs souterrains existants, on fera evaporer, jusqu'a obtention de tourteaux de sel, les volumes importants de dechets et de gainage, qui, par nature, sont peu susceptibles d'auto-echauffement. Les etudes en laboratoire et les premiers essais effectues avec un reservoir de 5000 gallons montrent que le passage d'un courant d'air chaud a travers la solution, associe a une carbonatation controlee pour transformer Thydroxyde de sodium libre en carbonate de sodium, permet d'eliminer suffisamment d'eau pour former un tourteau de sel non hygroscopique. Les dechets susceptibles d'auto-echauffement seront fractionnes pour permettre d'entreposer separement les emetteurs de chaleur a longue periode dans de petits recipients tres resistants. Etant donne que ces matieres peuvent etre utilisees avec profit, on pourrait en obtenir sur demande. Apres 5 a 10 ans de desintegration des emetteurs de chaleur a courte periode, les dechets salins residuels seront combiries avec les dechets courants de degainage pour evaporation comme il est dit plus haut. Pour pouvoir mener a bien le traitement chimique necessaire, on amenage un ancien batiment a cellules isolees. On recourra probablement a l'extraction par solvant (D2EHPA) pour separer le strontium et le cerium des dechets acides, mais on n'a pas encore decide si la separation du cesium se fera au moyen de l'extraction par solvant, par echanges d'ions ou par precipitation. On prevoit que l'ensemble de l'operation pourra etre realise aux environs de 1966. (author) [Spanish] En los 17 anos que vienen funcionando las instalaciones de Hanford, se ha conseguido un elevado grado de seguridad a un costo razonable almacenando los desechos radioquimicos de elevada actividad en forma de barros alcalinos en

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Lenoir, M.

    2009-09-15

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

  9. Effects of ionizing radiations on reticulated polymers associated to nuclear wastes. The HSF-SIMS technique contribution; Effets des radiations ionisantes sur les polymeres reticules associes aux dechets nucleaires. Apport de la technique HSF-SIMS

    Energy Technology Data Exchange (ETDEWEB)

    Debre, O [Lyon-1 Univ., 69 - Villeurbanne (France). Inst. de Physique Nucleaire

    1997-06-30

    Among the materials used for confinement of nuclear wastes of low and medium level activity the epoxyde resins are known as matrices which preserve well their properties in an ionizing environment. This work is dedicated to the investigation of the modifications occurring in molecular structure of these materials as well as of the ion exchange resins they incorporate, irradiated in different conditions. The first part deals with the analysis of a commercial reticulated epoxyde resin submitted to a 2 MGy integral dose gamma irradiation under two different dose rate (51 and 900 Gy/h), and under two different environments (air and water). The results obtained with the techniques providing structure information (time-of-flight mass spectrometry (HSF-SIMS) and FT-IR spectrometry) confirm those obtained by techniques sensible to macroscopic properties of material (DMA, DSC), taking into account that no noticeable irradiation effect can be made evident inside the material. On the other hand, an irradiation carried out in air results in a superficial oxidation, due probably to the action of the air radiolysis products. The preliminary results of an ion irradiation followed by an in-situ HSF-SIMS analysis pointed out to a basic difference between the energy amount transferred by gamma photons and fast ions; the last ones being able to induce scissions of the nearby liaisons in the material. The second part of this work is concerned with the ion exchange resins of the type PS-DVB saturated in water and non-active ions, simulating real wastes, irradiated in the same conditions as the epoxyde resins. In contrast to the results on the last one, it appears that the irradiation of these materials results primarily in scissions of the functional groups on which the ions are attached. In addition to this finding it appears that the role of water as carrying outward the attached ions appears to be fundamental 175 refs.

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

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

  11. 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.)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2011-02-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2004-07-01

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

  16. Microbial issues pertaining to the canadian concept for the disposal of nuclear fuel waste. Questions a examiner quant aux microbes lors du developpement du concept canadien de stockage permanent des dechets de combustible nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Stroes-Gascoyne, S.; West, J.M.

    1994-01-01

    This report formulates a number of views and positions on microbiological factors that could influence the performance of a disposal vault in plutonic rock. Microbiological factors discussed include the presence and survival of microbes, biofilms, corrosion, biodegradation (of emplaced materials), gas production, geochemical changes, radionuclide migration, colloid formation, mutation, pathogens and methylation. Not all issues can be fully resolved with the current state of knowledge. Studies being performed to underscore and strengthen current knowledge are briefly discussed.

  17. Technique of nuclear reactors controls; Technique des controles des reacteurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

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

    1953-12-15

    This report deal about 'Techniques of control of the nuclear reactors' in the goal to achieve the control of natural uranium reactors and especially the one of Saclay. This work is mainly about the measurement into nuclear parameters and go further in the measurement of thermodynamic variables,etc... putting in relief the new features required on behalf of the detectors because of their use in the thermal neutrons flux. In the domain of nuclear measurement, we indicate the realizations and the results obtained with thermal neutron detectors and for the measurement of ionizations currents. We also treat the technical problem of the start-up of a reactor and of the reactivity measurement. We give the necessary details for the comprehension of all essential diagrams and plans put on, in particular, for the reactor of Saclay. (author) [French] Nous avons aborde le probleme de la ''Technique du Controle des reacteurs nucleaires'' dans le but de realiser le controle du reacteur de Saclay. C'est ainsi que nous avons ete amene a etudier le probleme dans son ensemble, tel qu'il se pose pour tout reacteur a uranium naturel. Ce travail traite principalement du domaine des mesures a caractere nucleaire et s'etend dans le domaine des mesures thermodynamque de niveaux, etc... mettant en relief les caracteristiques nouvelles exigees de la part des detecteurs du fait de leur utilisation dans le flux de neutrons thermiques. Dans le domaine de mesures nucleaires, nous indiquons principalement les realisations et les resultats obtenus pour les detecteurs de neutrons thermiques et pour la mesure de courants d'ionisations. Nous traitons egalement du probleme technique du demarrage d'un reacteur et du probleme de la mesure de la reactivite. Nous donnons les details necessaires a la comrehension de tous les schemas et plans de cablages essentiels mis au point, en particulier, pour le reacteur de Saclay. (auteur)

  18. Vote par sondage uniforme incorruptible

    OpenAIRE

    Blanchard , Nicolas

    2016-01-01

    International audience; Introduit en 2012 par David Chaum, le vote par sondage uniforme (random-sample voting) est un protocole de vote basé sur un choix d'une sous-population représentative , permettant de limiter les coûts tout en ayant de nombreux avantages, principalement lorsqu'il est couplé a d'autres techniques comme ThreeBallot. Nous analysons un problème de corruptibilité potentielle où les votants peuvent vendre leur vote au plus offrant et proposons une variation du protocole reméd...

  19. General trends in the use of uranium in the nuclear industry; Tendances generales d'emploi de l'uranium dans les industries nucleaires

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

    It can be seen from a consideration of the development of the military and civil needs for uranium that, in the long run, the main outlet for the metal will be provided by its industrial applications. The technical uncertainties concerning the best method of producing atomic energy are still numerous and in fact reflect the hesitation in choosing one of two classes of fuel: that based on the metal and that based on the oxide. Four main factors should influence the choice: - the neutron reactivity and the enrichment of the uranium; - the operating temperature; - the resistance to radiation effects; - the chemical stability; but in actual fact, when the choice for a particular use has to be made, it will be another type of factor, such as the cost price, and weight and space considerations which will determine the choice of either metallic uranium or uranium oxide reactors. (author) [French] D'apres le developpement des besoins militaires ou civils en uranium, on voit que les usages industriels de ce metal constituent, a long terme, le debouche essentiel. Les incertitudes techniques, sur le procede optimum pour faire de l'energie nucleaire, restent nombreuses, et se traduisent finalement par une hesitation entre deux grandes classes de combustibles: ceux a base de metal et ceux a base d'oxyde: la preference a l'une ou l'autre de ces deux categories doit s'inspirer de quatre considerations: - la reactivite neutronique et l'enrichissement de l'uranium; - la temperature de fonctionnement; - la resistance aux effets du rayonnement; - la stabilite chimique; mais en definitive, lorsqu'il s'agira d'une application determinee, ce seront des considerations d'un autre ordre, comme le prix de revient, le poids et l'encombrement, qui determineront le choix entre piles a uranium metallique et piles a oxyde d'uranium. (auteur)

  20. 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

  1. Energies and media nr 30. Conditions for the nuclear sector. The fuel cycle and wastes. The usefulness of fuel reprocessing. Wastes; Energies et medias no. 30. La conjoncture, pour le nucleaire. Le cycle du combustible et les dechets. L'utilite du retraitement des combustibles. Les dechets

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2009-10-15

    After some comments on recent events in the nuclear sector in different countries (energy policy and projects in the USA, Europe, China, India, Russia), this issue proposes some explanations on the nuclear fuel cycle and on nuclear wastes: involved processes and products from mining to reprocessing and recycling, usefulness of reprocessing (future opportunities of fast neutron reactors, present usefulness of reprocessing with the recycling of separated fissile materials), impact of reprocessing on the environment in La Hague (gas and liquid releases, release standard definition), and the destiny of wastes

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-09-04

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

  3. Nuclear biological studies in France; Les etudes de biologie nucleaires en France

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-07-01

    On the occasion of a colloquium on radiobiological research programmes, a number of documents dealing with French accomplishments and projects in this field were collected together. We felt that it would be useful to assemble these papers in one report; although they are brief and leave gaps to be filled in, they provide certain data, give an overall view of the situation, and can also suggest a rough plan for the general policy to adopt in the field of 'nuclear' biological research; i.e. research based on the nuclear tracer method or devoted to the action of ionising radiations. (author) [French] Un colloque sur les programmes de recherche en radiobiologie nous a donne l'occasion de reunir des documents sur les realisations et les projets francais dans ce domaine. Il nous a semble utile de reunir en un rapport l'ensemble de ces documents, qui, malgre leur brievete et malgre les lacunes qu'ils comportent, donnent un certain nombre d'informations, permettent une vue d'ensemble et peuvent dessiner aussi l'ebauche d'une politique coherente en matiere de recherches biologiques 'nucleaires', c'est-a-dire de recherches basees sur la methode des indicateurs nucleaires ou consacrees a l'action des rayonnements ionisants. (auteur)

  4. The formation of scientists and technicians at the 'Centre d'Etudes Nucleaires' at Saclay

    International Nuclear Information System (INIS)

    Debiesse, J.

    1958-01-01

    The considerable needs in research workers and scientists which are asked by the nuclear energy obliged the Commissariat a l'Energie atomique to deal with a particular effort to increase the quantitative and qualitative formation of scientists. Most various ways have been used. 1- A National Institute of Nuclear Sciences and Nuclear Techniques was created, by a joint decree of the Prime Minister and the Minister for National Education (june 18, 1957). This Institute of Higher Teaching (250 students) indulges in the following matters: atomic engineering, quantum mechanics, theory and technic of particle accelerators, special metallurgy, radiobiology, thermic and mechanics of fluids. 2- An associated centre of the 'Conservatoire National des Arts et Metiers' was created (200 students) for technical assistants, drawers, etc. 3- In contribution with both electronic industry and Ministry of Work, the Centre d'Etudes Nucleaires contributes to an accelerated formation of technical assistants into Professional Centres. Conclusion: Training of scientists and research workers is one of the most important activities of the Centre d'Etudes Nucleaires de Saclay. Without losing its technical efficiency, it has supplied and varied means adapted to the various purposes that we shall reach. (author) [fr

  5. Nuclear biological studies in France; Les etudes de biologie nucleaires en France

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-07-01

    On the occasion of a colloquium on radiobiological research programmes, a number of documents dealing with French accomplishments and projects in this field were collected together. We felt that it would be useful to assemble these papers in one report; although they are brief and leave gaps to be filled in, they provide certain data, give an overall view of the situation, and can also suggest a rough plan for the general policy to adopt in the field of 'nuclear' biological research; i.e. research based on the nuclear tracer method or devoted to the action of ionising radiations. (author) [French] Un colloque sur les programmes de recherche en radiobiologie nous a donne l'occasion de reunir des documents sur les realisations et les projets francais dans ce domaine. Il nous a semble utile de reunir en un rapport l'ensemble de ces documents, qui, malgre leur brievete et malgre les lacunes qu'ils comportent, donnent un certain nombre d'informations, permettent une vue d'ensemble et peuvent dessiner aussi l'ebauche d'une politique coherente en matiere de recherches biologiques 'nucleaires', c'est-a-dire de recherches basees sur la methode des indicateurs nucleaires ou consacrees a l'action des rayonnements ionisants. (auteur)

  6. Associative memories in nuclear physics; Les memoires associatives en physique nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Blanca, E; Carriere, A [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1967-07-01

    Experiments in nuclear physics involve the use of large size 'memories'. After showing the difficulties arising from the use of such memories, the authors give the principles of the various programming methods which make it possible to operate the memories associatively thus benefiting from a reduction in size and better operational conditions. They attempt to estimate the shape and dimensions of an associative memory with cable connections which could be designed specially for nuclear research, contrary to those actually in service. (authors) [French] Les experiences de physique nucleaire necessitent l'emploi de 'memoires' de grandes dimensions. Apres avoir montre les inconvenients que presente l'utilisation de telles memoires, les auteurs exposent les principes des diverses methodes de programmation qui permettent d'assurer un fonctionnement des memoires sur le mode associatif donc une reduction de leurs dimensions et un meilleur usage. Ils tentent d'evaluer le format d'une memoire associative cablee qui, contrairement a celles qui existent actuellement, serait prevue specialement pour l'experimentation nucleaire. (auteurs)

  7. Analytic index for nuclear physicians uses; Repertoire analytique a l'usage des physiciens nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Ballini, R.; Barloutaud, R.; Bernas, R.; Bretonneau, P.; Chaminade, R.; Cohen, R.; Conjeaud, M.; Cotton, E.; Faraggi, H.; Grjebine, T.; Joffre, H.; Laboulaye, H. de; Lesueur, C.; Leveque, A.; Moreau, J.; Naggiar, V.; Papineau, L.; Prugne, P.; Schuhl, C.; Studinowski, FJ.; Netter, F.; Raievski, V.; Valladas, G. [Commissariat a l' Energie Atomique, Lab. du Fort de Chatillon, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires; Marty, N.; Renard, G. [College de France, Lab. de Chimie Nucleaire (France)

    The problem of the documentation in nuclear physics becomes constantly more complex. Every week brings its share of new publications, always more numerous and more varied. To remedy to this facts that we tried, in the service of Nuclear Physics of the CEA, to give to the documentation a character of a collective and systematized work. The present report covers the literature appeared between first January 1950 and first July 1951. (Volume 1: CEA report number 120; Volume 2: CEA report number 184). (M.B.) [French] Le probleme de la documentation en physique nucleaire devient sans cesse plus complexe. Chaque semaine apporte son lot de publications, toujours plus nombreuses et plus diversifiees. C'est pour essayer de porter remede a cet etat de choses que nous avons essaye, au service de Physique Nucleaire du C.E.A., de donner a la documentation le caractere d'un travail collectif systematise. Le present rapport couvre la litterature parue entre le premier Janvier 1950 et le premier Juillet 1951. (Tome 1: Rapport CEA numero 120; Tome 2: Rapport CEA numero 184). (M.B.)

  8. Par Pond Fish, Water, and Sediment Chemistry

    Energy Technology Data Exchange (ETDEWEB)

    Paller, M.H. [Westinghouse Savannah River Company, AIKEN, SC (United States); Wike, L.D.

    1996-06-01

    The objectives of this report are to describe the Par Pond fish community and the impact of the drawdown and refill on the community, describe contaminant levels in Par Pond fish, sediments, and water and indicate how contaminant concentrations and distributions were affected by the drawdown and refill, and predict possible effects of future water level fluctuations in Par Pond.

  9. Par Pond Fish, Water, and Sediment Chemistry

    International Nuclear Information System (INIS)

    Paller, M.H.; Wike, L.D.

    1996-06-01

    The objectives of this report are to describe the Par Pond fish community and the impact of the drawdown and refill on the community, describe contaminant levels in Par Pond fish, sediments, and water and indicate how contaminant concentrations and distributions were affected by the drawdown and refill, and predict possible effects of future water level fluctuations in Par Pond

  10. 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

  11. 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

  12. Contribution to the determination of Sb-Ag-Cu-Ga-Mo-Zn using 14 MeV neutron activation; Contribution au dosage de Sb-Ag-Cu-Ga-Mo-Zn par activation aux neutrons de 14 MeV

    Energy Technology Data Exchange (ETDEWEB)

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

    1966-04-01

    By using, 14 MeV, neutron irradiation it is possible to extend the field of application of neutron radio-activation analysis, in particular to the case of light elements. For, many other elements it can replace in-pile irradiation thereby making it possible, thanks to portable 14 MeV neutron generators, to carry out radio-activation analyses away from nuclear-research c e n t r e s. With a view to applying this analytical technique to routine work, we have developed some rapid chemical separation methods in order to make possible the determination of several elements which after exposure to fast neutrons, produce {beta} emitting nuclides which cannot be differentiated by a simple instrumental study, the emitted radiation being of the same type and of similar half-life the two cases. (author) [French] L'irradiation au moyen de neutrons de 14 MeV permet d'etendre le domaine d'application de l'analyse par radioactivation neutronique, en particulier aux elements legers. Cependant pour de nombreux autres elements elle peut remplacer l'irradiation en reacteur nucleaire permettant ainsi grace aux ensembles portables producteurs de neutrons de 14 MeV, l'extension de l'analyse par radioactivation a l'exterieur des centres d'etudes nucleaires. Dans le but d'appliquer cette methode d'analyse a des travaux de routine, nous avons mis au point des separations chimiques rapides, afin de permettre le dosage de quelques elements qui par irradiation aux neutrons rapides, engendrent des nucleides emetteurs {beta} qu'une simple etude instrumentale ne peut differencier en raison de l'identite de leur rayonnement et de leurs periodes radioactives trop proches. (auteur)

  13. Some fundamental aspects of boiling in nuclear reactors; Quelques aspects fondamentaux de l'ebullition dans les reacteurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Mondin, H; Lavigne, P; Semeria, R [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

    1964-07-01

    oscillation, the conditions of burnout are compared with those obtained under steady conditions. The burn-out flux following uniform 'stopped' heating has been studied in a channel containing still water. The flux shows a maximum as a function of unsaturation. The influence of the geometry and the nature of the metal was investigated. 4 - Output Oscillations: Using a low pressure (8 atm) loop, the influence of various parameters on the periods of output oscillations in a boiling channel on the thresholds at which they appear, was studied. Some new aspects of this complex phenomena were observed and are reported. (authors) [French] On indique les principaux resultats obtenus a Grenoble depuis quatre ans dans le domaine des mecanismes de l'ebullition et des phenomenes connexes dans les reacteurs nucleaires. 1 - OBSERVATION DE L'EBULLITION: Par photographie et cinematographie ultrarapide (8000 images par seconde maximum) on a observe l'ebullition en vase ou en canal jusqu'a 140 kg/cm{sup 2}. On a denombre les populations de germes (sites) generateurs de bulles et obtenu une correlation donnant leur nombre par unite de surface en fonction du flux thermique et de la pression. Le diametre des bulles se detachant de la paroi a ete etudie jusqu'a 140 kg/cm{sup 2}. On a mis en evidence trois types de bulles: - Les bulles en equilibre dont le diametre suit la formule de Fritz et Ende, - Les bulles d'ebullition dont le diametre diminue rapidement avec la pression (1/100 mm a 140 kg/cm{sup 2}), - Les coalescences apparaissant en liquide sature au-dessus de 15 W/cm{sup 2} et dont la proportion est independante de la pression. Par visualisation en strioscopie on observe les mouvements du film thermique associes a l'amorcage des germes, au depart et a la condensation des bulles; les mecanismes responsables de l'excellent transfert de chaleur ont pu ainsi etre precises. 2 - PERTES DE PRESSION EN ECOULEMENT DIPHASE: On a etabli un modele de variation continue du taux de vide dans un canal

  14. Integration of the nuclear energy among the production facilities of energy in France; Integration de l'energie nucleaire parmi les moyens de production de l'energie en france

    Energy Technology Data Exchange (ETDEWEB)

    Ailleret, P [Electricite de France (EDF), 75 - Paris (France). Direction des Etudes et Recherches; Taranger, P [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1955-07-01

    The present report gives an overview of the present facilities of energy productions in France and their perspectives. the electric production comes for half about power stations hydraulics and for half of thermal power stations. However due to the increase of the energy consumption, France is particularly interested by the atomic energy that appears to bring a supply in due time to the hydraulics and to limit a development of the thermal power stations to which the natural resources of France in classic fuel would not permit to cope presumably. The integration of the nuclear plants to the other production facilities will make itself gradually according to the evolution of the energy needs. (M.B.) [French] Le present rapport donne un apercu des moyens actuels de productions energetiques en France et de ses perspectives. la production electrique provient pour moitie environ de centrales hydraulique et pour moitie de centrales thermiques. Cependant face a l'augmentation de la consommation energetique, la France est tres particulierement interessee par l'energie atomique qui parait devoir apporter en temps utile la releve a l'hydraulique et limiter un developpement des centrales thermiques auxquels les ressources naturelles de la France en combustible classique ne permettraient vraisemblablement pas de faire face. L'integration des centrales nucleaires aux autres moyens de production se fera graduellment en fonction de l'evolution des besoins energetiques. (M.B.)

  15. Review of Development Status of Nuclear Superheat; Expose sur l'etat actuel des travaux concernant la surchauffe nucleaire; Obzor razrabotki voprosa o yadernykh peregrevatelyakh; Estudio de los progresos realizados en niateria de sobrecalentamiento nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Imhoff, D. H.; Pennington, R. T. [General Electric Company, San Jose, CA (United States)

    1963-10-15

    fuel irradiation performance, in-pile and out-of-pile uniform and localized corrosion evaluations, results from thermal superheat critical experiments, results from experimental heat-transfer testing and a brief appraisal of the economic incentives of the separate superheat reactor, integral superheat reactor, and mixed-spectrum superheat reactor design studies. (b) A brief description is given of the USAEC-Sponsored ESADA-VESR nuclear superheat fuel development programme. The development tasks, the initial core superheat fuel-element design, the range of experimental variables, and the expected results for the three-year fuel development programme are discussed. (author [French] Depuis 1959, la Societe General Electric s'occupe activement de mettre au point la surchauffe nucleaire dans les reacteurs ralentis a l'eau ordinaire. A cette epoque, le ''Superheat Advance Demonstration Experiment'' (SADE), finance par la societe, a permis d'obtenir, pour la premiere fois aux Etats-Unis, de la vapeur surchauffee par un dispositif nucleaire. Les auteurs du memoire font le point de la situation actuelle concernant la surchauffe nucleaire. Ils decrivent, dans une premiere partie, les trois principales installations de surchauffe nucleaire utilisees par la General Electric et, dans la seconde, les deux principaux programmes de recherches sur la surchauffe ainsi que les resultats les plus importants obtenus jusqu'ici dans ce domaine. 1. Principales installations pour les experiences de surchauffe: a) Breve description du SADE utilise dans le reacteur a eau bouillante de Vallecitos (VBWR), avec tableaux des conditions dans lesquelles se deroulent les experiences, et des elements combustibles irradies pendant la periode comprise entre mai 1959 et juin 1962; puis examen critique des resultats les plus importants ainsi obtenus. b) Breve description de l' ''Expanded Superheat Advance Demonstration Experiment'' (E-SADE) installe dans le reacteur de Vallecitos, avec tableaux des

  16. Directed and persistent movement arises from mechanochemistry of the ParA/ParB system.

    Science.gov (United States)

    Hu, Longhua; Vecchiarelli, Anthony G; Mizuuchi, Kiyoshi; Neuman, Keir C; Liu, Jian

    2015-12-22

    The segregation of DNA before cell division is essential for faithful genetic inheritance. In many bacteria, segregation of low-copy number plasmids involves an active partition system composed of a nonspecific DNA-binding ATPase, ParA, and its stimulator protein ParB. The ParA/ParB system drives directed and persistent movement of DNA cargo both in vivo and in vitro. Filament-based models akin to actin/microtubule-driven motility were proposed for plasmid segregation mediated by ParA. Recent experiments challenge this view and suggest that ParA/ParB system motility is driven by a diffusion ratchet mechanism in which ParB-coated plasmid both creates and follows a ParA gradient on the nucleoid surface. However, the detailed mechanism of ParA/ParB-mediated directed and persistent movement remains unknown. Here, we develop a theoretical model describing ParA/ParB-mediated motility. We show that the ParA/ParB system can work as a Brownian ratchet, which effectively couples the ATPase-dependent cycling of ParA-nucleoid affinity to the motion of the ParB-bound cargo. Paradoxically, this resulting processive motion relies on quenching diffusive plasmid motion through a large number of transient ParA/ParB-mediated tethers to the nucleoid surface. Our work thus sheds light on an emergent phenomenon in which nonmotor proteins work collectively via mechanochemical coupling to propel cargos-an ingenious solution shaped by evolution to cope with the lack of processive motor proteins in bacteria.

  17. Material movement of medium surrounding an underground nuclear explosion; Mouvement materiel du milieu environnant une explosion nucleaire souterraine

    Energy Technology Data Exchange (ETDEWEB)

    Guerrini, C; Garnier, J L [Commissariat a l' Energie Atomique, Bruyeres-le-Chatel (France). Centre d' Etudes

    1969-07-01

    The results of measurements of the mechanical effects in the, intermediate zone around underground nuclear explosions in Sahara granite are presented. After a description of the main characteristics of the equipment used, the laws drawn up using experimental results for the acceleration, the velocity, and the material displacement are presented. These laws are compared to those published in other countries for nuclear tests in granite, in tuff and in alluvial deposits. (authors) [French] Les resultats de mesures d'effets mecaniques en zone intermediaire autour d'essais nucleaires souterrains dans le granite du Sahara sont exposes. Apres avoir decrit, dans leurs grandes lignes, les materiels utilises, on presente les lois etablies avec les resultats experimentaux pour l'acceleration, la vitesse et le deplacement materiel. Ces lois sont comparees a celles publiees a l'etranger pour des essais nucleaires dans le granite, le tuf et les alluvions. (auteur)

  18. Contribution to the study of several chemical hazards in the Centre d'Etudes Nucleaires of Fontenay-aux-Roses; Contribution a l'etude de quelques nuisances chimiques au centre d'etudes nucleaires de Fontenay-aux-Roses

    Energy Technology Data Exchange (ETDEWEB)

    Megemont, C; Grau, C [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1968-10-01

    From the checking of 2750 index cards of hazards, the study relates the distribution of the chemical hazards in the Centre d'Etudes Nucleaires of Fontenay-aux-Roses. Those concerning the greatest number of agents in the Centre are classified according to the categories corresponding to the different conditions of working. Thus, the most important are put forward. Then, the authors rapidly make a review of hazards which may have some special interest because they appear more specific of the nuclear energy or because they are the most frequently noted on the index cards of hazards. The case of the tributylphosphate is studied more precisely. (authors) [French] A partir de l'examen de 2750 fiches de nuisances, l'etude porte sur la repartition des nuisances chimiques au Centre d'Etudes Nucleaires de Fontenay-aux-Roses. Celles qui concernent le plus grand nombre d'agents du Centre sont classees selon les categories correspondant aux differentes conditions de travail. Les plus importantes d'entre elles sont ainsi mises en evidence. | Les auteurs passent ensuite en revue, rapidement, les nuisances qui peuvent presenter un interet particulier soit parce qu'elles semblent plus specifiques de l'Energie Nucleaire, soit parce qu'on les rencontre le plus frequemment sur les fiches de nuisances. Le cas du tributylphosphate est envisage de facon plus detaillee. (auteurs)

  19. The 1989 annual report of the Institut de Physique Nucleaire-Orsay

    International Nuclear Information System (INIS)

    1989-01-01

    The activity report of the Institut de Physique Nucleaire (Orsay-France) from 1 Sep 1988 to 1 Aug 1989 is presented. Theoretical and experimental investigations were carried out in the following fields: light and medium exotic nuclei, on line spectroscopy, discrete high spin states, new radioactivities, thermal fission, detection systems, giant resonances, high excitation energy structure, reaction mechanisms at energies below 10 MeV/u and at 200 MeV/u and their evolution between 10 and 100 MeV/u, meson production, transfer reactions, spin modes in nuclei, dibaryonic resonances, inelastic scattering of polarized protons. Research programs in the field of radiochemistry and relating to inter-disciplinary fields are included. The activities involving teaching, the lists of publications conferences, seminars and theses are presented [fr

  20. Recherche documentaire par titrage automatique

    OpenAIRE

    Lopez , Cédric; Prince , Violaine; Roche , Mathieu

    2011-01-01

    Nous proposons dans cet article un système facilitant la recherche d'information dans un ensemble de documents textuels, basé sur le titrage (et sous-titrage) automatique. Ce dernier peut se révéler crucial, par exemple, dans le cadre de la problématique de l'accessibilité des pages web (norme W3C). Notre processus de titrage automatique consiste à extraire des syntagmes nominaux pertinents dans les textes, pouvant constituer des titres ou sous-titres candidats. Une approche originale combina...

  1. Study methods for the drillings around the underground nuclear explosions in the Sahara. Part 1. study of rock samples; Methodes d'etude des forages realises autour des explosions nucleaires souterraines au Sahara. Premiere partie: etude des echantillons de roche

    Energy Technology Data Exchange (ETDEWEB)

    Derlich, S [Commissariat a l' Energie Atomique, Bruyers-le-Chatel (France). Centre d' Etudes

    1969-07-01

    An examination of the mechanical effects produced on rocks by an underground nuclear explosion calls for the use of particular means of exploration which are described in this report, special attention being paid to the equipment used in connection with the French nuclear tests in the Sahara. The drilling methods used (rotary and turbo-drilling) are adapted to the particular conditions of the sampling programme, to the radioactivity and to the temperature in the region of the explosion. A study of the samples makes it possible to obtain the new characteristics of the rock and to assess the chemical and mechanical transformations which it has undergone. An examination of the core obtained from the drilling, together with a knowledge of the drilling parameters (depth of the probe, sample recovery, etc...), makes it possible to study the extent and the characteristics of the zones which have been damaged to different degrees according to their distance from the zero point: cavity, strongly powdered zone, fractured zone, chimney, zones containing high stresses leading to a particular type of fracture of the cores. The problems connected with the interpretation of the results are also presented. (author) [French] L'examen des effets mecaniques provoques par une explosion nucleaire souterraine sur la roche necessite la mise en oeuvre de moyens d'exploration particuliers dont l'expose fait l'objet de ce rapport, essentiellement pour les moyens utilises autour des essais nucleaires francais au Sahara. Les methodes de forage (rotary et turboforage) sont adaptees aux conditions particulieres dues au programme d'echantillonnage, a la radioactivite et a la temperature regnant a proximite du point de tir. L'etude des echantillons permet la determination des nouveaux caracteres de la roche et de ses transformations chimique et mecanique. L'examen des carottes et l'utilisation des parametres de forage (cotes sondeurs, recuperation des echantillons, etc...) permettent d'etudier l

  2. 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

    'essentiel d'une reglementation satisfaisante, il faut ajouter les substances radioactives provenant des retombees et qui penetrent dans les eaux par voie d'ecoulement ou sous forme de depot direct. Etant donne que les memes cours d'eau peuvent servir a une multiplicite d'usages, tels que la fourniture d'eau potable et d'eau a usage industriel, les sports nautiques, la peche, l'irrigation et la navigation, il y a lieu d'evaluer minutieusement l'effet de l'evacuation des dechets, sur chacune de ces activites. Les criteres actuels n'ofirent pas de donnees completes pour la determination des niveaux admissibles d'evacuation, a moins qu'on ne possede des renseignements sur les quantites de radionuclides determines deja contenues dans les eaux et sur ce qu'il advient de ces radionuclides lorsqu'ils sont entraines en aval. Les niveaux admissibles d'evacuation devront etre modifies conformement aux renseignements precites, en tenant compte particulierement des emplois que l'on fait de l'eau en aval. Lorsqu'on autorise, sur un cours d'eau donne, des ecoulements de plusieurs origines differentes, il est indispensable de fixer des quantites maxima de radionuclides determines, en prenant en consideration la mesure dans laquelle les populations residant en aval sont exposees aux rayonnements quelle que soit leur source. Les auteurs du memoire suggerent plusieurs methodes permettant de resoudre le probleme que pose le traitement des dechets eu egard a l'utilisation des cours d'eau en aval; ils examinent plusieurs des difficultes qui resultent de l'application des differentes methodes envisagees. (author) [Spanish] Cada ano es mayor la cantidad de desechos radiactivos que se vierten en las corrientes fluviales, como consecuencia de la labor de numerosos laboratorios comerciales que utilizan materials radiactivos y como resultado tambien del funcionamiento de las instalaciones de energia atomica. A los desechos que se evacuan directamente en los rios en condiciones rigurosamente controladas

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

    For low-level waste disposal in coastal waters the character of the biota and the eating habits of local human populations will determine the safe limits of contamination. In such a situation the sedimentary bottom populations win be important, since they will be exposed continuously, while planktonic and fish populations will drift through or enter the area of contamination sporadically. In the open ocean, on the other hand, planktonic populations are of prime importance, both as the food supply of pelagic edible species, and because they may be effective in transporting isotopes. Similar questions face biologists studying either sedentary or planktonic populations. These include the need to know the distribution and density of populations of various species, the rate of growth of the individuals and of the populations, the seasonal cycle of production and of abundance, the ability of various organisms to accumulate various elements, and the ways in which these elements are transported through the food web, to the bottom through sedimentation or vertically within the water column through migration and exchange. For each specific waste-disposal problem a survey of the local biota will be required, as will the subsequent monitoring of the operation. (author) [French] En ce qui concerne l'evacuation des dechets de faible activite dans les eaux cotieres, les limites de securite pour la contamination seront determinees par le milieu biologique et le regime alimentaire des habitants de la region. Dans une telle situation, ce sont les populations du fond sedimentaire qui joueront un role important puisqu'elles subissent une exposition permanente alors que le plancton et les poissons n'entrent dans les regions contaminees qu'en passant ou dans des cas isoles. En revanche, dans la haute mer, les populations planctoniques sont d'une importance primordiale a la fois comme source alimentaire pour les especes pelagiques comestibles et comme transporteurs eventuels d

  4. 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

  5. SECHAGE DE PRODUITS GRANULAIRES PAR DESHYDRATATION PAR DETENTES SUCCESSIVES (DDS)

    OpenAIRE

    Abdulla , Galal; Mellouk , Hamid; Belghit , Abdelhamid; Allaf , Karim

    2009-01-01

    International audience; Dans cette étude, nous avons évalué les performances d'un nouveau procédé de séchage dans le cas du liège en granulés. Ce procédé (La déshydratation par détentes successives : DDS) consiste à soumettre le matériau liège dans une chambre hermétique aux variations cycliques de la pression. Chaque cycle est composé d'une compression et d'une décompression. La phase de compression est réalisée en injectant de l'air comprimé à température ambiante provenant d'un compresseur...

  6. 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

  7. Mechanics and electronics as auxiliary techniques in nuclear research and exploitation; Mecanique et electronique auxiliaires de la recherche et de l'exploitation nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Weill, J. [Commissariat a l' energie atomique et aux energies alternatives - CEA, Centre d' Etudes nucleaires de Saclay, Departement Electronique, Groupe Controle des Reacteurs (France)

    1959-07-01

    Electronics and mechanics form the basic techniques used in the field of measurement and control in nuclear physics experiments, and in nuclear machine installations. The delegate describes some instruments typical of the use of these techniques in the fields of calculation, detection, amplification and nuclear Installations. Reprint of a paper published in 'Bulletin S.F.M.' n. 25 (3. quarter 1957) [French] L'electronique et la mecanique constituent les techniques de base utilisees clans le domaine des mesures et du controle effectues dans les experiences de physique nucleaire et dans les installations des engins nucleaires. Le Conferencier decrit plusieurs appareils caracteristiques de l'emploi de ces techniques dans les domaines du calcul, des detecteurs, de l'amplification et des lnstallations nucleaires. Reproduction d'un article publie dans le 'Bulletin S.F.M.' n. 25 (3e trimestre 1957)

  8. La preuve par le nombre

    Directory of Open Access Journals (Sweden)

    Hélène Verdier

    2012-04-01

    Full Text Available S’il en était besoin, la question des usages et de la finalité des résultats de l’inventaire général pourrait être abordée par le nombre : nombre d’œuvres répertoriées, de communes inventoriées, de clichés photographiques réalisés, de dossiers, de consultations des notices dans les bases de données… Les additions aujourd’hui sont éloquentes, mais elles laissent dans l’ombre le rôle de l’inventaire qui, en mettant en œuvre une démarche systématique de connaissance, participe à l’ identificatio...

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

  10. Par Pond vegetation status Summer 1995 -- Summary

    International Nuclear Information System (INIS)

    Mackey, H.E. Jr.; Riley, R.S.

    1996-01-01

    The water level of Par Pond was lowered approximately 20 feet in mid-1991 in order to protect downstream residents from possible dam failure suggested by subsidence on the downstream slope of the dam and to repair the dam. This lowering exposed both emergent and nonemergent macrophyte beds to drying conditions resulting in extensive losses. A survey of the newly emergent, shoreline aquatic plant communities of Par Pond began in June 1995, three months after the refilling of Par Pond to approximately 200 feet above mean sea level. These surveys continued in July, September, and late October, 1995. Communities similar to the pre-drawdown, Par Pond aquatic plant communities are becoming re-established. Emergent beds of maidencane, lotus, waterlily, and watershield are extensive and well developed. Cattail occurrence continued to increase during the summer, but large beds common to Par Pond prior to the drawdown have not formed. Estimates from SPOT HRV, remote sensing satellite data indicated that as much as 120 hectares of emergent wetlands vegetation may have been present along the Par Pond shoreline by early October, 1995. To track the continued development of macrophytes in Par Pond, future surveys throughout 1996 and 1997, along with the continued evaluation of satellite data to map the areal extent of the macrophyte beds of Par Pond, are planned

  11. 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

  12. SCPRI Emergency Kit for Use in the Event of a Nuclear Accident; Le Dispositif d'Intervention Rapide du SCPRI en Cas d'Accident Nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Ervet, P.; Moroni, J. P.; Pellerin, P. [Service Central de Protection Contre les Rayonnements Ionisants, Ministere des Affaires Sociales, Le Vesinet (France)

    1969-10-15

    In the event of a nuclear accident necessitating implementation of the ORSEC radiation protection plan, the Service central de protection contre les rayonnements ionisants (Central Service for Protection against Ionizing Radiations), in conjunction with the Service national de la protection civile (National Civil Defence Service), has adopted the necessary measures for rapid evaluation of possible contamination as promptly as possible. With this aim in mind the Service has prepared emergency kits, which are permanently stored at airfields in the Paris region; these can be carried by aircraft together with two engineers from the Service, thereby enabling them to reach the site of the incident with the specialized equipment in a few hours at most. This paper describes the monitoring and sampling equipment as well as the conditions under which the kit is carried and used (it operates independently by having a built-in generating unit). It is basically designed to permit an initial assessment of the situation, to furnish local authorities with data on which to base decisions for the safety of the population, and to determine any additional measures that need to be adopted. (author) [French] Dans le cas d'un accident nucleaire impliquant la mise en application du plan ORSEC radiologique, en liaison avec le Service national de la protection civile, le Service central de protection contre les rayonnements ionisants a pris les dispositions necessaires pour faire une evaluation rapide, aussi preooce que possible, des contaminations eventuelles. Dans ce but, il a realise des cantines d'intervention qui sont deposees en permanence sur les aerodromes de la region parisienne, et peuvent etre embarquees par avion avec deux ingenieurs du service qui peuvent etre ainsi sur les lieux de l'incident, avec un materiel specialise, dans un delai qui n'excede pas quelques heures. Le memoire decrit le materiel de mesure et de prelevement, ainsi que les conditions de transport et d

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-02-15

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

  14. The study of neutron transport by oscillation method; Etude du transport des neutrons par la methode de modulation

    Energy Technology Data Exchange (ETDEWEB)

    Raievski, V

    1959-07-01

    The oscillation method is of very general use for studying the behavior of thermal neutrons in media. The main experiments are described and a general theory of them is given. This theory, which is presented in the first part, is established using the two-group approximation which has proved its efficiency in the case of thermal neutron piles. The validity of the two-group approximation is recalled. This allows definition of the meaning of the parameters used in the theory and which are measured in these experiments. The experiments carried out by this method are described, especially those performed at the Centre d'Etudes Nucleaires de Saclay where the method has been extensively used. These experiments are interpreted by means of the general theory given previously. In this way, the identity of parameters measured by this method and those given by the theory is proved. This is particularly conclusive is the case of the mean life of neutrons in a pile. (author) [French] La methode de modulation est un procede tres general d'etude des proprietes neutroniques des milieux contenant des neutrons thermiques. Le present rapport a pour but de decrire les principales de ces experiences et d'en donner une theorie generale. Cette theorie, exposee dans la premiere partie, est etablie dons le cadre de l'approximation a deux groupes de vitesse qui a prouve son efficacite dons le cas des piles a neutrons thermiques. Le domaine de validite de l'approximation a deux groupes est rappele au debut, ce qui permet de definir avec precision la signification des parametres qui entrent dons la theorie et qui font l'objet de ces mesures. La deuxieme partie decrit les experiences realisees, en particulier celles effectuees au Centre d'Etudes Nucleaires de Saclay ou la methode a ete considerablement developpee. Ces experiences sont interpretees dans le cadre de la theorie generale exposee precedemment. On prouve ainsi l'identite des parametres mesures par cette methode et de ceux figurant

  15. ¡París!

    Directory of Open Access Journals (Sweden)

    Beatriz Caballero

    2003-01-01

    Full Text Available El día no le alcanzaba para caminarlo. Conocía cada puente, cada calle,plaza, museo, rincón, iglesia, café, y la mesa con el mejor ángulo para mirar siempre una iglesia, ojalá Saint-Germain-des-Pres, o Notre-Dame. Siempre contaba la impresión que le había causado a Bolívar ver allí cuando el papa coronó a Napoleón. Él se iba para la oficina todos los días, Luis a un taller a pintar, Antonio a estudiar ciencias políticas, yo al colegio y mamá hacía las cosas prácticas. Aprendíamos francés todos al tiempo y por la noche nos contábamos lo nuevo que cada uno había aprendido. Mamá después, cuando ya se quería volver, decía que París nos había maleado a todos. Estaba en pleno furor el cine francés de la "nueva ola", pero ella sólo me llevaba a ver películas de vaqueros pues no se fiaba de la clasificación de los periódicos.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-02-15

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

  17. Piles used for the nuclear control of materials; Empilements pour le controle nucleaire des materiaux

    Energy Technology Data Exchange (ETDEWEB)

    Raievski, V; Sautiez, B; Bailly du Bois, B; Tretiakoff, O; Thome, P; Vidal, R; Koppel Martelly, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    The devices which make it possible to check on the nuclear qualities of the materials used in reactor construction are described. These verifications bear on substantial masses of materials, following the last stage of their machining. The components found in all these are a graphite pile into which the material to be investigated is inserted, a source of neutrons made up of an Ra-Be system, and a proportional BF{sub 3} counter. The devices described here bear on checking graphite, beryllium oxide and uranium absorption, as well as on a verification of the {sup 235}U content of fuel elements. (author)Fren. [French] On decrit des dispositifs permettant de controler les qualites nucleaires de materiaux utilises dans la construction des piles. Ce controle s'effectue sur des masses importantes de materiaux apres la phase finale d'usinage. Ces dispositifs ont en commun un empilement de graphite recevant le materiau a etudier, une source de neutrons de Ra-Be et un compteur proportionnel a BF{sub 3}. Les dispositifs decrits concernent le controle de l'absorption du graphite, de la glucine et de l'uranium, ainsi que le controle de la teneur en {sup 235}U des elements de combustion. (auteur)

  18. Underground nuclear explosions. Geological survey of the cavities; Explosions nucleaires souterraines etude geologique des cavites

    Energy Technology Data Exchange (ETDEWEB)

    Faure, J [Commissariat a l' Energie Atomique, Bruyeres-le-Chatel (France). Centre d' Etudes

    1969-07-01

    A geological survey of underground nuclear explosions makes it possible to determine the main characteristics of the cavity formed. The lower portion is spherical; the same was very likely true of the roof, which collapses in the majority of media with the exception of rock-salt. Its radius, for a given bomb size, can vary by a factor of two according to the type of rock. The lay-out of its contents depends on the characteristics of the solid and liquid products at the moment of the roof collapse; according to the medium involved, mixing of the rubble and the mud-flow occurs (granite) or does not occur (tuff and alluvia). In all media, the average physical properties can be evaluated. (author) [French] L'etude geologique d'explosions nucleaires souterraines permet de determiner les principaux caracteres de la cavite creee. Sa partie inferieure est spherique; il en etait vraisemblablement de meme de sa voute, effondree dans la plupart des milieux a l'exception du sel gemme. Son rayon, a energie d'engin egale, varie selon les roches du simple au double. La disposition de son contenu depend des caracteristiques des produits solides et liquides au moment de la chute du toit; selon le cas, il n'y a pas (tuf et alluvions) ou il y a (granite) melange des eboulis et des laves. Dans tous les milieux, les proprietes physiques moyennes peuvent etre evaluees. (auteur)

  19. Improvements to the properties of uranium by addition of small quantities of other metals; Ameliorations apportees a l'uranium par de faibles additions metalliques

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

    {sup 235}. Dans les conditions optimales de fonctionnement, un meme materiau combustible doit alors fournir un minimum de 3000 MWj/t, soit 72.10{sup 6} kWh par tonne d'uranium naturel, tout en etant porte a une temperature suffisante pour jouer efficacement son role de source de chaleur (entre 350 et 550 deg. C minimum). Or d'une facon assez surprenante, les agregats polycristallins des billettes d'uranium obtenues par coulee sous vide, ou apres filage a haute temperature, se presentent comme un ensemble de grains tres grossiers, a contours dechiquetes et irreguliers, et comportent de nombreuses marques de deformation intragranulaire (macles, lignes de glissement), accompagnees de fortes sous-structures. En plus, le spectre de la dimension des grains s'etend de quelques microns a quelques millimetres, selon les plages micrographiques examinees. Sous irradiation a ces temperatures, l'uranium metallique pur en barreaux cylindriques de diametre de l'ordre du pouce, se deforme: il se produit des fissures dans la masse, des variations de dimensions longitudinales et transversales (qui se traduisent par des peaux d'orange), soit par croissances plus ou moins directionnelles, soit par deformations superficielles qui peuvent provoquer des ruptures du materiau, de sa gaine ou des fleches suffisamment importantes pour obstruer les canaux de refroidissement. Il a ete reconnu par la suite que cette instabilite, sous l'effet des contraintes thermiques d'origine nucleaire, est due a la morphologie heterogene de l'uranium et a sa structure cristalline anisotrope (U{sub {alpha}} ou U{sub {beta}}). (auteur)

  20. Validity of the electrical model representation of the effects of nuclear magnetic resonance (1961); Validite de la representation par modele electrique des effets de resonance magnetique nucleaire (1961)

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-07-01

    When studying the behaviour of a magnetic resonance transducer formed by the association of an electrical network and of a set of nuclear spins, it is possible to bring about a representation that is analytically equivalent by means of an entirely electrical model, available for transients as well as steady-state. A detailed study of the validity conditions justifies its use in most cases. Also proposed is a linearity criterion of Bloch's equations in transient state that is simply the prolongation of the well-known condition of non-saturation in the steady-state. (author) [French] L'etude du comportement d'un transducteur a resonance magnetique forme de l'association d'un reseau electrique et d'un ensemble de noyaux dotes de spin, montre qu'il est possible d'en deduire une representation analytiquement equivalente au moyen d'un modele entierement electrique utilisable pour un regime transitoire aussi bien que pour un regime permanent. Une etude detaillee des conditions de validite permet d'en justifier l'emploi dans la majorite des cas. On propose enfin un critere de linearite des equations de Bloch en regime transitoire, qui constitue un prolongement de la condition connue de non-saturation en regime stationnaire. (auteur)

  1. Atomic spectroscopy study of nuclear properties of francium and cesium isotopes; Etude par spectroscopie atomique de proprietes nucleaires d'isotopes de francium et de cesium

    Energy Technology Data Exchange (ETDEWEB)

    Coc, A

    1986-04-15

    This work is based on the study of cesium ({sup 118,146}Cs) and francium ({sup 207-213}Fr,{sup 220-228}Fr) isotopes by hyperfine atomic spectroscopy and on the interpretation of these results from the nuclear physics point of view. The measured nuclear quantities are: the spin, the magnetic moment, the electric quadrupole moment and the mean square charge radius. The experimental method which is based on hyperfine optical pumping with a tunable laser, followed by magnetic analysis of the atoms is described in the first part. Results related to atomic physics are also presented. In the second part, these data are interpreted in the framework of nuclear models. The deformation of light cesium isomers are compared to values obtained from a theoretical self-consistent calculation. Heavy francium isotopes are situated in an area where the existence of static octupole deformations have been predicted. The odd-even staggering measured on the mean square radius is abnormal in this region. However, on the basis of experimental data, no definitive conclusion can be drawn regarding the nature of these deformations. (author)

  2. Progressive supranuclear palsy dopamine D2 receptor tomoscintigraphy to detect L-dopamine efficiency. Paralysies supra-nucleaires progressives. Quantification des recepteurs dopaminergiques D2 par tomoscintigraphie

    Energy Technology Data Exchange (ETDEWEB)

    Tranquart, F; Henry Le Bras, F; Toffol, B de; Autret, A; Guilloteau, D; Baulieu, J L [Hopital Bretonneau, 37 - Tours (France)

    1994-09-01

    Progressive supranuclear palsy (PSP) may sometimes be misdiagnosed as Parkinson's disease in its early stages, hence an early positive diagnosis of PSP based on dopamine D2 receptor density could be extremely valuable. In the present case report, the absence of dopamine D2 receptors was clearly demonstrated in the striatum using [sup 123]I-iodobenzamide (IBZM) tomoscintigraphy. This illustrates the potential use of IBZM tomoscintigraphy to identify Parkinson-like's disease presenting with decreased dopamine D2 receptor density; and hence to predict L-Dopa effectiveness. Further studies are needed to evaluate the value of IBZM tomoscintigraphy in the different Parkinson's like diseases. (authors). 11 refs., 2 figs.

  3. Atomic spectroscopy study of nuclear properties of francium and cesium isotopes; Etude par spectroscopie atomique de proprietes nucleaires d'isotopes de francium et de cesium

    Energy Technology Data Exchange (ETDEWEB)

    Coc, A

    1986-04-15

    This work is based on the study of cesium ({sup 118,146}Cs) and francium ({sup 207-213}Fr,{sup 220-228}Fr) isotopes by hyperfine atomic spectroscopy and on the interpretation of these results from the nuclear physics point of view. The measured nuclear quantities are: the spin, the magnetic moment, the electric quadrupole moment and the mean square charge radius. The experimental method which is based on hyperfine optical pumping with a tunable laser, followed by magnetic analysis of the atoms is described in the first part. Results related to atomic physics are also presented. In the second part, these data are interpreted in the framework of nuclear models. The deformation of light cesium isomers are compared to values obtained from a theoretical self-consistent calculation. Heavy francium isotopes are situated in an area where the existence of static octupole deformations have been predicted. The odd-even staggering measured on the mean square radius is abnormal in this region. However, on the basis of experimental data, no definitive conclusion can be drawn regarding the nature of these deformations. (author)

  4. The sea water desalination by the nuclear reactors; Le dessalement de l'eau de mer par les reacteurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Nisan, S. [CEA Cadarache, Dir. du Developpement et de l' Innovation Nucleares DDIN, 13 - Saint-Paul-lez-Durance (France)

    2002-07-01

    This document underlines the importance of water shortage in many areas in the world in the future. The water sea desalination can be a efficient solution to this problem. The desalination methods are presented. In this context the desalination reactors appear as a competitive solution, facing the fossil energies systems not only for the simultaneous electric power and drinking water production, but also for the minimization of greenhouse gases. (A.L.B.)

  5. Perception of the nuclear industry by general practitioner in Champagne-Ardennes (France); Perception du nucleaire par le medecin generaliste en region Champagne-Ardenne

    Energy Technology Data Exchange (ETDEWEB)

    Bouet, P; Goasguen, P; Lewicki, M; Petit, J F; Villette, M

    1990-06-01

    In the case of a nuclear accident, the general practitioners should be the relay in the population information. In order to confront their knowledge and sensitivity with the nuclear industry problems, the authors have conducted an inquiry near to 144 general practitioners in Champagne-Ardennes area, in the immediate neighbourhood of nuclear facilities (CHOOZ, Nogent-sur-Seine, Gravelines) or not. Four subjects are studied: -their perception of the nuclear industry in the environment problems - their knowledge in nuclear physics - their knowledge about the nuclear power plant - their attitude in front of a radiation accident. The authors show that their education and knowledges about the nuclear industry is insufficient and propose several solutions in order to cope with these difficulties.

  6. Preparation and study of the properties of lead telluride and cadmium telluride diodes for use in nuclear spectrometry; Preparation et etude des proprietes de diodes au tellurure de plomb et au tellurure de cadmium en vue d'une utilisation en spectrometrie nucleaire

    Energy Technology Data Exchange (ETDEWEB)

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

    1969-07-01

    resistivite de notre materiau nous empeche de l'utiliser en detection de rayonnements nucleaires. Differents types de structures a base de CdTe ont ete etudiees. L'une des diodes realisees a permis la detection de particules alpha. Les performances limitees de ce detecteur sont expliquees par la presence dans CdTe de defauts de reseau jouant le role de centres de recombinaison des porteurs de charge. L'analyse des proprietes de diodes realisees par diffusion d'or dans CdTe a permis d'identifier ce defaut, la lacune de cadmium, dont la presence est due a un ecart a la stoechiometrie lors de la preparation du materiau. (auteur)

  7. Development of a software for a multi-processor system aimed at the on-line control of nuclear physics experiments; Developpement de logiciel pour un systeme multiprocesseur destine au controle en ligne d'experiences de physique nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Poggioli, Jean Renaud

    1984-03-02

    This research thesis reports the development of a software for an acquisition computer aimed at the on-line control of nuclear physics experiments. An original architecture, based on the assignment of a processor to each fundamental task, enables the implementation of a high performance system. In order to make the user free of programming constraints, the author developed a software for dynamic generation of acquisition and processing codes. These codes are created from a data base which is programmed by the user by using a language close to the physical reality. Procedures of interactive control of the experiment are thus simplified by displaying function menus on the operator terminal. The author evokes possible hardware improvements and possible extensions of the system [French] Cette these rend compte du developpement logiciel realise pour un calculateur d'acquisition destine au controle en ligne d'experiences de Physique Nucleaire. Une architecture originale, basee sur l'attribution d'un processeur a chacune des taches fondamentales permet de facon simple la mise en oeuvre d'un systeme a hautes performances. Le souci de liberer l'utilisateur des contraintes de programmation a conduit a l'elaboration d'un logiciel de generation dynamique des codes acquisition et traitement; ces derniers sont crees a partir d'une base de donnees que l'experimentateur programme a l'aide d'un langage approchant la realite physique. Les procedures de controle interactif de l'experience se trouvent simplifiees par l'affichage de menus de fonctions sur la console operateur. En conclusion sont evoquees les ameliorations materielles et les extensions possibles du systeme. (auteur)

  8. Development of a power-period calculation unit for nuclear reactor Control; Etude et realisation d'un ensemble de calcul puissance periode pour le controle d'un reacteur nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Martin, J [Commissariat a l' Energie Atomique, Centre d' Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France)

    1966-10-01

    The apparatus studied is a digital calculating assembly which makes it possible to prepare and to present numerically the period and power of a nuclear reactor during operation, from start-up to nominal power. The pulses from a fission chamber are analyzed continuously, using real time. A small number of elements is required because of the systematic use of a calculation technique comprising the determination of a base 2 logarithm by a linear approximation. The accuracy obtained for the period is of the order of 14%; the response time of the order of the calculated period value. An approximate value of the power (30%) is given at each calculation cycle together with the power thresholds required for the control. (author) [French] L'appareil etudie est un ensemble de calcul digital permettant d'elaborer et d'afficher numeriquement la periode et la puissance, d'un reacteur nucleaire lors de son fonctionnement depuis le demarrage jusqu'a la puissance nominale. Il traite en temps reel, de facon continue, les impulsions en provenance d'une chambre de fission. Grace a l'utilisation systematique d'une technique de calcul, la determination d'un logarithme a base 2 par approximation lineaire, un nombre reduit d'elements est utilise. La precision obtenue sur la periode est de l'ordre de 14 pour cent, le temps de reponse de l'ordre de la valeur de la periode calculee. Un ordre de grandeur de la puissance (30 pour cent) est donne a chaque cycle de calcul ainsi que des seuils de puissance necessaires au controle. (auteur)

  9. C9.A/14 steelwork joints de poutres par plaque frontale : assemblages par gousset

    CERN Document Server

    2015-01-01

    Les Tables de résistances ultimes des assemblages boulonnés par plaque frontale et par gousset, complétées par une description des modèles de calcul et des exemples d’application, ont pour but de faciliter la tâche de l'ingénieur et du constructeur. Cette première partie C9.A/14 contient les chapitres suivants: - Joints de poutres par plaque frontale en acier S235 et S355 - Assemblages par gousset en acier S235 et S355 Les Tables contiennent des données relatives à la géométrie ainsi que les valeurs de calcul correspondantes des résistances ultimes des assemblages ; elles remplacent le chapitre « Assemblages par plaques frontales et boulons HR » des anciennes Tables C9.1 de 1983 / 2002. Le calcul de ces assemblages par plaque frontale est basé sur les hypothèses du modèle de la méthode des composants décrite dans la norme SN EN 1993-1-8. Les vérifications sont effectuées selon la norme SIA 263:2013. Les assemblages par gousset remplacent les assemblages par double cornière, (telle...

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

    Directory of Open Access Journals (Sweden)

    M.L BENMALEK

    2000-06-01

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

  11. Analytic catalog for the use of the nuclear physicists; Repertoire analytique a l'usage des physiciens nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Ballini, R.; Barloutaud, R.; Bernas, R.; Chaminade, R.; Cohen, R.; Conjeaud, M.; Cotton, E.; Faraggi, H.; Grjebine, T.; Laboulaye, H. de; Lehmann, P.; Leveque, A.; Levi, C.; Moreau, J.; Naggiar, V.; Olkowsky, J.; Papineau, L.; Papineau, L.; Prugne, P.; Schuhl, C.; Szteinsznaider, D.; Tzara, C.; Valladas, G. [Commissariat a l' Energie Atomique, Saclay(France). Centre d' Etudes Nucleaires; Marty, N.; Renard, G. [College de France, Lab. de Chimie Nucleaire (France)

    1952-07-01

    The problem of the documentation in nuclear physics becomes constantly more complex. Every week brings its share of publications, always more numerous and more varied. To remedy to this problem, we tried, at the Nuclear Physics Services of the CEA, to give to the documentation the character of a collective and systematized work. The present report covers the literature appeared between January 1, 1950 and July 1, 1951. (Volume 1: CEA report number 120; Volume 2: CEA report number 184). (M.B.) [French] Le probleme de la documentation en physique nucleaire devient sans cesse plus complexe. Chaque semaine apporte son lot de publications, toujours plus nombreuses et plus diversifiees. C'est pour essayer de porter remede a cet etat de choses que nous avons essaye, au service de Physique Nucleaire du C.E.A., de donner a la documentation le caractere d'un travail collectif systematise. Le present rapport couvre la litterature parue entre le 1 Janvier 1950 et le 1 Juillet 1951. (Tome 1: Rapport CEA numero 120; Tome 2: Rapport CEA numero 184). (M.B.)

  12. Analytic catalog for the use of the nuclear physicists; Repertoire analytique a l'usage des physiciens nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Ballini, R; Barloutaud, R; Bernas, R; Chaminade, R; Cohen, R; Conjeaud, M; Cotton, E; Faraggi, H; Grjebine, T; Laboulaye, H de; Lehmann, P; Leveque, A; Levi, C; Moreau, J; Naggiar, V; Olkowsky, J; Papineau, L; Papineau, L; Prugne, P; Schuhl, C; Szteinsznaider, D; Tzara, C; Valladas, G [Commissariat a l' Energie Atomique, Saclay(France). Centre d' Etudes Nucleaires; Marty, N; Renard, G [College de France, Lab. de Chimie Nucleaire (France)

    1952-07-01

    The problem of the documentation in nuclear physics becomes constantly more complex. Every week brings its share of publications, always more numerous and more varied. To remedy to this problem, we tried, at the Nuclear Physics Services of the CEA, to give to the documentation the character of a collective and systematized work. The present report covers the literature appeared between January 1, 1950 and July 1, 1951. (Volume 1: CEA report number 120; Volume 2: CEA report number 184). (M.B.) [French] Le probleme de la documentation en physique nucleaire devient sans cesse plus complexe. Chaque semaine apporte son lot de publications, toujours plus nombreuses et plus diversifiees. C'est pour essayer de porter remede a cet etat de choses que nous avons essaye, au service de Physique Nucleaire du C.E.A., de donner a la documentation le caractere d'un travail collectif systematise. Le present rapport couvre la litterature parue entre le 1 Janvier 1950 et le 1 Juillet 1951. (Tome 1: Rapport CEA numero 120; Tome 2: Rapport CEA numero 184). (M.B.)

  13. Protease-activated receptor (PAR)-2 is required for PAR-1 signalling in pulmonary fibrosis

    NARCIS (Netherlands)

    Lin, Cong; von der Thüsen, Jan; Daalhuisen, Joost; ten Brink, Marieke; Crestani, Bruno; van der Poll, Tom; Borensztajn, Keren; Spek, C. Arnold

    2015-01-01

    Idiopathic pulmonary fibrosis is the most devastating diffuse fibrosing lung disease of unknown aetiology. Compelling evidence suggests that both protease-activated receptor (PAR)-1 and PAR-2 participate in the development of pulmonary fibrosis. Previous studies have shown that bleomycin-induced

  14. General phenomenology of underground nuclear explosions; Phenomenologie generale des explosions nucleaires souterraines

    Energy Technology Data Exchange (ETDEWEB)

    Derlich, S; Supiot, F [Commissariat a l' Energie Atomique, Bruyeres-le-Chatel (France). Centre d' Etudes

    1969-07-01

    An essentially qualitatively description is given of the phenomena related to underground nuclear explosions (explosion of a single unit, of several units in line, and simultaneous explosions). In the first chapter are described the phenomena which are common to contained explosions and to explosions forming craters (formation and propagation of a shock-wave causing the vaporization, the fusion and the fracturing of the medium). The second chapter describes the phenomena related to contained explosions (formation of a cavity with a chimney). The third chapter is devoted to the phenomenology of test explosions which form a crater; it describes in particular the mechanism of formation and the different types of craters as a function of the depth of the explosion and of the nature of the ground. The aerial phenomena connected with explosions which form a crater: shock wave in the air and focussing at a large distance, and dust clouds, are also dealt with. (authors) [French] On donne une description essentiellement qualitative des phenomenes lies aux explosions nucleaires souterraines (explosion d'un seul engin, d'engins en ligne et explosions simultanees). Dans un premier chapitre sont decrits les phenomenes communs aux explosions contenues et aux explosions formant un cratere (formation et propagation d'une onde de choc provoquant la vaporisation, la fusion et la fracturation du milieu). Le deuxieme chapitre decrit les phenomenes lies aux tirs contenus (formation d'une cavite et d'une cheminee). Le troisieme chapitre est consacre a la phenomenologie des tirs formant un cratere et decrit notamment le mecanisme de formation et les differents types de crateres en fonction de la profondeur d'explosion et de la nature du terrain. Les phenomenes aeriens lies aux explosions formant un cratere: onde de pression aerienne et focalisation a grande distance, nuages de poussieres, sont egalement abordes. (auteurs)

  15. 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)

  16. The Technical Training Programme for Nuclear Power Station Personnel; Programme de formation technique du personnel des centrales nucleaires; Programma tekhnicheskoj podgotovki personala yadernoj ehlektrostantsii; El programa de formacion tecnica del personal de una central nucleoelectrica

    Energy Technology Data Exchange (ETDEWEB)

    Howey, G. R. [Hydro-Electric Power Commission of Ontario, Toronto, Ontario (Canada)

    1963-10-15

    .), responsible for maintenance of all mechanical equipment; and (5) Service maintainers: responsible for a wide variety of less skilled tasks requiring lower qualifications. In addition to these general categories a few specialists are required, such as chemists and radiation protection officers. Organization of the NPD staff and training for future nuclear-power needs will be discussed. (author) [French] La centrale nucleaire de demonstration canadienne (NPD), creee par un organisme federal, l'Atomic Energy of Canada Limited, est exploitee par une compagnie provinciale de distribution d'electricite, la Hydro-Electric Power Commission of Ontario, qui pourvoit aussi aux besoins en personnel. Le recrutement et la formation du personnel de la centrale ont ete difficiles du fait que, recemment encore, la plupart des besoins en electricite de l'Ontario pouvaient etre satisfaits par les abondantes ressources hydro-electriques de cette province. La multiplication des centrales thermiques, depuis 1950, a cree une enorme demande de personnel. Pour faire face a cette situation, on a organise la formation de personnel pour les centrales nucleaires de la maniere suivante: a) un groupe initial d'ingenieurs a ete selectionne parmi des specialistes ayant une vaste experience des travaux dans le domaine nucleaire de l 'exploitation des centrales thermiques et de la production d'electricite; b) on a selectionne un autre groupe d'operateurs et d'agents des services d'entretien hautement qualifies; c) ces groupes ont recu une formation systematique comprenant l'exploitation de centrales nucleaires et de centrales thermiques a charbon, un enseignement theorique et pratique et des instructions donnees par les specialistes qui ont concu les plans de NPD ; d) un centre de formation nucleaire a ete cree et charge de la selection et de la formation du personnel supplementaire ainsi que de l 'organisation des examens officiels; il doit s'assurer, d'une maniere generale, de la competence du personnel

  17. Synthesis and purification of some alkyl phenanthrenes and presentation of their infrared, ultraviolet, nuclear magnetic resonance and mass spectra; Synthese et purification de quelques alcoylphenanthrenes et presentation ds leurs spectres d'absorption infrarouge, ultraviolette, de resonance magnetique nucleaire et de masse

    Energy Technology Data Exchange (ETDEWEB)

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

    1965-01-01

    We have carried out the synthesis of: - phenanthrene - its five monomethyl derivatives - three dimethyl derivatives - two trimethyl derivatives. We have then purified these products as well as a certain number of others obtained from various sources. We have been able to obtain in the majority of cases, a purity of 99.5 per cent or over, these figures being obtained by low voltage mass spectrometry. Finally we have recorded the infrared, ultraviolet, nuclear magnetic resonance and mass spectra of these products for which an atlas has been drawn up. (author) [French] Nous avons realise la synthese: - du phenanthrene - de ses cinq derives monomethyles - de trois de ses derives dimethyles - de deux de ses derives trimethyles. Nous avons ensuite purifie ces produits ainsi qu'un certain nombre d'autres que nous avons obtenus de sources differentes. Nous avons pu atteindre, dans la plupart des cas, une purete egale ou superieure a 99,5 pour cent, chiffres determines par la spectrometrie de masse a basse tension. Enfin, nous avons enregistre les spectres infrarouges, ultraviolets, de resonance magnetique nucleaire et de masse de ces produits dont nous avons fait un atlas. (auteur)

  18. Re-enrichment of depleted uranium by passage through a gaseous diffusion installation; Reenrichissement de l'uranium appauvri par passage dans une installation de diffusion gazeuse

    Energy Technology Data Exchange (ETDEWEB)

    Lagrange, P; Billous, O [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    The reader will find in this paper an economic study of the re-utilization of depleted uranium from nuclear reactors, whether its content be above or under natural proportions. Re-utilization is possible either through bringing the depleted product up to its initial content of {sup 235}U by mixture with a richer concentrate, or else by passing it through a gaseous diffusion plant. The economic area of such re-utilization depends on a number of considerations. We give a general study of it, with reference to some typical gaseous diffusion facilities. (author)Fren. [French] Ce rapport examine au point de vue economique la reutilisation de l'uranium appauvri provenant des reacteurs nucleaires, qu'il soit indifferemment en dessus ou en dessous de la teneur naturelle. Cette reutilisation peut se faire soit en ramenant le produit a sa teneur initiale en isotope 235 par un melange convenable avec un concentre plus riche, soit en le faisant passer dans une usine de Diffusion Gazeuse. La zone de rentabilite de cette reutilisation depend de diverses conditions economiques. Elle est etudiee ci-dessous d'une maniere generale, puis en se referant a des installations-type de diffusion gazeuse. (auteur)

  19. ParA and ParB coordinate chromosome segregation with cell elongation and division during Streptomyces sporulation

    Science.gov (United States)

    Donczew, Magdalena; Mackiewicz, Paweł; Wróbel, Agnieszka; Flärdh, Klas; Zakrzewska-Czerwińska, Jolanta

    2016-01-01

    In unicellular bacteria, the ParA and ParB proteins segregate chromosomes and coordinate this process with cell division and chromosome replication. During sporulation of mycelial Streptomyces, ParA and ParB uniformly distribute multiple chromosomes along the filamentous sporogenic hyphal compartment, which then differentiates into a chain of unigenomic spores. However, chromosome segregation must be coordinated with cell elongation and multiple divisions. Here, we addressed the question of whether ParA and ParB are involved in the synchronization of cell-cycle processes during sporulation in Streptomyces. To answer this question, we used time-lapse microscopy, which allows the monitoring of growth and division of single sporogenic hyphae. We showed that sporogenic hyphae stop extending at the time of ParA accumulation and Z-ring formation. We demonstrated that both ParA and ParB affect the rate of hyphal extension. Additionally, we showed that ParA promotes the formation of massive nucleoprotein complexes by ParB. We also showed that FtsZ ring assembly is affected by the ParB protein and/or unsegregated DNA. Our results indicate the existence of a checkpoint between the extension and septation of sporogenic hyphae that involves the ParA and ParB proteins. PMID:27248800

  20. Contamination potentielle des aliments par des ...

    African Journals Online (AJOL)

    SARA Computers

    la notion de la pollution et de l'exposition aux PCBs, lorsque 77% n'ont pas conscience de cette situation de risque ... 2018). Quoique la contamination par les. PCBs soit de faible niveau, elle est ...... Université Paris-Est, Paris, France ; 183.

  1. A mathematical model for cost of maritime transport. Application to competitiveness of nuclear vessels; Modele mathematique du cout de transport maritime application a la competitivite du navire nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Dorval, C [Commissariat a l' Energie Atomique, 75 - Paris (France)

    1966-05-01

    In studying the competitiveness of a nuclear merchant vessel, economic assessments in terms of figures were discarded in favor of a simplified model, which gives a clearer idea of the mechanism of the comparison between alternative vessels and the particular influence of each parameter. An expression is formulated for the unit cost per ton carried over a given distance as a function of the variables (speed and deadweight tonnage) and is used to determine the optima for conventional and nuclear vessels. To represent the freight market involved in the optimization studies, and thus in the competitiveness computation, two cases are taken into account: the tonnage to be carried annually is limited, and the tonnage to be carried annually is not limited. In both cases the optima are calculated and compared for a conventional and a nuclear vessel. Competitiveness curves are plotted as a function of the ratios of nuclear and conventional fuel costs and nuclear and conventional marginal power costs. These curves express the limiting values of the above two ratios for which the transport costs of the nuclear and conventional vessels are equal. The competitiveness curves vary considerably according to the hypothesis adopted for the freight market and the limit of tonnage carried annually. (author) [French] Pour etudier la competitivite du navire marchand nucleaire, plutot que de nous livrer a des evaluations economiques chiffrees, discutables dans l'etat actuel des etudes, nous utilisons un modele simplifie permettant de mieux saisir le mecanisme de la comparaison des navires et l'influence particuliere de chaque parametre. Nous etablissons une expression du cout unitaire de la tonne transportee sur un parcours donne en fonction des variables vitesse et port en lourd. Et nous l'utilisons pour determiner les optima des navires classiques et nucleaires. Pour representer le marche du fret qui intervient dans les etudes d'optimisation, et donc dans la recherche de la

  2. Contribution to the study of thermal mixing between nuclear spin systems; Contribution a l'etude du melange thermique entre systemes de spins nucleaires

    Energy Technology Data Exchange (ETDEWEB)

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

    1967-02-15

    This work describes methods of dynamic nuclear polarization in solids based on the thermal mixing between nuclear spin systems. The description of the thermal mixing processes involves most of the fundamental aspects of the spin temperature theory. The experiments, conducted with paradichlorobenzene and para-dibromobenzene, yield a detailed confirmation of the theoretical predictions. (author) [French] Ce travail decrit des methodes de polarisation dynamique nucleaire dans les solides basees sur le melange thermique entre systemes de spins nucleaires. La description des processus de melange thermique met en jeu la plupart des aspects fondamentaux de la theorie de la temperature de spin. Les experiences, realisees avec du paradichlorobenzene et du paradibromobenzene, apportent une confirmation detaillee des previsions theoriques. (auteur)

  3. CFD analysis of PAR performance as function of inlet design

    Energy Technology Data Exchange (ETDEWEB)

    Park, Kweonha, E-mail: khpark@kmou.ac.kr [Division of Mechanical and Energy systems Engineering, Korea Maritime University, Dongsam-dong, Yeongdo-gu, Busan 606-791 (Korea, Republic of); Khor, Chong Lee, E-mail: itachi_829@hotmail.com [Department of Mechanical Engineering, Korea Maritime University (Korea, Republic of)

    2016-01-15

    Highlights: • The new concept of PAR (passive autocatalytic recombiner) was proposed and analyzed. • Guidance wall was added at the bottom of PAR to enhance the flow rate through the catalyst. • The new concept of PAR was proved to have a better hydrogen removal performance. - Abstract: Passive autocatalytic recombiner (PAR) is very useful hydrogen mitigation measurement. It is widely implemented in the current and advanced light water reactors (ALWRs). The design of the PARs should be optimized for the specific use under severe accident scenarios. Several techniques and innovations have been fused into the PAR, as an effort to increase its efficiency of hydrogen mitigation. This study proposes different concepts of PAR, which applied some changes to the honeycomb catalyst PAR made by the Korea Nuclear Technology (KNT) Inc. Two slices of plate are added to the bottom of PAR model, which intended to act as a reflection wall and promote the gas flow into PAR. Hydrogen volume fraction was given 4 vol. % which tested by KNT to investigate the performance of PAR in different direction gas flow conditions to see maximum hydrogen recombination rate. The new concept of PAR was proved to have a better hydrogen removal performance compared to the original honeycomb catalyst PAR.

  4. CFD analysis of PAR performance as function of inlet design

    International Nuclear Information System (INIS)

    Park, Kweonha; Khor, Chong Lee

    2016-01-01

    Highlights: • The new concept of PAR (passive autocatalytic recombiner) was proposed and analyzed. • Guidance wall was added at the bottom of PAR to enhance the flow rate through the catalyst. • The new concept of PAR was proved to have a better hydrogen removal performance. - Abstract: Passive autocatalytic recombiner (PAR) is very useful hydrogen mitigation measurement. It is widely implemented in the current and advanced light water reactors (ALWRs). The design of the PARs should be optimized for the specific use under severe accident scenarios. Several techniques and innovations have been fused into the PAR, as an effort to increase its efficiency of hydrogen mitigation. This study proposes different concepts of PAR, which applied some changes to the honeycomb catalyst PAR made by the Korea Nuclear Technology (KNT) Inc. Two slices of plate are added to the bottom of PAR model, which intended to act as a reflection wall and promote the gas flow into PAR. Hydrogen volume fraction was given 4 vol. % which tested by KNT to investigate the performance of PAR in different direction gas flow conditions to see maximum hydrogen recombination rate. The new concept of PAR was proved to have a better hydrogen removal performance compared to the original honeycomb catalyst PAR.

  5. The decommissioning of nuclear facilities; Le demantelement des installations nucleaires de base

    Energy Technology Data Exchange (ETDEWEB)

    Niel, J.Ch.; Rieu, J.; Lareynie, O.; Delrive, L.; Vallet, J.; Girard, A.; Duthe, M.; Lecomte, C.; Rozain, J.P.; Nokhamzon, J.G.; Davoust, M.; Eyraud, J.L.; Bernet, Ph.; Velon, M.; Gay, A.; Charles, Th.; Leschaeva, M.; Dutzer, M.; Maocec, Ch.; Gillet, G.; Brut, F.; Dieulot, M.; Thuillier, D.; Tournebize, F.; Fontaine, V.; Goursaud, V.; Birot, M.; Le Bourdonnec, Th.; Batandjieva, B.; Theis, St.; Walker, St.; Rosett, M.; Cameron, C.; Boyd, A.; Aguilar, M.; Brownell, H.; Manson, P.; Walthery, R.; Wan Laer, W.; Lewandowski, P.; Dorms, B.; Reusen, N.; Bardelay, J.; Damette, G.; Francois, P.; Eimer, M.; Tadjeddine, A.; Sene, M.; Sene, R

    2008-11-15

    ,; the fifth part presents the external points of view on dismantling with: the decommissioning of Saint-Laurent A, as seen by the local information committee, decommissioning: the urge for a public consultation, an evaluation of the work of the 'conseil superieur de la surete et de linformation nucleaire' (C.S.S.I.N.) - a consultative body dealing with information in the field of nuclear safety) on the issue of decommissioning basic nuclear installations, monitoring the decommissioning of nuclear facilities and examining applications. (N.C.)

  6. Statistical treatment of data. Application to nuclear electronics; Traitement des informations en regime statistique. Applications a l'electronique nucleaire

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

    In this report the data of probability calculations are applied to the analyses of counting losses in experiments on chance events encountered in nuclear physics. The distribution of time intervals according to Poisson's law is studied and various applications of this are given: calculation of counting losses on a scale preceded by a fast de-multiplying circuit, decrease of the counting rate on the multichannel selectors, recording of statistical distribution phenomena on magnetic bands. (author) [French] Ce rapport applique les donnees du calcul des probabilites a l'analyse des pertes de comptage dans les experiences sur des evenements aleatoires rencontres en physique nucleaire. La distribution des intervalles de temps suivant une loi de Poisson est etudiee et differentes applications en sont donnees: calcul des pertes de comptage sur une echelle precedee d'un circuit de demultiplication rapide, diminution du taux de comptage sur les selecteurs multicanaux, enregistrement de phenomenes a distribution statistique sur bandes magnetiques. (auteur)

  7. Economic consequences of the Swiss 'Sortir du nucleaire' and 'Moratoire-plus' popular initiatives - Analysis using a balanced model

    International Nuclear Information System (INIS)

    Mueller, A.; Wickart, M.; Van Nieuwkoop, R.

    2001-01-01

    This article is a short version of the ENET number 210359. This report for the Swiss Federal Office of Energy (SFOE) presents the results of a study made to assess the economic consequences of two models for the opting out of nuclear energy in Switzerland, as proposed in two popular initiatives. The 'Sortir du nucleaire' (electricity without atomic power) initiative calls for the shutting down of the existing nuclear power stations and the 'Moratoire-plus' initiative calls for a stop on the building of new atomic power stations for 10 years. The method used for assessing the costs and benefits resulting if the initiatives were accepted in a public vote is described. Basic assumptions made on further factors concerning the electricity and energy markets are discussed. Results of analyses made for various scenarios with respect to CO 2 emissions are presented and include discussions on risk costs, effects on employment and welfare aspects

  8. Dosimeter calibration facilities and methods at the Radiation Measurement Laboratory of the Centre d'etudes nucleaires, Grenoble

    International Nuclear Information System (INIS)

    Choudens, H. de; Herbaut, Y.; Haddad, A.; Giroux, J.; Rouillon, J.; CEA Centre d'Etudes Nucleaires de Grenoble, 38

    1975-01-01

    At the Centre d'etudes nucleaires, Grenoble, the Radiation Measurement Laboratory, which forms part of the Environmental Protection and Research Department, serves the entire Centre for purposes of dosimetry and the calibration of dose meters. The needs of radiation protection are such that one must have facilities for checking periodically the calibration of radiation-monitoring instruments and developing special dosimetry techniques. It was thought a good idea to arrange for the dosimetry and radiation protection team to assist other groups working at the Centre - in particular, the staff of the biology and radiobiology laboratories - and also bodies outside the framework of the French Commissariat a l'energie atomique. Thus, technical collaboration has been established with, for example, Grenoble's Centre hospitalier universitaire (university clinic), which makes use of the facilities and skills available at the Radiation Measurement Laboratory for solving special dosimetry problems. With the Laboratory's facilities it is possible to calibrate dose meters for gamma, beta and neutron measurements

  9. Wastes vitrification by plasma torch: study of a glass formulation compatible with a wide range of B wastes; Vitrification des dechets par torche a plasma: recherche d'une formulation de verre compatible avec un large eventail de dechets B

    Energy Technology Data Exchange (ETDEWEB)

    Poitou, S.; Richaud, D.; Fiquet, O.; Gramondi, P.; Massit, H. [CEA Cadarache, Dept. d' Entreposage et de Stockage des Dechets, 13 - Saint-Paul-lez-Durance (France)

    2001-07-01

    Within the context of radioactive waste management, CEA has equipped itself with a 'PLASMARC' device. The central element of this device is a plasma torch treatment furnace. It has been implemented and validated for the vitrification of low level radioactive wastes. Meanwhile, the plasma torch presents potentially interests for immobilizing under an inert form in vitreous matrices, B wastes which are generally divided and of complex chemical composition. The application of this process to this type of wastes has been studied here. The obtained results show that with the plasma torch it is possible to make glasses with a high amount of silicon and aluminium oxide and which are adapted to the treatment / packaging of the B wastes. (O.M.)

  10. SAFARI 2000 PAR Measurements, Kalahari Transect, Botswana, Wet Season 2000

    Data.gov (United States)

    National Aeronautics and Space Administration — Ceptometer data from a Decagon AccuPAR (Model PAR-80) were collected at four sites in Botswana during the SAFARI 2000 Kalahari Transect Wet Season Campaign (March,...

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

    OpenAIRE

    Morisot, Alain; Tournier, Jean Paul

    1986-01-01

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

  12. Detection of burst cans in the reactors cooled by gaseous phase; Detection des ruptures de gaine dans les reacteurs refroidis par phase gazeuse

    Energy Technology Data Exchange (ETDEWEB)

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

    1955-07-01

    In a nuclear reactor including the bars or plates cooled by a gaseous fluid, burst risks to occur in the sheath assuring the tightness separation between the cooling gas and the fissile materials. It is necessary to be able to detect the formation of these cracks as possible in order to avoid all risk of fission products release or any reaction of uranium to the contact of the refrigerating gas. It is however the increase of the radioactivity in the cooling gas due to the scattering of the fission products that permits to signal the apparition of a crack or to follow its evolution. It is possible to detect cracks of the order of the square millimeter. In this report, we will detail the principle and the realization of a device used for the surveillance of a natural uranium reactor cooled by air circulation. (M.B.) [French] Dans un reacteur nucleaire comportant des barres ou des plaques refroidies par un fluide gazeux des fissures risquent de se produire dans les gaines assurant la separation etanche entre le gaz de refroidissement et les materiaux fissiles. II est necessaire de pouvoir detecter la formation de ces fissures des que possible afin d'eviter tout risque de liberation de produits de fission ou de reaction de l'uranium au contact du gaz refrigerant. C'est cependant l'augmentation de la radioactivite du gaz de refroidissement due a la dispersion des produits de fission qui permet de signaler l'apparition d'une fissure ou de suivre son evolution. On peut ainsi detecter des fissures de l'ordre du millimetre carre. Dans ce rapport, nous detaillerons le principe et la realisation d'un appareil utilise pour la surveillance d'un reacteur a uranium naturel refroidi par circulation d'air. (M.B.)

  13. Protection of uranium by electrodeposition of nickel and diffusion; Protection de l'uranium par nickelage electrolytique et diffusion

    Energy Technology Data Exchange (ETDEWEB)

    Chauvin, G; Coriou, H; Hure, J [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1959-07-01

    diffusion, that which is richest in nickel UNi{sub 5}, is the hardest and most brittle. This brittleness results in the systematic appearance of fractures at the Ni-UNi{sub 5} interface; all the diffusion layers remain fixed to the uranium. (author) [French] Ce travail s'integre dans le cadre tres general du probleme de gainage de l'uranium dans les reacteurs nucleaires. En effet il convient notamment: - D'assurer une protection du combustible (uranium) contre la corrosion par le refrigerant (eau lourde, CO, etc.) dans le cas d'une rupture de gaine (Al, Zr, etc.); - D'eviter la diffusion prohibitive U-Al (cas d'une gaine en aluminium) par l'emploi d'une couche intermediaire d'un metal dont la cinetique de diffusion avec l'uranium soit, dans les memes conditions, considerablement plus faible que celle de l'aluminium. De la presente etude, basee sur l'utilisation eventuelle du nickel comme couche intermediaire, on peut degager les principaux points suivants: 1) Apres lui avoir fait subir un traitement de surface chimique determine, on peut realiser sur l'uranium des depots electrolytiques de nickel d'une adherence telle que, apres un recuit sans l'application d'aucune pression, ces depots donnent lieu a une bonne diffusion intermetallique U-Ni. Tout en restant tres inferieure a celle du systeme U-Al, cette diffusion permet de renforcer la protection, donc d'accroitre la resistance du combustible a la corrosion. 2) Toutes autres conditions egales par ailleurs, l'experience montre que la qualite des zones de diffusion obtenues depend de la nature du bain de nickelage. 3) Les bains classiques de nickelage utilises jusqu'a present dans ce domaine d'etude contiennent 20 a 40 g/l d'acide borique a titre de tampon electrolytique. Il en resulte une contamination extremement elevee des depots de nickel par 400 a 500 ppm de bore. Nous montrons qu'avec au moins un bain exempt de poisons nucleaires, on peut obtenir des zones de diffusion U-Ni tres saines. 4) Apres un recuit de 100 heures

  14. Some magnetic resonance properties of solutions of sodium in liquid ammonia; Contribution a l'etude des solutions de sodium dans l'ammoniac liquide par resonance magnetique

    Energy Technology Data Exchange (ETDEWEB)

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

    1968-02-01

    Dilute solutions of sodium in liquid ammonia are studied by the mean of dynamic polarization techniques, and with the aid of Becker Lindquist and Alder model. Paramagnetic shifts are computed as a function of the 'average spin density', for each of the nuclear spin system. The nuclear contributions to the Overhauser shift are computed in the same way. A theoretical study of the main relaxation processes is carried out for each of the nuclear spin system and for the electronic spin system. The dynamic polarization experiments consist in classical measurement of the Overhauser enhancement for nitrogen, and in direct measurements of nitrogen Knight shift and nuclear contributions to the Overhauser shift by the mean of double irradiation techniques. The results show that, in dilute solutions, the relaxation of nitrogen arises from quadrupole interaction and from hyperfine interaction with unpaired electrons. Both interactions are of the same order of magnitude. Overhauser shift measurements show that the spin density is negative at the proton site, in agreement with Hughes results. (author) [French] Les solutions diluees de sodium dans l'ammoniac sont etudiees au moyen des techniques de la polarisation dynamique, sur la base du modele de Becker Lindquist et Aider. Les deplacements paramagnetiques des raies de resonance nucleaire des differents noyaux sont analyses en faisant appel a la notion de ''densite moyenne de spin'' introduite par l'auteur; et les differentes contributions nucleaires au deplacement d'Overhauser sont calculees en fonction de cette meme grandeur. Une etude theorique de la relaxation de chaque systeme de spin permet d'evaluer l'importance relative des differents mecanismes mis en jeu. Les experiences de polarisation dynamique effectuees au cours de ce travail consistent en mesures classiques de l'effet Overhauser sur l'azote, d'une part, et en la mise en oeuvre de techniques originales pour mesurer le deplacement de Knight de l'azote et les

  15. Plasma suPAR is lowered by smoking cessation

    DEFF Research Database (Denmark)

    Eugen-Olsen, Jesper; Ladelund, Steen; Sørensen, Lars Tue

    2016-01-01

    BACKGROUND: Soluble urokinase plasminogen activator receptor (suPAR) is a stable inflammatory biomarker. In patients, suPAR is a marker of disease presence, severity and prognosis. In the general population, suPAR is predictive of disease development, such as diabetes and cardiovascular disease a...

  16. Copenhagen uPAR prostate cancer (CuPCa) database

    DEFF Research Database (Denmark)

    Lippert, Solvej; Berg, Kasper D; Høyer-Hansen, Gunilla

    2016-01-01

    AIM: Urokinase plasminogen activator receptor (uPAR) plays a central role during cancer invasion by facilitating pericellular proteolysis. We initiated the prospective 'Copenhagen uPAR Prostate Cancer' study to investigate the significance of uPAR levels in prostate cancer (PCa) patients. METHODS...

  17. The inflammatory marker suPAR after cardiac arrest

    DEFF Research Database (Denmark)

    Rundgren, Malin; Lyngbaek, Stig; Fisker, Helle

    2015-01-01

    . This pilot study aimed at investigating suPAR levels in relation to outcome after CA and mild induced hypothermia. METHODS: suPAR levels were measured at 6, 36, and 72 hours in patients treated with hypothermia after CA. suPAR levels were analyzed in relation to survival after 6 months. Receiver operating...

  18. Experimental contamination of margaritana margaritifera (L) (a Fresh water bivalve) by caesium 137; Contamination experimentale de margaritana margaritifera (L) (bivalve d'eau douce) par le cesium 137

    Energy Technology Data Exchange (ETDEWEB)

    Foulquier, L; Bovard, P; Grauby, A [Commissariat a l' Energie Atomique, Cadarache (France). Centre d' Etudes Nucleaires

    1966-07-01

    The hydro biological research carried out in the Radio-Ecology Section has led the authors to study some Margaritana sampling stations situated down-stream from the Monts d'Arree nuclear power station. They describe the preservation and contamination methods used for fixing the {sup 137}Cs concentration factors in the case of Margaritana Margaritifera (L). The results of experiments carried out over a period of one hundred days show that the specific activity of the various organs is stabilized after thirty to thirty-five days. The authors have noticed a relatively low adsorption on the shell through the intermediary of micro-organisms, and a strong and rapid absorption in the soft parts. The concentration factors have values, at equilibrium, of around: 9 for the shell, 300 for all the organs, and 38 for the whole animal. A comparison of these results with work published by other authors makes it possible to draw general conclusions concerning the mechanism of {sup 137}Cs fixation by lamellibranch, as well as their capacity of fixation. (author) [French] Les etudes hydrobiologiques effectuees au sein de la Section de Radio-Ecologie ont amene les auteurs a etudier des stations de prelevement de Margaritana en aval de la Centrale Nucleaire des Monts d'Arree. Ils decrivent les methodes de conservation et de contamination utilisees pour l'etablissement des facteurs de concentration du {sup 137}Cs par Margaritana margaritifera (L). Les resultats des experimentations menees pendant cent jours montrent que les activites specifiques de la coquille et des differents organes se stabilisent au bout de trente a trente-cinq jours. Les auteurs constatent une adsorption relativement faible sur la coquille par l'intermediaire des micro-organismes et une absorption forte et rapide dans les parties molles. Les facteurs de concentration se situent, a l'equilibre, autour de: 9 pour la coquille, 300 pour l'ensemble des organes et 38 si l'on considere l'animal total. Cette etude

  19. Phosphorylation of Mycobacterium tuberculosis ParB participates in regulating the ParABS chromosome segregation system.

    Science.gov (United States)

    Baronian, Grégory; Ginda, Katarzyna; Berry, Laurence; Cohen-Gonsaud, Martin; Zakrzewska-Czerwińska, Jolanta; Jakimowicz, Dagmara; Molle, Virginie

    2015-01-01

    Here, we present for the first time that Mycobacterium tuberculosis ParB is phosphorylated by several mycobacterial Ser/Thr protein kinases in vitro. ParB and ParA are the key components of bacterial chromosome segregation apparatus. ParB is a cytosolic conserved protein that binds specifically to centromere-like DNA parS sequences and interacts with ParA, a weak ATPase required for its proper localization. Mass spectrometry identified the presence of ten phosphate groups, thus indicating that ParB is phosphorylated on eight threonines, Thr32, Thr41, Thr53, Thr110, Thr195, and Thr254, Thr300, Thr303 as well as on two serines, Ser5 and Ser239. The phosphorylation sites were further substituted either by alanine to prevent phosphorylation or aspartate to mimic constitutive phosphorylation. Electrophoretic mobility shift assays revealed a drastic inhibition of DNA-binding by ParB phosphomimetic mutant compared to wild type. In addition, bacterial two-hybrid experiments showed a loss of ParA-ParB interaction with the phosphomimetic mutant, indicating that phosphorylation is regulating the recruitment of the partitioning complex. Moreover, fluorescence microscopy experiments performed in the surrogate Mycobacterium smegmatis ΔparB strain revealed that in contrast to wild type Mtb ParB, which formed subpolar foci similar to M. smegmatis ParB, phoshomimetic Mtb ParB was delocalized. Thus, our findings highlight a novel regulatory role of the different isoforms of ParB representing a molecular switch in localization and functioning of partitioning protein in Mycobacterium tuberculosis.

  20. Phosphorylation of Mycobacterium tuberculosis ParB participates in regulating the ParABS chromosome segregation system.

    Directory of Open Access Journals (Sweden)

    Grégory Baronian

    Full Text Available Here, we present for the first time that Mycobacterium tuberculosis ParB is phosphorylated by several mycobacterial Ser/Thr protein kinases in vitro. ParB and ParA are the key components of bacterial chromosome segregation apparatus. ParB is a cytosolic conserved protein that binds specifically to centromere-like DNA parS sequences and interacts with ParA, a weak ATPase required for its proper localization. Mass spectrometry identified the presence of ten phosphate groups, thus indicating that ParB is phosphorylated on eight threonines, Thr32, Thr41, Thr53, Thr110, Thr195, and Thr254, Thr300, Thr303 as well as on two serines, Ser5 and Ser239. The phosphorylation sites were further substituted either by alanine to prevent phosphorylation or aspartate to mimic constitutive phosphorylation. Electrophoretic mobility shift assays revealed a drastic inhibition of DNA-binding by ParB phosphomimetic mutant compared to wild type. In addition, bacterial two-hybrid experiments showed a loss of ParA-ParB interaction with the phosphomimetic mutant, indicating that phosphorylation is regulating the recruitment of the partitioning complex. Moreover, fluorescence microscopy experiments performed in the surrogate Mycobacterium smegmatis ΔparB strain revealed that in contrast to wild type Mtb ParB, which formed subpolar foci similar to M. smegmatis ParB, phoshomimetic Mtb ParB was delocalized. Thus, our findings highlight a novel regulatory role of the different isoforms of ParB representing a molecular switch in localization and functioning of partitioning protein in Mycobacterium tuberculosis.

  1. Effect of cobalt-60 {gamma} radiation and of thermal neutrons on high resistance P and N silicon. Possibility of obtaining a nuclear compensation for P type silicon; Effects du rayonnement {gamma} du cobalt 60 et de neutrons thermiques sur du silicium P et N de haute resistivite. Possibilite de realiser une compensation nucleaire d'un silicium du type P

    Energy Technology Data Exchange (ETDEWEB)

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

    1965-11-01

    Type P silicon has been compensated by the production of a controlled and uniform amount of donor atoms ({sup 31}P) using thermal neutrons to bring about a nuclear transformation. It is shown that it is possible in this way to reduce by a factor of about one hundred the overall concentration of residual ionised impurities in the purest crystals obtained by floating zone purification (2 x 10{sup 12} atoms/cm{sup 3}). The degree compensation obtained is limited by the initial inhomogeneity of acceptor impurities which have to be compensated. Lattice defects which still remain after prolonged annealings reduce the life-time of the material to about 10 {mu}s approximately. Particle detectors having thicknesses of 2 to 5 mm have been built by this process; they give good results, particularly at low temperatures. A study has also been made of the number and of the nature of lattice defects produced by thermal neutrons in high resistivity P and N type crystals. These defects have been compared to those produced by {gamma} rays from {sup 60}Co. A discussion is given of the validity of the Wertheim model concerning pronounced recombination at low temperatures (77 deg. K - 300 deg. K) of primary defect-interstitial pairs. The nature of the defects introducing energy levels into the lower half of the forbidden band has been studied. (author) [French] On a compense du silicium de type P en produisant, au moyen de neutrons thermiques, par transmutation nucleaire une quantite controlee et uniforme d'atomes donneurs ({sup 31}P). On montre qu'on peut ainsi reduire de cent fois environ la densite nette d'impuretes ionisees residuelles subsistant dans les cristaux les plus purs obtenus par purification par zone flottante (2.10{sup 12} atomes/cm{sup 3}). Le degre de compensation obtenu est limite par i'inhomogeneite initiale des impuretes acceptrices a compenser. Des defauts de reseau qui subsistent meme apres des recuits prolonges reduisent la duree de vie du materiau a 10 {mu

  2. [Ambroise Paré in French literature].

    Science.gov (United States)

    Dumaitre, P

    1995-01-01

    The 16th century by its passionate side has been the favourite one of authors of historical novels in which among the heroes of "cloak and dagger stories" appears sometime Ambroise Paré. Alexandre Dumas (the father) has shown him at the court of Charles IX in La Reine Margot (1845) where he does not however play a great role. On the contrary, Balzac in Le Martyr calviniste (1842) has given him a capital part close to the dying François II, whom he intended to trepanize but had to give up this idea as a consequence of the opposition of the queen-mother Catherine de Médicis. In the present century, Robert Merle in Paris ma bonne ville (Fortune de France, 3, 1980) shows Paré at the time of the Saint Barthélemy.

  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. Par Pond refill water quality sampling

    International Nuclear Information System (INIS)

    Koch, J.W. II; Martin, F.D.; Westbury, H.M.

    1996-08-01

    This study was designed to document anoxia and its cause in the event that the anoxia caused a fish kill. However, no fish kill was observed during this study, and dissolved oxygen and nutrient concentrations generally remained within the range expected for southeastern reservoirs. Par Pond water quality monitoring will continue during the second summer after refill as the aquatic macrophytes become reestablished and nutrients in the sediments are released to the water column

  5. Energetic conversion (biogas) of used edible oils by means of co-digestion together with various waste materials from the food industry; Valorisation energetique (biogaz) d'huiles comestibles usagees par codigestion avec differents dechets d'origine agroalimentaire

    Energy Technology Data Exchange (ETDEWEB)

    Membrez, Y; Fruteau de Laclos, H

    2002-07-01

    The aim of this project was the valorisation of used edible oils by co-digestion together with agricultural or food waste, without any risk for human and animal health. It included the technical economical aspects. In the bibliographic part a state-of-the-art on fat digestion in Switzerland and Europe was done. The possible co-substrates were examined, under a biological aspect as well as economical and strategic aspects. Food waste from restaurants and canteens, that are used up to now for pig feeding, were retained. The co-digestion gives a new perspective for the valorisation of this kind of waste, whose traditional way of valorisation is compromised by the new EU directives. The experimental part aimed to define the possibilities and limits for the co-digestion of used edible oil with food waste as co-substrate. The study was done in a 690 litres bio-reactor. The results showed that co-digestion of edible oil with food waste is feasible with interesting performances, if oil doesn't account for more than 15% of the mixture (on dry matter). Biogas production amounted to 400-450 litres per kg input COD (chemical oxygen demand), with 60-65% CH{sub 4}. Based on the observed results a tender document was done, in order to consult manufacturers of co-digestion plants. An economical simulation was realised on the basis of the most complete offer. This simulation revealed that a benefit of CHF 3500 per year can be obtained for a plant processing 200 t/y edible oil and 9000 t/y food waste. Co-digestion allows for valorisation of edible oil, together with a co-substrate whose traditional utilisation will not be possible in the future. It leads to the production of renewable energy, with a positive economical balance. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2003-02-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Bourbon, X.

    1994-12-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-09-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Barthelemy, B

    2003-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Barthelemy, B

    2003-06-01

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

  11. 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.)

  12. State of knowledge on the water radiolysis in cemented wasteforms and its approach by simulation; Etat des connaissances sur la radiolyse de l'eau dans les colis de dechets cimentes et son approche par simulation

    Energy Technology Data Exchange (ETDEWEB)

    Bouniol, P

    2004-07-01

    The decomposition of water under radiation within the cementitious matrix is at the origin of a potential source of harmful effects in the wasteform and their environment (pressurization and emanation of di-hydrogen) which can have an impact on the safety. In the aim of a better evaluation of the 'H{sub 2}' risk induced by such a complex and heterogeneous system, this document is an analysis of the elements necessary for a global understanding of the radiolysis in the cemented wasteform to be achieved: - summary of the basic knowledge on water radiolysis with transposition to the cementitious medium, - critical review of the various phenomenologies at work in a wasteform (radioactive source-term, gas transport, mineral equilibria); description of their mutual couplings and of their feedback on radiolytic chemistry; identification of the determining parameters, - presentation of a selection of experimental facts putting in light some theoretical points, - presentation of an outline of operational model deriving from the global vision; presentation of an adapted tool for simulation (CHEMSIMUL) and study of the influence of the principal parameters, starting from a reference case. The main result of this work is that it is shown, in the case of a {beta}{gamma} source term, that the control of the pore fluid composition by calcium octo-hydrate peroxide constitutes an efficient regulating mechanism for the radiolysis and H{sub 2} production. Not likely possible in the case of an {alpha} source term, this suggests a separate management of the wasteform according to their radiological contents. The gaps and limits of the model which are also evoked are promising of a lot of research prospects, primarily of a fundamental nature (impact of the porous medium). (author)

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

    Energy Technology Data Exchange (ETDEWEB)

    Zokimila, P

    2005-10-15

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

  14. Centromere pairing by a plasmid-encoded type I ParB protein

    DEFF Research Database (Denmark)

    Ringgaard, Simon; Löwe, Jan; Gerdes, Kenn

    2007-01-01

    The par2 locus of Escherichia coli plasmid pB171 encodes two trans-acting proteins, ParA and ParB, and two cis-acting sites, parC1 and parC2, to which ParB binds cooperatively. ParA is related to MinD and oscillates in helical structures and thereby positions ParB/parC-carrying plasmids regularly......, hence identifying the N terminus of ParB as a requirement for ParB-mediated centromere pairing. These observations suggest that centromere pairing is an important intermediate step in plasmid partitioning mediated by the common type I loci....

  15. Contribution to the experimental survey of the nuclear isomerism. Application of the deferred coincidences method to research and to the survey of metastable states of short period; Contribution a l'etude experimentale de l'isomerie nucleaire. Application de la methode des coincidences differees a la recherche et a l'etude d'etats metastables de periode courte

    Energy Technology Data Exchange (ETDEWEB)

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

    1953-06-15

    Various methods of the physics brought many informations on the nuclear elements which one can arrange some ponderable quantities, what is the case of the steady elements and some, unsteady elements, as most of natural radioelements. On the other hand, elements of shorter life duration, and notably those that are carried to an excited state, are more badly known, and one can get information to their consideration that by the mediator of the properties of the transitions that they undergo, when they give birth has best-known nuclear cash: among these transitions represent the isomeric transitions. The goal of this work is the survey of the isomeric transitions from metastable states of short period, included in the domain of the microsecond to some milliseconds. The method of the deferred coincidences has been put to the point and applied in this goal while using the advantages of the selectors to several channels, under two main aspects where the device to several channels was either a selector of time, either a selector of amplitudes. This method served to study the working of Geiger-Muller counter and to measure with precision the period of {sup 181}Ta{sup *} in of the varied experimental conditions. The adopted value is 17,2 {+-}0,2 {mu}s. This work also found an immediate practical application to the setting in evidence of very weak quantities of hafnium in zirconium, of which it constitutes a tenacious and difficult impurity to analyze by the ordinary ways. (M.B.) [French] Les diverses methodes de la physique ont apporte de nombreux renseignements sur les especes nucleaires dont on peut disposer en quantites ponderables, ce qui est le cas des especes stables et de certaines especes instables, comme la plupart des radioelements naturels. Par contre, les noyaux de duree de vie plus courte, et notamment ceux qui sont portes a un etat excite, sont plus mal connus, et on ne peut obtenir de renseignements a leur egard que par l'intermediaire des proprietes des

  16. Atomic Transport Problems of Interest in Nuclear Systems; Problemes de Transport Atomique Presentant un Interet dans les Systemes Nucleaires; Problemy perenosa atomov, predstavlyayushchie interes v yadernykh sistemakh; Problemas de Transporte Atomico de Interes para la Ingenieria Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Lundy, T. S.; Winslow, F. R. [Oak Ridge National Laboratory, TN (United States)

    1966-02-15

    ) [French] Les auteurs discutent plusieurs problemes qui surgissent lorsqu'on veut appliquer les constantes fondamentales de diffusion a des systemes presentant un interet pratique, notamment a ceux que l'on rencontre dans le genie nucleaire. Ces problemes comprennent des experiences de diffusion isotherme, la diffusion sous gradient thermique et les effets de rayonnements sur les processus de diffusion. La plupart des donnees dignes de foi sur la diffusion dans les solides ont ete obtenues a partir de cas dans lesquels il n'y avait essentiellement pas de gradient de concentration des especes diffusantes. Toutefois, dans les systemes qui presentent un interet pour les specialistes du genie nucleaire, il y a presque invariablement des gradients de concentration. C'est pourquoi il faut avoir une connaissance pratique de la relation entre les coefficients d'autodiffusion et de diffusion chimique pour pouvoir determiner les coefficients applicables dans chaque cas d'espece. En outre, il faut egalement connaitre les coefficients d'activite thermodynamique en fonction de la composition. Recemment, il a ete clairement demontre qu'il est dangereux d'utiliser aveuglement une expression d'Arrhenius pour decrire les variations de la diffusion selon la temperature, car cela peut entrainer des erreurs considerables dans le calcul theorique des coefficients de diffusion. Les auteurs discutent les consequences qui en decoulent, particulierement pour les systemes cubiques centres refractaires. Ils ont etudie, tant theoriquement qu'experimentalement, l'effet d'un gradient thermique sur la distribution des impuretes de substitution dans un metal. Ces travaux ont permis de mieux apprecier l'importance de cet effet dans des systemes presentant un interet du point de vue nucleaire. L'accroissement de la diffusion par les champs de rayonnements demeure toujours un probleme d'un interet reel. Les auteurs ont fait les premieres mesures directes de l'effet du bombardement par des particules rapides

  17. 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

  18. 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

  19. Childhood Pars Planitis; Clinical Features and Outcomes

    Directory of Open Access Journals (Sweden)

    Homayoon Nikkhah

    2011-01-01

    Full Text Available Purpose: To evaluate the demographic and clinical features of childhood pars planitis, and to determine the therapeutic and visual outcomes of the disease. Methods: Medical records of pediatric patients (less than 16 years of age at diagnosis with pars planitis and at least 6 months of follow-up who were referred to Labbafinejad Medical Center, Tehran, Iran over a 22 year period were reviewed. Results: Overall, 117 eyes of 61 patients including 51 (83.6% male subjects were included. Mean age at the time of diagnosis was 7.8΁3.2 (range, 3-16 years. Mean best corrected visual acuity (BCVA was 0.88΁0.76 logMAR at presentation which improved to 0.39΁0.51 logMAR at final visit (P<0.001. Endotheliitis was present in 23 (19.6% eyes and was significantly more prevalent in subjects younger than 9 years (P=0.025. Cataract formation (41.9% and cystoid macular edema (19.7% were the most prevalent complications. Univariate regression analysis showed that better baseline visual acuity (OR=0.38, 95%CI 0.21-0.70, P=0.002, age older than 5 years at disease onset (OR=0.36, 95%CI 0.14-0.9, P=0.029, absence of endotheliitis (OR=0.39, 95%CI 0.15-0.99, P=0.047 and female gender (OR=3.77, 95%CI 1.03-13.93, P=0.046 were significantly associated with final BCVA of 20/40 or better. Conclusion: Childhood pars planitis was much more common among male subjects. Endotheliitis may be a sign of inflammation spillover and is more prevalent in younger patients. Visual prognosis is favorable in most patients with appropriate treatment.

  20. Fluctuations in a system depending on several random parameters. Application to reactors (1962); Fluctuations d'un systeme dependant de plusieurs parametres aleatoires. Application aux reacteurs nucleaires (1962)

    Energy Technology Data Exchange (ETDEWEB)

    Blaquiere, A [Faculte des Sciences de Paris, 75 (France); Pachowska, R [Universite Technique de Varsovie (Poland)

    1962-07-01

    We have previously developed a method for studying neutronic fluctuations in nuclear reactors using the analogy between the behaviour of a reactor and that of certain common radioelectric circuits. The fluctuations may then be calculated by introducing into the circuit a suitable noise source. By this method we have been able to consider the overall fluctuations in a particularly simple form and we have provided a physical significance for certain results obtained more laboriously by other methods. The object of the present report is to generalise this method and in particular to extend it to the case of a reactor having a cellular structure and to apply it to fluctuations within a cell. It is thus shown that the fluctuations in a cell are the resultant of two terms: - a rapidly evolving Poissonian noise, not related to the overall fluctuations; - a slowly evolving noise, when the reactor is not too far from criticality, which is related to the overall fluctuations. The first term arises from a rapid 'ordering' of the system, during which time the cells come mutually into equilibrium. The second term is due to the coordinated evolution of all the cells, after the end of the first transitory phase. The conclusions reached show that it would be useful to complete the study with an analysis of non-linear phenomena which can considerably influence the transitory behaviour of the cells during the initial pre-equilibrium phase. This report also Stresses the relationship of the new method to the old methods. It tends also to place pile fluctuation theory in a more general framework, that of the fluctuations of a system depending on several random parameters; from this point of view, the method could easily be transposed and adapted to the study of other physical problems of this type. (authors) [French] Nous avons precedemment developpe une methode d'etude des fluctuations neutroniques des reacteurs nucleaires mettant a profit l'analogie entre le comportement d

  1. Contribution to the study of time-resolution in pulse electronics for nuclear physics: phase control circuits; Contribution a l'etude de la resolution en temps de l'electronique impulsionnelle pour physique nucleaire: les circuits de mise en phase

    Energy Technology Data Exchange (ETDEWEB)

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

    1969-07-01

    Phase control circuits make it possible to improve quite markedly the time resolution in pulse electronics. They replace a random pulse, of which the time of arrival with respect to a reference zero is being measured, by another pulse whose phase is well determined with respect to that, of a clock taken as reference. The time spectrum of the output, delayed, can always be situated inside channels of width {delta}T defined by the clock. The time statistics of the events analyzed is always correct even if the transition time for the circuits defining the channels represents a large fraction of {delta}T: the coding of the time becomes perfect, The phase control circuits, used in precision chronometry, are widely applied in Nuclear Physics since the lime spectra obtained are representative, indirectly, of certain values which are required to be measured with great accuracy. A description is given of: the constitution and operation of phase control circuits; a chain with automatic analysis and automatic reading, built for testing these circuits. Finally the measurement results are given. (author) [French] Les circuits de mise en phase permettent d'ameliorer notablement la resolution en temps de l'electronique impulsionnelle. Ils substituent a une impulsion aleatoire, dont on cherche a mesurer l'instant d'arrivee par rapport a un instant pris pour origine, une autre impulsion dont la phase est bien determinee par rapport a celle d'une horloge prise comme reference. Le spectre temporel de sortie, retarde, peut toujours etre situe a l'interieur des canaux de largeur {delta}T, definis par l'horloge. La statistique temporelle des evenements analyses est toujours correcte, meme si la duree de transition des circuits definissant les canaux represente une grande fraction de {delta}T: le codage de temps devient parfait. Les circuits de mise en phase, utilises en chronometrie fine, sont tres employes en Physique Nucleaire car les spectres temporels oblenus sont representatifs

  2. Accouchement par forceps: indications et pronostic materno-foetal ...

    African Journals Online (AJOL)

    L'accouchement par voie basse, peut être parfois compromis par des facteurs maternels, foetaux ou materno-foetaux nécessitant des moyens thérapeutiques comme le forceps pour achever l'accouchement par voie naturelle. Le forceps, une méthode qui n'est pas sans risque pour la mère et le nouveau-né. Nous avons ...

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

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

  4. Nuclear purity and the production of uranium (1962); La purete nucleaire et la fabrication de l'uranium (1962)

    Energy Technology Data Exchange (ETDEWEB)

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

    1962-07-01

    When the production of 'nuclear grade' uranium is dealt with, it is difficult, the author of this study points out, to separate its chemical, technical, and economical bearings. While recalling the evolution of chemical processes in various countries and describing the technic of uranium manufacture in the plant of the French 'Commissariat a l'Energie Atomique' at Le Bouchet, the author outlines the effect of economical contingencies on the problems the chemists and engineer are faced with. The question of cost price is also considered here with particular attention. (author) [French] Lorsqu'il s'agit de la production d'uranium de 'qualite nucleaire', il est difficile, souligne l'auteur de cette etude, de separer les aspects chimique, technique et economique. Aussi, en retracant l'evolution des procedes chimiques dans divers pays et decrivant les techniques de fabrication de l'uranium a l'usine du Bouchet du Commissariat a l'Energie Atomique, l'auteur ne manque-t-il pas de rappeler les incidences de la conjoncture economique sur les problemes posees au chimiste et a l'ingenieur. La question du prix de revient, egalement, est traitee ici avec une attention particuliere. (auteur)

  5. Public debate about the EPR nuclear power plant at Flamanville; Debat public sur la centrale nucleaire EPR a Flamanville

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    The project of building of he EPR reactor at Flamanville (Manche, France) has been submitted to the public debate. This document includes a presentation of the project and of the rules of the public debate, a synthesis of the file made by the prime contractor (EDF), a synthesis of the collective book of national actors concerned by the project (a group of associations for environment protection, Areva company, the ministries of economy and ecology, Global Chance, association of pro-nuclear ecologists (AEPN), 'Sortir du Nucleaire' (out-of nuclear) network, group of scientists for the information about nuclear (GSIEN), association for the promotion of the Flamanville site (Proflam), French nuclear energy society (SFEN) in association with 'Sauvons le Climat' (let's save climate), regional collective association 'EPR non merci, ni ailleurs, ni ici' (EPR, no thanks, neither elsewhere, nor here), NegaWatt), and 5 detailed books of actors: ACRO (association for the control of radioactivity in Western France), CFDT and CGT syndicates, the economic and social council of Basse Normandie region, and Proflam. (J.S.)

  6. Public debate about the EPR nuclear power plant at Flamanville; Debat public sur la centrale nucleaire EPR a Flamanville

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    The project of building of he EPR reactor at Flamanville (Manche, France) has been submitted to the public debate. This document includes a presentation of the project and of the rules of the public debate, a synthesis of the file made by the prime contractor (EDF), a synthesis of the collective book of national actors concerned by the project (a group of associations for environment protection, Areva company, the ministries of economy and ecology, Global Chance, association of pro-nuclear ecologists (AEPN), 'Sortir du Nucleaire' (out-of nuclear) network, group of scientists for the information about nuclear (GSIEN), association for the promotion of the Flamanville site (Proflam), French nuclear energy society (SFEN) in association with 'Sauvons le Climat' (let's save climate), regional collective association 'EPR non merci, ni ailleurs, ni ici' (EPR, no thanks, neither elsewhere, nor here), NegaWatt), and 5 detailed books of actors: ACRO (association for the control of radioactivity in Western France), CFDT and CGT syndicates, the economic and social council of Basse Normandie region, and Proflam. (J.S.)

  7. PAR1 activation affects the neurotrophic properties of Schwann cells.

    Science.gov (United States)

    Pompili, Elena; Fabrizi, Cinzia; Somma, Francesca; Correani, Virginia; Maras, Bruno; Schininà, Maria Eugenia; Ciraci, Viviana; Artico, Marco; Fornai, Francesco; Fumagalli, Lorenzo

    2017-03-01

    Protease-activated receptor-1 (PAR1) is the prototypic member of a family of four G-protein-coupled receptors that signal in response to extracellular proteases. In the peripheral nervous system, the expression and/or the role of PARs are still poorly investigated. High PAR1 mRNA expression was found in the rat dorsal root ganglia and the signal intensity of PAR1 mRNA increased in response to sciatic nerve transection. In the sciatic nerve, functional PAR1 receptor was reported at the level of non-compacted Schwann cell myelin microvilli of the nodes of Ranvier. Schwann cells are the principal population of glial cells of the peripheral nervous system which myelinate axons playing an important role during axonal regeneration and remyelination. The present study was undertaken in order to determine if the activation of PAR1 affects the neurotrophic properties of Schwann cells. Our results suggest that the stimulation of PAR1 could potentiate the Schwann cell ability to favour nerve regeneration. In fact, the conditioned medium obtained from Schwann cell cultures challenged with a specific PAR1 activating peptide (PAR1 AP) displays increased neuroprotective and neurotrophic properties with respect to the culture medium from untreated Schwann cells. The proteomic analysis of secreted proteins in untreated and PAR1 AP-treated Schwann cells allowed the identification of factors differentially expressed in the two samples. Some of them (such as macrophage migration inhibitory factor, matrix metalloproteinase-2, decorin, syndecan 4, complement C1r subcomponent, angiogenic factor with G patch and FHA domains 1) appear to be transcriptionally regulated after PAR1 AP treatment as shown by RT-PCR. Copyright © 2017 Elsevier Inc. All rights reserved.

  8. Taare Zameen Par and dyslexic savants.

    Science.gov (United States)

    Chakravarty, Ambar

    2009-04-01

    The film Taare Zameen Par (Stars upon the Ground) portrays the tormented life at school and at home of a child with dyslexia and his eventual success after his artistic talents are discovered by his art teacher at the boarding school. The film hints at a curious neurocognitive phenomenon of creativity in the midst of language disability, as exemplified in the lives of people like Leonardo da Vinci and Albert Einstein, both of whom demonstrated extraordinary creativity even though they were probably affected with developmental learning disorders. It has been hypothesized that a developmental delay in the dominant hemisphere most likely 'disinhibits' the nondominant parietal lobe, unmasking talents-artistic or otherwise-in some such individuals. It has been suggested that, in remedial training, children with learning disorders be encouraged to develop such hidden talents to full capacity, rather than be subjected to the usual overemphasis on the correction of the disturbed coded symbol operations.

  9. Soudage de bois feuillus par friction rotationnelle

    OpenAIRE

    Belleville, Benoît

    2012-01-01

    Les différentes colles utilisées actuellement par l’industrie du meuble au Canada nécessitent des temps de polymérisation constituant un goulot dans la production des meubles et limitant l’atteinte de la production unitaire. Ces adhésifs synthétiques généralement issus de la pétrochimie nécessitent énormément d’énergie lors de leur confection. L’utilisation de connecteurs métalliques ou plastiques, quant à elle, limite les phases de découpage et sablage subséquentes. La présence d’adhésifs et...

  10. Determination of local boiling in light water reactors by correlation of the neutron noise; Determination de l'ebullition locale dans les reacteurs a eau legere par correlation du bruit neutronique

    Energy Technology Data Exchange (ETDEWEB)

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

    1968-07-01

    The power limit of swimming-pool type reactors depends on the phenomenon of the appearance of burn-out. In order to determine this limit we have attempted to detect the local boiling which usually occurs before the burn out. Local boiling has been simulated by an electrically heated plate placed in the core of the reactor Siloette. The study of local boiling, which is based on the properties of the correlation functions for the neutron noise of detectors placed in the core, shows that a privileged frequency occurs in the power spectrum of the noise. It is intended in the future to determine the influence of various parameters on this characteristic frequency. (author) [French] La limitation de la puissance des reacteurs nucleaires de type piscine est due au phenomene d'apparition de 'burn out'. Pour determiner cette limitation, nous nous sommes proposes dans ce rapport de detecter l'ebullition locale qui apparait generalement avant le 'burn out'. L'ebullition locale a ete simulee par une plaque chauffee electriquement et placee dans le coeur du reacteur SILOETTE. L'etude de l'ebullition locale, qui est basee sur les proprietes des fonctions de correlation du bruit neutronique de detecteurs places clans le coeur, fait apparaitre une frequence privilegiee dans le spectre de puissance du bruit. On envisage dans l'avenir, de determiner l'influence des divers parametres sur cette frequence caracteristique. (auteur)

  11. TMS suppression of right pars triangularis, but not pars opercularis, improves naming in aphasia

    Science.gov (United States)

    Naeser, Margaret A.; Martin, Paula I.; Theoret, Hugo; Kobayashi, Masahito; Fregni, Felipe; Nicholas, Marjorie; Tormos, Jose M.; Steven, Megan S.; Baker, Errol H.; Pascual-Leone, Alvaro

    2011-01-01

    This study sought to discover if an optimum 1 cm2 area in the non-damaged right hemisphere (RH) was present, which could temporarily improve naming in chronic, nonfluent aphasia patients when suppressed with repetitive transcranial magnetic stimulation (rTMS). Ten minutes of slow, 1 Hz rTMS was applied to suppress different RH ROIs in eight aphasia cases. Picture naming and response time (RT) were examined before, and immediately after rTMS. In aphasia patients, suppression of right pars triangularis (PTr) led to significant increase in pictures named, and significant decrease in RT. Suppression of right pars opercularis (POp), however, led to significant increase in RT, but no change in number of pictures named. Eight normals named all pictures correctly; similar to aphasia patients, RT significantly decreased following rTMS to suppress right PTr, versus right POp. Differential effects following suppression of right PTr versus right POp suggest different functional roles for these regions. PMID:21864891

  12. ParABS system in chromosome partitioning in the bacterium Myxococcus xanthus.

    Directory of Open Access Journals (Sweden)

    Antonio A Iniesta

    Full Text Available Chromosome segregation is an essential cellular function in eukaryotic and prokaryotic cells. The ParABS system is a fundamental player for a mitosis-like process in chromosome partitioning in many bacterial species. This work shows that the social bacterium Myxococcus xanthus also uses the ParABS system for chromosome segregation. Its large prokaryotic genome of 9.1 Mb contains 22 parS sequences near the origin of replication, and it is shown here that M. xanthus ParB binds preferentially to a consensus parS sequence in vitro. ParB and ParA are essential for cell viability in M. xanthus as in Caulobacter crescentus, but unlike in many other bacteria. Absence of ParB results in anucleate cells, chromosome segregation defects and loss of viability. Analysis of ParA subcellular localization shows that it clusters at the poles in all cells, and in some, in the DNA-free cell division plane between two chromosomal DNA masses. This ParA localization pattern depends on ParB but not on FtsZ. ParB inhibits the nonspecific interaction of ParA with DNA, and ParA colocalizes with chromosomal DNA only when ParB is depleted. The subcellular localization of ParB suggests a single ParB-parS complex localized at the edge of the nucleoid, next to a polar ParA cluster, with a second ParB-parS complex migrating after the replication of parS takes place to the opposite nucleoid edge, next to the other polar ParA cluster.

  13. Concerning the dynamic instability of actin homolog ParM

    International Nuclear Information System (INIS)

    Popp, David; Yamamoto, Akihiro; Iwasa, Mitsusada; Narita, Akihiro; Maeda, Kayo; Maeda, Yuichiro

    2007-01-01

    Using in vitro TIRF- and electron-microscopy, we reinvestigated the dynamics of native ParM, a prokaryotic DNA segregation protein and actin homolog. In contrast to a previous study, which used a cysteine ParM mutant, we find that the polymerization process of wild type ATP-ParM filaments consists of a polymerization phase and a subsequent steady state phase, which is dynamically unstable, like that of microtubules. We find that the apparent bidirectional polymerization of ParM, is not due to the intrinsic nature of this filament, but results from ParM forming randomly oriented bundles in the presence of crowding agents. Our results imply, that in the bacterium, ParM filaments spontaneously form bipolar bundles. Due to their intrinsic dynamic instability, ParM bundles can efficiently 'search' the cytoplasmic lumen for DNA, bind it equally well at the bipolar ends and segregate it approximately symmetrically, by the insertion of ParM subunits at either end

  14. The protein kinase SIK downregulates the polarity protein Par3

    DEFF Research Database (Denmark)

    Vanlandewijck, Michael; Dadras, Mahsa Shahidi; Lomnytska, Marta

    2018-01-01

    on Par3. Functionally, this mechanism impacts on tight junction downregulation. Furthermore, SIK contributes to the loss of epithelial polarity and examination of advanced and invasive human cancers of diverse origin displayed high levels of SIK expression and a corresponding low expression of Par3...

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-02-15

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

  16. Recombination in the human Pseudoautosomal region PAR1.

    Directory of Open Access Journals (Sweden)

    Anjali G Hinch

    2014-07-01

    Full Text Available The pseudoautosomal region (PAR is a short region of homology between the mammalian X and Y chromosomes, which has undergone rapid evolution. A crossover in the PAR is essential for the proper disjunction of X and Y chromosomes in male meiosis, and PAR deletion results in male sterility. This leads the human PAR with the obligatory crossover, PAR1, to having an exceptionally high male crossover rate, which is 17-fold higher than the genome-wide average. However, the mechanism by which this obligatory crossover occurs remains unknown, as does the fine-scale positioning of crossovers across this region. Recent research in mice has suggested that crossovers in PAR may be mediated independently of the protein PRDM9, which localises virtually all crossovers in the autosomes. To investigate recombination in this region, we construct the most fine-scale genetic map containing directly observed crossovers to date using African-American pedigrees. We leverage recombination rates inferred from the breakdown of linkage disequilibrium in human populations and investigate the signatures of DNA evolution due to recombination. Further, we identify direct PRDM9 binding sites using ChIP-seq in human cells. Using these independent lines of evidence, we show that, in contrast with mouse, PRDM9 does localise peaks of recombination in the human PAR1. We find that recombination is a far more rapid and intense driver of sequence evolution in PAR1 than it is on the autosomes. We also show that PAR1 hotspot activities differ significantly among human populations. Finally, we find evidence that PAR1 hotspot positions have changed between human and chimpanzee, with no evidence of sharing among the hottest hotspots. We anticipate that the genetic maps built and validated in this work will aid research on this vital and fascinating region of the genome.

  17. Direct digital control of furnaces irradiated in nuclear reactors; Surveillance et regulation multiplexee par calculateur numerique de fours irradies

    Energy Technology Data Exchange (ETDEWEB)

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

    1969-07-01

    An experimental direct digital control system has been realised in the 'C.E.N.G.', in order to verify that a computer makes easier the control of the experiments done in the nuclear reactors and to solve the theoretical and technical difficulties. The regulation is applied to thermal processes. The sampled data systems theory permits to choose the type of an efficient and simple digital compensator, and to establish a diagram which gives the values of the correcting parameters (obtained by minimizing the difference between the output and the input when perturbations occur). The programme execute, in simultaneity, supervision and regulation. Complex possibilities of printing out measures and alarms existed. The computer works out an incremental correction which makes step motors to turn. These motors act on the heating organs. The theoretical values and answers have been confirmed. The accuracy was limited essentially by the input quantification (1/1000 th). The comfort of such a system has been noticeable. (author) [French] Une installation de controle numerique direct fut realisee a titre experimental au C.E.N.G pour verifier qu'un ordinateur rendait plus aisee l'exploitation des experiences faites en pile nucleaire et pour degager les difficultes theoriques et techniques. La regulation s'applique a des processus thermiques. La theorie des systemes echantillonnes a permis de choisir un type de correcteur numerique simple et efficace et d'etablir un abaque qui donne les valeurs des parametres correcteurs minimisant les ecarts enregistres entre la reponse et la consigne en presence de perturbations. Le programme effectuait simultanement de la surveillance et de la regulation. Une restitution complexe des informations et des alarmes sur machine a ecrire etait possible. Le calculateur elaborait une correction incrementielle qui faisait tourner des moteurs pas a pas, lesquels commandaient les organes de puissance de chauffage. Les valeurs et les reponses theoriques ont

  18. Direct digital control of furnaces irradiated in nuclear reactors; Surveillance et regulation multiplexee par calculateur numerique de fours irradies

    Energy Technology Data Exchange (ETDEWEB)

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

    1969-07-01

    An experimental direct digital control system has been realised in the 'C.E.N.G.', in order to verify that a computer makes easier the control of the experiments done in the nuclear reactors and to solve the theoretical and technical difficulties. The regulation is applied to thermal processes. The sampled data systems theory permits to choose the type of an efficient and simple digital compensator, and to establish a diagram which gives the values of the correcting parameters (obtained by minimizing the difference between the output and the input when perturbations occur). The programme execute, in simultaneity, supervision and regulation. Complex possibilities of printing out measures and alarms existed. The computer works out an incremental correction which makes step motors to turn. These motors act on the heating organs. The theoretical values and answers have been confirmed. The accuracy was limited essentially by the input quantification (1/1000 th). The comfort of such a system has been noticeable. (author) [French] Une installation de controle numerique direct fut realisee a titre experimental au C.E.N.G pour verifier qu'un ordinateur rendait plus aisee l'exploitation des experiences faites en pile nucleaire et pour degager les difficultes theoriques et techniques. La regulation s'applique a des processus thermiques. La theorie des systemes echantillonnes a permis de choisir un type de correcteur numerique simple et efficace et d'etablir un abaque qui donne les valeurs des parametres correcteurs minimisant les ecarts enregistres entre la reponse et la consigne en presence de perturbations. Le programme effectuait simultanement de la surveillance et de la regulation. Une restitution complexe des informations et des alarmes sur machine a ecrire etait possible. Le calculateur elaborait une correction incrementielle qui faisait tourner des moteurs pas a pas, lesquels commandaient les organes de puissance de chauffage. Les valeurs

  19. Nuclear energy. Waste-packages activity measurement. Part. 1: high-resolution gamma spectrometry in integral mode with open geometry; ISO 14850-1: 2004. Energie nucleaire -- Mesurage de l'activite de colis de dechets. Partie 1: Spectrometrie gamma haute resolution en mode integral et geometrie ouverte

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    ISO 14850:2004 describes a procedure for measurements of gamma-emitting radionuclide activity in homogeneous objects such as unconditioned waste (including process waste, dismantling waste, etc.), waste conditioned in various matrices (bitumen, hydraulic binder, thermosetting resins, etc.), notably in the form of 100 L, 200 L, 400 L or 800 L drums, and test specimens or samples, (vitrified waste), and waste packaged in a container, notably technological waste. It also specifies the calibration of the gamma spectrometry chain. The gamma energies used generally range from 0,05 MeV to 3 MeV.

  20. Nuclear energy - Waste-packages activity measurement - Part.1: high-resolution gamma spectrometry in integral mode with open geometry; ISO 14850-1:2004. Energie nucleaire - Mesurage de l'activite de colis de dechets - Partie 1: spectrometrie gamma haute resolution en mode integral et geometrie ouverte

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    ISO 14850:2004 describes a procedure for measurements of gamma-emitting radionuclide activity in homogeneous objects such as unconditioned waste (including process waste, dismantling waste, etc.), waste conditioned in various matrices (bitumen, hydraulic binder, thermosetting resins, etc.), notably in the form of 100 L, 200 L, 400 L or 800 L drums, and test specimens or samples, (vitrified waste), and waste packaged in a container, notably technological waste. It also specifies the calibration of the gamma spectrometry chain. The gamma energies used generally range from 0,05 MeV to 3 MeV. (authors)

  1. 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)

  2. Isotope tracing ({sup 29}Si and {sup 18}O) of the alteration mechanisms of the French glass 'SON68' used for the storage of nuclear waste; Tracage isotopique ({sup 29}Si and {sup 18}O) des mecanismes de l'alteration du verre de confinement des dechets nucleaires: 'SON68'

    Energy Technology Data Exchange (ETDEWEB)

    Valle, N

    2001-07-01

    This study aims to enhance our understanding of the mechanisms of aqueous corrosion of the glasses used for the storage of nuclear waste. Glass samples 'SON68', doped with a different rare earth element (La, Ce or Nd), were altered simultaneously with water enriched in {sup 29}Si and {sup 18}O, throughout a period of 20 months. The aim of such isotope tracing was (i) to follow the 'real' exchanges between glass and solution and (ii) to understand the reactions involving Si-O bonds in the leached layer during alteration. Leachates were analyzed by ICP-MS and -AES, and elemental and isotopic variations in the altered glass layer were measured by ion-probe, using a depth profiling technique. Elemental analyses enabled the distribution of the elements in the two layers of altered glass (phyllosilicates and gel) to be established, and the results reveal a selective partitioning of elements between the two layers. Isotopic analyses of altered layers and leachates allowed phyllosilicates to be distinguished from gel, and suggest two different mechanisms of formation. Whilst phyllosilicates grow on the surface of the glass by a mechanism of precipitation, gel is formed by a succession of hydrolysis / condensation reactions taking place mainly at the gel / pristine glass interface. This gel is formed by the in situ rearrangement of hydrated species, without reaching equilibrium with the solution. Moreover, an experimental technique has been developed enabling one to trace the transport of silicon from the solution into the altered glasses, under an isotopic gradient. Diffusion profiles, obtained by ion-probe, have been modeled and have allowed the determination of the apparent silicon diffusion coefficient (DSi) in gels. Therefore, our experiments have permitted the quantification of the influence of both the alteration conditions (dynamic or static tests) and the solution composition on the value of DSi. (author)

  3. The CNRS and the nuclear wastes management. Contribution to the program on the electronuclear cycle downstream PACE at the law of the 30 December 1991; Le CNRS et la gestion des dechets nucleaires. Contribution du programme sur l'aval du cycle electronucleaire PACE a la loi du 30 decembre 1991

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    This document is a presentation of the activities of the PACE program. It presents the researches historical aspects, the researches concerning the axis 1 (transmutation, nuclear data acquisition, scenarios, separation and physico-chemistry in homogenous solution, the specific conditioning) and the axis 2 researches (the containment safety studies of the underground disposal, the physico-chemical phenomenons at the interfaces, the radionuclides migration). (A.L.B.)

  4. Nuclear fuel cycle and marine environment. Behavior of the Rhone river effluents in the mediterranean sea and of wastes dumped in the northeast atlantic; Cycle du combustible nucleaire et milieu marin. Devenir des effluents rhodaniens en mediterranee et des dechets immerges en atlantique nord-est

    Energy Technology Data Exchange (ETDEWEB)

    Charmasson, S

    1998-07-01

    Man-made radionuclides released into the marine environment by the installations from the nuclear fuel cycle are used as tracers of various bio-geochemical processes. Several installations belonging to the whole nuclear fuel cycle, except the uranium mining, are set up on the Rhone River Banks. The sea disposal of low and intermediate level radioactive waste has never been authorized in the Mediterranean sea but several sites have been used in the North-East especially in abyssal waters. Radionuclides released by the Rhone river installations are used in order to study the dynamics of the Rhone inputs into the Mediterranean Sea. In the river, freshwater samples reflect quite accurately the discharge composition with a predominance of {sup 106}Ru, a radionuclide mostly released by the spent nuclear fuel reprocessing plant in Marcoule. Conversely, at the Rhone mouth, in the sediment compartment {sup 106}Ru yields to caesium isotopes ({sup 134}Cs and {sup 137}Cs) in importance. As these two isotopes demonstrate very different half-lives (30,2 and 2,1 years respectively), the temporal evolution of their ratio acts as a chronometer enabled to date sediment accumulation near the river mouth. Mean accumulation rates greater than 35 cm y{sup -1} have been determined in the pro-deltaic zone near the Roustan buoys over the period 1983-1991. Accumulation rates decrease rapidly with distance from the mouth and therefore most of the {sup 137}Cs inventory in this part of the Gulf of Lions is limited to the pro-deltaic area. A first study about the part the different {sup 137}Cs sources in the Mediterranean Sea play in this inventory has been carried out. Direct (atmospheric) and indirect (fluviatile) inputs due to fallout from both past nuclear tests and the Chernobyl accident could contribute to this inventory at the highest to 40 % while the industrial releases could contribute at the lowest to 60 %. The last site used for the dumping of low and intermediate level radioactive waste in the North-East Atlantic has been the subject of studies especially as regards the biological compartment. Indeed, the occurrence in abyssal waters of a very motile fauna, i.e. fish (Coryphaenoides armatus) and amphipods (Eurythenes gryllus), able to undertake important vertical migrations into the water column, represents a possible pathway towards the surface for the dumped radionuclides. The ignorance as regards populations inhabiting this site has led to a study of the population structure for the amphipod Eurythenes gryllus. This species is cosmopolite since it is found at all the latitudes in the world ocean both in bathyal and abyssal waters. Well known for its necrophagy and ability to consume baits, it is supposed to feed on carcasses. However, study of a natural radionuclide, i.e. {sup 210}Po, in this species has shown that it is possible that it feeds also on particle fluxes. In order to verify the validity of the data used for the modelling of the radiological assessment of these operations, in situ labelling experiments have been realized on these amphipods as well as on polychaetes from food labelled with radionuclides characterizing the dumped wastes. Though these results are still too few to acknowledge this validity, as expected from studies on coastal species the transfer factors food-organisms are quite low. Analyses carried out for surveillance purposes both on the fish Coryphaenoides armatus and the amphipod Eurythenes gryllus show that in these deep waters the main source of man-made radioactivity is the global fallout due to the atmospheric nuclear testing carried out mainly in the sixties. A transfer via the particle fluxes is necessary to explain the concentrations found for {sup 3}H, {sup 137}Cs, {sup 238}Pu and {sup 239+240}Pu. However, {sup 238}Pu/{sup 239+240}Pu isotopic ratios in some fish samples suggest and influence from the dumped wastes and underline the possible part taken by these necrophagous organisms in the dispersion of radionuclides released form the low and intermediate level radioactive waste dumped in the North-East Atlantic. (author)

  5. (Alpha, gamma) irradiation effect on the alteration of high-level radioactive wastes matrices (UO{sub 2}, hollandite, glass SON68); Effet de l'irradiation (alpha, gamma) sur l'alteration des matrices de dechets nucleaires de hautes activites (UO{sub 2}, hollandite, verre SON68)

    Energy Technology Data Exchange (ETDEWEB)

    Suzuki, T

    2007-06-15

    The aim of this work is to determine the effect of irradiation on the alteration of high level nuclear waste forms matrices. The matrices investigated are UO{sub 2} to simulate the spent fuel, the hollandite for the specific conditioning of Cs, and the inactive glass SON68 representing the nuclear glass R7T7) The alpha irradiation experiments on UO{sub 2} colloids in aqueous carbonate media have enabled to distinguish between the oxidation of UO{sub 2} matrix as initial and dissolution as subsequent step. The simultaneous presence of carbonate and H{sub 2}O{sub 2} (product resulting from water radiolysis) increased the dissolution rate of UO{sub 2} to its maximum value governed by the oxidation rate. ii) The study of hollandite alteration under gamma irradiation confirmed the good retention capacity for Cs and Ba. Gamma irradiation had brought only a little influence on releasing of Cs and Ba in solution. Electronic irradiation had conducted to the amorphization of the hollandite only for a dose 1000 times higher than the auto-induced dose of Ba over millions of years. iii) The experiences of glass irradiation under alpha beam and of helium implantation in the glass SON68 were analyzed by positon annihilation spectroscopy. No effect has been observed on the solid surface for an irradiation dose equal to 1000 years of storage. (author)

  6. 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)

  7. Irradiations effects on the structure of boro-silicated glasses: long term behaviour of nuclear waste glassy matrices; Effets d'irradiations sur la structure de verres borosilicates - comportement a long terme des matrices vitreuses de stockage des dechets nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Bonfils, J. de

    2007-09-15

    This work deals with the long term behaviour of R7T7-type nuclear waste glasses and more particularly of non-active boro-silicated glasses made up of 3 or 5 oxides. Radioactivity of active glasses is simulated by multi energies ions implantations which reproduce the same defects. The damages due to the alpha particles are simulated by helium ions implantations and those corresponding to the recoil nucleus are obtained with gold ions ones. Minor actinides, stemming from the used fuel, is simulated by trivalent rare-earths (Eu{sup 3+} and Nd{sup 3+}). In a first part, we have shown by macroscopic experiments (Vickers hardness - swelling) and optical spectroscopies (Raman - ATR-IR) that the structure of the glassy matrices is modified under implantations until a dose of 2,3.10{sup 13} at.cm{sup -2}, which corresponds to a R7T7 storage time estimated at 300 years. Beyond this dose, no additional modifications have been observed. The second part concerns the local environment of the rare-earth ions in glasses. Two different environments were found and identified as follows: one is a silicate rich one and the other is attributed to a borate rich one. (author)

  8. 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.

  9. 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.)

  10. Magnetic resonance studies of solid polymers; Etude des polymeres solides par resonance magnetique

    Energy Technology Data Exchange (ETDEWEB)

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

    1969-07-01

    This paper is a review of the application of nuclear magnetic resonance (NMR) to solid polymers. In the first, theoretical part, the elements of the theory of NMR, which are necessary for the study of the properties of solid polymers are discussed: the moments method, nuclear relaxation and the distribution of correlation times. In the second part the experimental results are presented. (author) [French] Cette etude est une recherche bibliographique sur l'application de la resonance magnetique nucleaire (RMN) aux polymeres solides. Dans la premiere partie theorique on discute les elements de la theorie de RMN, necessaires pour l'etude des proprietes des polymeres solides: la methode des moments, la relaxation nucleaire et la distribution des temps de correlation. La deuxieme partie presente les resultats des experiences. (auteur)

  11. Detection and location of can rupture in reactors cooled by a flow of water; Detection et localisation des ruptures de gaines sur les reacteurs refroidis par circulation d'eau

    Energy Technology Data Exchange (ETDEWEB)

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

    1968-07-01

    This report brings together the principal methods of fission-product detection used for water reactors. The position, type and method of adjustment is given for each detector. The methods for localizing the defective elements are explained, in particular those using water sampling or decreases in the flux. A few installations are briefly described. They correspond to particular types of reactors using boiling, pressurized or cold water. Amongst the many methods used, it can be noted that when the fuel is resistant, the installations are fairly compact. In nuclear super-heated reactors on the other hand, the study of fuel behaviour calls for larger installations. An identification of defective elements exists when the reactor structure allows it. If this is not possible, a localization in a group of elements is obtained by a flux depression. (author) [French] Ce rapport rassemble les principales methodes de detection de produits de fission utilisees pour des reacteurs a eau. On indique pour les detecteurs leurs emplacements, leurs types, leurs reglages. On explique quelles sont les methodes de localisation des elements defectueux, en particulier celles utilisant des prelevements d'eau ou des depressions de flux. Quelques installations sont decrites sommairement. Elles correspondent a des types particuliers de reacteurs a eau bouillante, pressurisee ou froide. Parmi les nombreuses methodes utilisees, on constate que les installations sont peu importantes, lorsque le combustible est resistant. Par contre dans les reacteurs a surchauffe nucleaire l'etude du comportement du combustible necessite des installations plus importantes. Une identification d'elements defectueux existe lorsque la structure du reacteur le permet. A defaut une localisation dans un groupe d'elements est obtenue par depression de flux. (auteur)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-07-01

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

  13. PARs for combustible gas control in advanced light water reactors

    International Nuclear Information System (INIS)

    Hosler, J.; Sliter, G.

    1997-01-01

    This paper discusses the progress being made in the United States to introduce passive autocatalytic recombiner (PAR) technology as a cost-effective alternative to electric recombiners for controlling combustible gas produced in postulated accidents in both future Advanced Light Water Reactors (ALWRs) and certain U. S. operating nuclear plants. PARs catalytically recombine hydrogen and oxygen, gradually producing heat and water vapor. They have no moving parts and are self-starting and self-feeding, even under relatively cold and wet containment conditions. Buoyancy of the hot gases they create sets up natural convective flow that promotes mixing of combustible gases in a containment. In a non-inerted ALWR containment, two approaches each employing a combination of PARs and igniters are being considered to control hydrogen in design basis and severe accidents. In pre-inerted ALWRs, PARs alone control radiolytic oxygen produced in either accident type. The paper also discusses regulatory feedback regarding these combustible gas control approaches and describes a test program being conducted by the Electric Power Research Institute (EPRI) and Electricite de France (EdF) to supplement the existing PAR test database with performance data under conditions of interest to U.S. plants. Preliminary findings from the EPRI/EdF PAR model test program are included. Successful completion of this test program and confirmatory tests being sponsored by the U. S. NRC are expected to pave the way for use of PARs in ALWRs and operating plants. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-02-15

    'un stade au stade suivant. Les auteurs exposent les resultats d'etudes en laboratoire sur la production de verres au phosphate, suivant un processus continu, avec differents types de dechets liquides. Ces etudes, qui sont en cours depuis une vingtaine de mois, ont pour objet de determiner les parametres de fonctionnement essentiels, en tenant compte notamment de la resistance a la corrosion et de l'integrite physique du creuset et haute temperature. Les auteurs commentent aussi le diagramme de circulation ainsi que les plans et le fonctionnement d'une installation experimentale pouvant produire 14 dm{sup 3} de verre par jour en etant alimentee de maniere continue avec des dechets simules. (author) [Spanish] En el estudio de los metodos para la evacuacion definitiva de desechos de elevada radiactividad, que se realiza en el Brookhaven National Laboratory, se viene prestando particular atencion a la formacion de vidrios al fosfato como recurso para incorporar los productos de fision a un medio estable. Interesa principalmente encontrar un proceso con arreglo al cual la conversion, desde los desechos acuosos en bruto hasta el producto vitreo final, pueda efectuarse enteramente en fase liquida. En este sentido, el metodo del vidrio al fosfato ofrece una serie de importantes ventajas y, en particular, se presta para el desarrollo de un proceso continuo en cuyo curso el medio liquido puede pasar facilmente de una operacion a otra. El autor expone los resultados de estudios de laboratorio sobre la obtencion de vidrios al fosfato, con arreglo a un procedimiento continuo con distintos tipos de desechos acuosos. Estos estudios se vienen realizando desde unos veinte meses atras y su proposito es determinar los parametros funcionales basicos, prestandose particular atencion a la resistencia a la corrosion y a la integridad fisica del crisol de alta temperatura. Ademas, se examina en la memoria el trazado del diagrama de circulacion, juntamente con el calculo y los resultados obtenidos

  15. Experimental contamination of margaritana margaritifera (L) (a Fresh water bivalve) by caesium 137; Contamination experimentale de margaritana margaritifera (L) (bivalve d'eau douce) par le cesium 137

    Energy Technology Data Exchange (ETDEWEB)

    Foulquier, L.; Bovard, P.; Grauby, A. [Commissariat a l' Energie Atomique, Cadarache (France). Centre d' Etudes Nucleaires

    1966-07-01

    The hydro biological research carried out in the Radio-Ecology Section has led the authors to study some Margaritana sampling stations situated down-stream from the Monts d'Arree nuclear power station. They describe the preservation and contamination methods used for fixing the {sup 137}Cs concentration factors in the case of Margaritana Margaritifera (L). The results of experiments carried out over a period of one hundred days show that the specific activity of the various organs is stabilized after thirty to thirty-five days. The authors have noticed a relatively low adsorption on the shell through the intermediary of micro-organisms, and a strong and rapid absorption in the soft parts. The concentration factors have values, at equilibrium, of around: 9 for the shell, 300 for all the organs, and 38 for the whole animal. A comparison of these results with work published by other authors makes it possible to draw general conclusions concerning the mechanism of {sup 137}Cs fixation by lamellibranch, as well as their capacity of fixation. (author) [French] Les etudes hydrobiologiques effectuees au sein de la Section de Radio-Ecologie ont amene les auteurs a etudier des stations de prelevement de Margaritana en aval de la Centrale Nucleaire des Monts d'Arree. Ils decrivent les methodes de conservation et de contamination utilisees pour l'etablissement des facteurs de concentration du {sup 137}Cs par Margaritana margaritifera (L). Les resultats des experimentations menees pendant cent jours montrent que les activites specifiques de la coquille et des differents organes se stabilisent au bout de trente a trente-cinq jours. Les auteurs constatent une adsorption relativement faible sur la coquille par l'intermediaire des micro-organismes et une absorption forte et rapide dans les parties molles. Les facteurs de concentration se situent, a l'equilibre, autour de: 9 pour la coquille, 300 pour l'ensemble des organes et 38 si l'on considere

  16. uPAR as anti-cancer target

    DEFF Research Database (Denmark)

    Lund, Ida K; Illemann, Martin; Thurison, Tine

    2011-01-01

    , and a potential diagnostic and predictive impact of the different uPAR forms has been reported. Hence, pericellular proteolysis seems to be a suitable target for anti-cancer therapy and numerous approaches have been pursued. Targeting of this process may be achieved by preventing the binding of uPA to u...... using mouse monoclonal antibodies (mAbs) against mouse uPA or uPAR. These reagents will target uPA and uPAR in both stromal cells and cancer cells, and their therapeutic potential can now be assessed in syngenic mouse cancer models....

  17. Limnological database for Par Pond: 1959 to 1980

    International Nuclear Information System (INIS)

    Tilly, L.J.

    1981-03-01

    A limnological database for Par Pond, a cooling reservoir for hot reactor effluent water at the Savannah River Plant, is described. The data are derived from a combination of research and monitoring efforts on Par Pond since 1959. The approximately 24,000-byte database provides water quality, primary productivity, and flow data from a number of different stations, depths, and times during the 22-year history of the Par Pond impoundment. The data have been organized to permit an interpretation of the effects of twenty years of cooling system operations on the structure and function of an aquatic ecosystem

  18. Protease-activated receptor (PAR2, but not PAR1, is involved in collateral formation and anti-inflammatory monocyte polarization in a mouse hind limb ischemia model.

    Directory of Open Access Journals (Sweden)

    Lisa G van den Hengel

    Full Text Available AIMS: In collateral development (i.e. arteriogenesis, mononuclear cells are important and exist as a heterogeneous population consisting of pro-inflammatory and anti-inflammatory/repair-associated cells. Protease-activated receptor (PAR1 and PAR2 are G-protein-coupled receptors that are both expressed by mononuclear cells and are involved in pro-inflammatory reactions, while PAR2 also plays a role in repair-associated responses. Here, we investigated the physiological role of PAR1 and PAR2 in arteriogenesis in a murine hind limb ischemia model. METHODS AND RESULTS: PAR1-deficient (PAR1-/-, PAR2-deficient (PAR2-/- and wild-type (WT mice underwent femoral artery ligation. Laser Doppler measurements revealed reduced post-ischemic blood flow recovery in PAR2-/- hind limbs when compared to WT, while PAR1-/- mice were not affected. Upon ischemia, reduced numbers of smooth muscle actin (SMA-positive collaterals and CD31-positive capillaries were found in PAR2-/- mice when compared to WT mice, whereas these parameters in PAR1-/- mice did not differ from WT mice. The pool of circulating repair-associated (Ly6C-low monocytes and the number of repair-associated (CD206-positive macrophages surrounding collaterals in the hind limbs were increased in WT and PAR1-/- mice, but unaffected in PAR2-/- mice. The number of repair-associated macrophages in PAR2-/- hind limbs correlated with CD11b- and CD115-expression on the circulating monocytes in these animals, suggesting that monocyte extravasation and M-CSF-dependent differentiation into repair-associated cells are hampered. CONCLUSION: PAR2, but not PAR1, is involved in arteriogenesis and promotes the repair-associated response in ischemic tissues. Therefore, PAR2 potentially forms a new pro-arteriogenic target in coronary artery disease (CAD patients.

  19. Novel role for proteinase-activated receptor 2 (PAR2) in membrane trafficking of proteinase-activated receptor 4 (PAR4).

    Science.gov (United States)

    Cunningham, Margaret R; McIntosh, Kathryn A; Pediani, John D; Robben, Joris; Cooke, Alexandra E; Nilsson, Mary; Gould, Gwyn W; Mundell, Stuart; Milligan, Graeme; Plevin, Robin

    2012-05-11

    Proteinase-activated receptors 4 (PAR(4)) is a class A G protein-coupled receptor (GPCR) recognized through the ability of serine proteases such as thrombin and trypsin to mediate receptor activation. Due to the irreversible nature of activation, a fresh supply of receptor is required to be mobilized to the cell surface for responsiveness to agonist to be sustained. Unlike other PAR subtypes, the mechanisms regulating receptor trafficking of PAR(4) remain unknown. Here, we report novel features of the intracellular trafficking of PAR(4) to the plasma membrane. PAR(4) was poorly expressed at the plasma membrane and largely retained in the endoplasmic reticulum (ER) in a complex with the COPI protein subunit β-COP1. Analysis of the PAR(4) protein sequence identified an arginine-based (RXR) ER retention sequence located within intracellular loop-2 (R(183)AR → A(183)AA), mutation of which allowed efficient membrane delivery of PAR(4). Interestingly, co-expression with PAR(2) facilitated plasma membrane delivery of PAR(4), an effect produced through disruption of β-COP1 binding and facilitation of interaction with the chaperone protein 14-3-3ζ. Intermolecular FRET studies confirmed heterodimerization between PAR(2) and PAR(4). PAR(2) also enhanced glycosylation of PAR(4) and activation of PAR(4) signaling. Our results identify a novel regulatory role for PAR(2) in the anterograde traffic of PAR(4). PAR(2) was shown to both facilitate and abrogate protein interactions with PAR(4), impacting upon receptor localization and cell signal transduction. This work is likely to impact markedly upon the understanding of the receptor pharmacology of PAR(4) in normal physiology and disease.

  20. Utilisation de l'essai comete et du biomarqueur gamma-H2AX pour detecter les dommages induits a l'ADN cellulaire par le 5-bromodeoxyuridine post-irradiation

    Science.gov (United States)

    La Madeleine, Carole

    Ce memoire est presente a la Faculte de medecine et des sciences de la sante de l'Universite de Sherbrooke en vue de l'obtention du grade de maitre es sciences (M.Sc.) en radiobiologie (2009). Un jury a revise les informations contenues dans ce memoire. Il etait compose de professeurs de la Faculte de medecine et des sciences de la sante soit : Darel Hunting PhD, directeur de recherche (departement de medecine nucleaire et radiobiologie), Leon Sanche PhD, directeur de recherche (departement de medecine nucleaire et radiobiologie), Richard Wagner PhD, membre du programme (departement de medecine nucleaire et radiobiologie) et Guylain Boissonneault PhD, membre exterieur au programme (departement de biochimie). Le 5-bromodeoxyuridine (BrdU), un analogue halogene de la thymidine reconnu depuis les annees 60 comme etant un excellent radiosensibilisateur. L'hypothese la plus repandue au sujet de l'effet radio sensibilisant du BrdU est qu'il augmente le nombre de cassures simple et double brin lorsqu'il est incorpore dans l'ADN de la cellule et expose aux radiations ionisantes. Toutefois, de nouvelles recherches semblent remettre en question les observations precedentes. Ces dernieres etudes ont confirme que le BrdU est un bon radiosensibilisateur, car il augmente les dommages radio-induits dans l'ADN. Mais, c'est en etant incorpore dans une region simple brin que le BrdU radiosensibilise l'ADN. Ces recherches ont egalement revele pour la premiere fois un nouveau type de dommages produits lors de l'irradiation de l'ADN contenant du BrdU : les dimeres interbrins. Le but de ces travaux de recherche est de determiner si la presence de bromodeoxyuridine dans l'ADN augmente l'induction de bris simple et / ou double brin chez les cellules irradiees en utilisant de nouvelles techniques plus sensibles et specifiques que celles utilisees auparavant. Pour ce faire, les essais cometes et la detection des foci H2AX phosphorylee pourraient permettre d'etablir les effets engendres par

  1. Positron Accumulator Ring (PAR) power supply

    International Nuclear Information System (INIS)

    Fathizadeh, M.

    1995-01-01

    The Positron Accumulator Ring (PAR) consists of 8 dipole magnets connected in series. These magnets are energized via one 12-pulse dc power supply. The power supply consists of four phase controlled half-wave wye group converters. Each of the two half-wave converters are connected through an interphase transformer to obtain a full-wave converter with 120 degrees conduction. The input voltage for these two half-wave converters are 180 degrees apart. The two full-wave converters are connected in parallel through a third interphase transformer. This type of connection of the converters not only provides the required output current, it also improves the input power factor of the power supply. The output of the wye group converters is filtered through a passive L-R-C filter to reduce the ripple content of the output current. At low current values of the power supply the current ripple is high, thus a large filter is needed, which adds to the cost of the power supply, however at high output current levels, the current ripple is less severe. The large size of the filter can be reduced by adding an anti-parallel rectifier diode(D1) to the output of the power supply. A freewheeling diode(D2) is connected before the choke to circulate the current once the power supply is turned off. In order to measure the current in the magnet a high precision, low drift, zero flux current transductor is used. This transductor senses the magnet current which provides a feedback signal to control the gating of the converter's thyristors. A true 14 bit Digital to Analog Converter (DAC) is programmed by the control computer for the required current value, providing a reference for the current regulator. Fast correction of the line transients is provided by a relatively fast voltage loop controlled by a high gain slow response current loop

  2. First-in-human uPAR PET

    DEFF Research Database (Denmark)

    Persson, Morten; Skovgaard, Dorthe; Brandt-Larsen, Malene

    2015-01-01

    A first-in-human clinical trial with Positron Emission Tomography (PET) imaging of the urokinase-type plasminogen activator receptor (uPAR) in patients with breast, prostate and bladder cancer, is described. uPAR is expressed in many types of human cancers and the expression is predictive...... for targeted molecular imaging with PET. The safety, pharmacokinetic, biodistribution profile and radiation dosimetry after a single intravenous dose of (64)Cu-DOTA-AE105 were assessed by serial PET and computed tomography (CT) in 4 prostate, 3 breast and 3 bladder cancer patients. Safety assessment...... of invasion, metastasis and indicates poor prognosis. uPAR PET imaging therefore holds promise to be a new and innovative method for improved cancer diagnosis, staging and individual risk stratification. The uPAR specific peptide AE105 was conjugated to the macrocyclic chelator DOTA and labeled with (64)Cu...

  3. Peptide-Based Optical uPAR Imaging for Surgery

    DEFF Research Database (Denmark)

    Juhl, Karina; Christensen, Anders; Persson, Morten

    2016-01-01

    Near infrared intra-operative optical imaging is an emerging technique with clear implications for improved cancer surgery by enabling a more distinct delineation of the tumor margins during resection. This modality has the potential to increase the number of patients having a curative radical...... tumor resection. In the present study, a new uPAR-targeted fluorescent probe was developed and the in vivo applicability was evaluated in a human xenograft mouse model. Most human carcinomas express high level of uPAR in the tumor-stromal interface of invasive lesions and uPAR is therefore considered...... an ideal target for intra-operative imaging. Conjugation of the flourophor indocyanine green (ICG) to the uPAR agonist (AE105) provides an optical imaging ligand with sufficiently high receptor affinity to allow for a specific receptor targeting in vivo. For in vivo testing, human glioblastoma xenograft...

  4. Contribution de la tomographie par coherence optique au diagnostic ...

    African Journals Online (AJOL)

    Contribution de la tomographie par coherence optique au diagnostic de la neuropathie optique toxique. C.O.A. Abouki, S Alamou, C.R.A. Assavedo, L Odoulami-Yehouessi, I Sounouvou, S Hounnou-Tchabi ...

  5. Analysis of ParB-centromere interactions by multiplex SPR imaging reveals specific patterns for binding ParB in six centromeres of Burkholderiales chromosomes and plasmids.

    Directory of Open Access Journals (Sweden)

    Flavien Pillet

    Full Text Available Bacterial centromeres-also called parS, are cis-acting DNA sequences which, together with the proteins ParA and ParB, are involved in the segregation of chromosomes and plasmids. The specific binding of ParB to parS nucleates the assembly of a large ParB/DNA complex from which ParA-the motor protein, segregates the sister replicons. Closely related families of partition systems, called Bsr, were identified on the chromosomes and large plasmids of the multi-chromosomal bacterium Burkholderia cenocepacia and other species from the order Burkholeriales. The centromeres of the Bsr partition families are 16 bp palindromes, displaying similar base compositions, notably a central CG dinucleotide. Despite centromeres bind the cognate ParB with a narrow specificity, weak ParB-parS non cognate interactions were nevertheless detected between few Bsr partition systems of replicons not belonging to the same genome. These observations suggested that Bsr partition systems could have a common ancestry but that evolution mostly erased the possibilities of cross-reactions between them, in particular to prevent replicon incompatibility. To detect novel similarities between Bsr partition systems, we have analyzed the binding of six Bsr parS sequences and a wide collection of modified derivatives, to their cognate ParB. The study was carried out by Surface Plasmon Resonance imaging (SPRi mulitplex analysis enabling a systematic survey of each nucleotide position within the centromere. We found that in each parS some positions could be changed while maintaining binding to ParB. Each centromere displays its own pattern of changes, but some positions are shared more or less widely. In addition from these changes we could speculate evolutionary links between these centromeres.

  6. Analysis of ParB-centromere interactions by multiplex SPR imaging reveals specific patterns for binding ParB in six centromeres of Burkholderiales chromosomes and plasmids.

    Science.gov (United States)

    Pillet, Flavien; Passot, Fanny Marie; Pasta, Franck; Anton Leberre, Véronique; Bouet, Jean-Yves

    2017-01-01

    Bacterial centromeres-also called parS, are cis-acting DNA sequences which, together with the proteins ParA and ParB, are involved in the segregation of chromosomes and plasmids. The specific binding of ParB to parS nucleates the assembly of a large ParB/DNA complex from which ParA-the motor protein, segregates the sister replicons. Closely related families of partition systems, called Bsr, were identified on the chromosomes and large plasmids of the multi-chromosomal bacterium Burkholderia cenocepacia and other species from the order Burkholeriales. The centromeres of the Bsr partition families are 16 bp palindromes, displaying similar base compositions, notably a central CG dinucleotide. Despite centromeres bind the cognate ParB with a narrow specificity, weak ParB-parS non cognate interactions were nevertheless detected between few Bsr partition systems of replicons not belonging to the same genome. These observations suggested that Bsr partition systems could have a common ancestry but that evolution mostly erased the possibilities of cross-reactions between them, in particular to prevent replicon incompatibility. To detect novel similarities between Bsr partition systems, we have analyzed the binding of six Bsr parS sequences and a wide collection of modified derivatives, to their cognate ParB. The study was carried out by Surface Plasmon Resonance imaging (SPRi) mulitplex analysis enabling a systematic survey of each nucleotide position within the centromere. We found that in each parS some positions could be changed while maintaining binding to ParB. Each centromere displays its own pattern of changes, but some positions are shared more or less widely. In addition from these changes we could speculate evolutionary links between these centromeres.

  7. Prise en charge des intoxications par envenimation chez les enfants ...

    African Journals Online (AJOL)

    Les signes cliniques étaient dominés par les douleurs (98%) suivies des hémorragies (73,80%) pour les morsures de serpent, la douleur pour les piqures de scorpion (100%) et les oedèmes pour les piqures d'abeilles (100%). Les cas de morsure de serpent ont été traités par le sérum antivenimeux polyvalent. Conclusion: ...

  8. Intoxication par la paraphényléne-diamine

    African Journals Online (AJOL)

    raoul

    9 mars 2011 ... remède contre la douleur par Averbukh [8], ou contre la constipation par Schemesh [9], mais l´utilisation à des fins autolytique reste toujours prédominante. Le tableau clinique de l´intoxication à ... une anurie ayant nécessité le recours à l´hémodialyse. Ce taux de survenue d´IRA anurique est relativement ...

  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. Croissance epitaxiale de GaAs sur substrats de Ge par epitaxie par faisceaux chimiques

    Science.gov (United States)

    Belanger, Simon

    La situation energetique et les enjeux environnementaux auxquels la societe est confrontee entrainent un interet grandissant pour la production d'electricite a partir de l'energie solaire. Parmi les technologies actuellement disponibles, la filiere du photovoltaique a concentrateur solaire (CPV pour concentrator photovoltaics) possede un rendement superieur et mi potentiel interessant a condition que ses couts de production soient competitifs. La methode d'epitaxie par faisceaux chimiques (CBE pour chemical beam epitaxy) possede plusieurs caracteristiques qui la rendent interessante pour la production a grande echelle de cellules photovoltaiques a jonctions multiples a base de semi-conducteurs III-V. Ce type de cellule possede la meilleure efficacite atteinte a ce jour et est utilise sur les satellites et les systemes photovoltaiques a concentrateur solaire (CPV) les plus efficaces. Une des principales forces de la technique CBE se trouve dans son potentiel d'efficacite d'utilisation des materiaux source qui est superieur a celui de la technique d'epitaxie qui est couramment utilisee pour la production a grande echelle de ces cellules. Ce memoire de maitrise presente les travaux effectues dans le but d'evaluer le potentiel de la technique CBE pour realiser la croissance de couches de GaAs sur des substrats de Ge. Cette croissance constitue la premiere etape de fabrication de nombreux modeles de cellules solaires a haute performance decrites plus haut. La realisation de ce projet a necessite le developpement d'un procede de preparation de surface pour les substrats de germanium, la realisation de nombreuses sceances de croissance epitaxiale et la caracterisation des materiaux obtenus par microscopie optique, microscopie a force atomique (AFM), diffraction des rayons-X a haute resolution (HRXRD), microscopie electronique a transmission (TEM), photoluminescence a basse temperature (LTPL) et spectrometrie de masse des ions secondaires (SIMS). Les experiences ont permis

  11. New purchase conditions by EDF, of the electrical power produced by the energy valorization installations of domestic wastes and assimilated; Nouvelles conditions d'achat par EDF de l'electricite produite par les installations de valorisation energetique des dechets managers et assimiles

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-05-01

    The State Secretary for the Industry, C. Pierret, approved the new purchase conditions by EDF, concerning the electric power, produced by the installations of domestic wastes energy valorization. This action is in agreement with the energy policy. The purchase conditions are presented and commented. (A.L.B.)

  12. Non-intrusive measurement of tritium activity in waste drums by modelling a {sup 3}He leak quantified by mass spectrometry; Mesure non intrusive de l'activite de futs de dechets trities par modelisation d'une fuite {sup 3}He et sa quantification par spectrometrie de masse

    Energy Technology Data Exchange (ETDEWEB)

    Demange, D

    2002-07-03

    This study deals with a new method that makes it possible to measure very low tritium quantities inside radioactive waste drums. This indirect method is based on measuring the decaying product, {sup 3}He, and requires a study of its behaviour inside the drum. Our model considers {sup 3}He as totally free and its leak through the polymeric joint of the drum as two distinct phenomena: permeation and laminar flow. The numerical simulations show that a pseudo-stationary state takes place. Thus, the {sup 3}He leak corresponds to the tritium activity inside the drum but it appears, however, that the leak peaks when the atmospheric pressure variations induce an overpressure in the drum. Nevertheless, the confinement of a drum in a tight chamber makes it possible to quantify the {sup 3}He leak. This is a non-intrusive measurement of its activity, which was experimentally checked by using reduced models, representing the drum and its confinement chamber. The drum's confinement was optimised to obtain a reproducible {sup 3}He leak measurement. The gaseous samples taken from the chamber were purified using selective adsorption onto activated charcoals at 77 K to remove the tritium and pre-concentrate the {sup 3}He. The samples were measured using a leak detector mass spectrometer. The adaptation of the signal acquisition and the optimisation of the analysis parameters made it possible to reach the stability of the external calibrations using standard gases with a {sup 3}He detection limit of 0.05 ppb. Repeated confinement of the reference drums demonstrated the accuracy of this method. The uncertainty of this non-intrusive measurement of the tritium activity in 200-liter drums is 15% and the detection limit is about 1 GBq after a 24 h confinement. These results led to the definition of an automated tool able to systematically measure the tritium activity of all storage waste drums. (authors)

  13. Non-intrusive measurement of tritium activity in waste drums by modelling a {sup 3}He leak quantified by mass spectrometry; Mesure non intrusive de l'activite de futs de dechets trities par modelisation d'une fuite {sup 3}He et sa quantification par spectrometrie de masse

    Energy Technology Data Exchange (ETDEWEB)

    Demange, D

    2002-07-03

    This study deals with a new method that makes it possible to measure very low tritium quantities inside radioactive waste drums. This indirect method is based on measuring the decaying product, {sup 3}He, and requires a study of its behaviour inside the drum. Our model considers {sup 3}He as totally free and its leak through the polymeric joint of the drum as two distinct phenomena: permeation and laminar flow. The numerical simulations show that a pseudo-stationary state takes place. Thus, the {sup 3}He leak corresponds to the tritium activity inside the drum but it appears, however, that the leak peaks when the atmospheric pressure variations induce an overpressure in the drum. Nevertheless, the confinement of a drum in a tight chamber makes it possible to quantify the {sup 3}He leak. This is a non-intrusive measurement of its activity, which was experimentally checked by using reduced models, representing the drum and its confinement chamber. The drum's confinement was optimised to obtain a reproducible {sup 3}He leak measurement. The gaseous samples taken from the chamber were purified using selective adsorption onto activated charcoals at 77 K to remove the tritium and pre-concentrate the {sup 3}He. The samples were measured using a leak detector mass spectrometer. The adaptation of the signal acquisition and the optimisation of the analysis parameters made it possible to reach the stability of the external calibrations using standard gases with a {sup 3}He detection limit of 0.05 ppb. Repeated confinement of the reference drums demonstrated the accuracy of this method. The uncertainty of this non-intrusive measurement of the tritium activity in 200-liter drums is 15% and the detection limit is about 1 GBq after a 24 h confinement. These results led to the definition of an automated tool able to systematically measure the tritium activity of all storage waste drums. (authors)

  14. Iodine-131 treatment of hyperthyroidism in the elderly. Results in 180 patients. Radioprotection and waste management in 131-iodine therapy; Traitement de l'hyperthyroidie du sujet age par l'iode 131. A propos de 180 patients. Problemes de radioprotection et de gestion des dechets lies au traitement par l'iode 131

    Energy Technology Data Exchange (ETDEWEB)

    Dejax, C.; Freitas, D. de; Leroux, M.A.; Aubert, B. [Centre Jean-Perrin, Medecine Nucleaire, 63 - Clermont-Ferrand (France); Vennat, J.C. [Centre Jean-Perrin, Radiopharmacie, 63 - Clermont-Ferrand (France); Kwiatkowski, F. [Centre Jean-Perrin, Biostatistiques, 63 - Clermont-Ferrand (France)

    2005-09-15

    A retrospective study has been performed in patients treated by iodine-131 for hyperthyroidism between April 1999 and February 2004..Among the 270 patients, 180 were more than 65 years old. After 65 years, hyperthyroidism is most often the consequence of a toxic adenoma or multi-nodular goiter while Graves' disease is most frequent in young patients. Iodine-131 is usually proposed as first line treatment in the elderly, at the opposite of young patients. With a mean follow-up of 12 months, return to euthyroidism is observed in 56.5% of the older patients and in 73.6% of the young patients. We explain this results by the lower incidence of Graves' disease in the elderly. Nuclear medicine physicians are legally obliged to provide patients with a proper information about radioprotection. Recommendations should nevertheless not induce overdue nor illegitimate fear. They should not only be written and standardized, but also given orally and adapted to each patient. Urinary incontinence is not specific to the old patients, but it is more frequent after 65. Collection and storage of contaminated waste is sometimes difficult and has often to be solved on a case by case basis. (author)

  15. The Enrico Fermi Atomic Power Plant; La centrais nucleaire Enrico Fermi; Atomnaya ehlektrostantsiya im Ehnriko Fermi.; La central nucleoelectrica Enrico Fermi

    Energy Technology Data Exchange (ETDEWEB)

    Hartwell, R. W. [Power Reactor Development Company, Detroit, MI (United States)

    1963-10-15

    sodium-water reaction took place in the No. 1 steam generator. The rupture disc, which was installed for such an eventuality, operated correctly. The cause and effect of this failure is currently being investigated. Completion of pre-operational testing. Anticipating the issuance of a low power licence, the final assembly and test programme is being completed in March. (author) [French] La construction de la centrale nucleaire Enrico Fermi, equipee d'un reacteur surgenerateur a neutrons rapides de 100 MWe, a ete virtuellement terminee en decembre 1961. Au cours des derniers 18 mois, on a minutieusement verifie les circuits et les parties constitutives. Ce programme de verifications avant la mise en service a ete tres utile pour verifier les plans et determiner les modifications a y apporter. Tous les problemes ont pu etre resolus. Voici la liste des principales modifications: Bouclier de graphite. En decembre 1960, on a rempli le circuit primaire de sodium liquide et on a procede a des essais tres pousses. Lorsqu'on a rouvert l'enceinte de protection primaire, apres les essais a 540{sup o}C, on a constate que la plus grande partie des blocs de graphite entourant le reacteur s'etait deterioree. Ces blocs, destines a supporter de hautes temperatures, etaient impregnes de bore; ils s'etaient dilates et avaient perdu leur resistance. Une analyse approfondie a montre que le liant du graphite avait cede. On a decide de remplacer tout le graphite, d'utiliser du carbure de bore a la place du bore, d'assujettir les blocs par des dispositifs mecaniques et de maintenir l'humidite a la valeur minimum. Modifications a l'interieur du caisson du reacteur. On a procede a des reparations et modifications pour supprimer la cause du collage des barreaux et les dommages qui en resultaient, et pour prevenir d'autres defaillances du mecanisme de manutention des cartouches. Pour ce faire, on a du retirer le mecanisme de manutention et vider le caisson contenant le sodium. Des specialistes

  16. Serum suPAR in patients with FSGS: trash or treasure?

    NARCIS (Netherlands)

    Maas, R.J.H.; Deegens, J.K.J.; Wetzels, J.F.M.

    2013-01-01

    The urokinase-type plasminogen activator receptor (uPAR) has important functions in cell migration. uPAR can be shed from the cell membrane resulting in soluble uPAR (suPAR). Further cleavage gives rise to shorter fragments with largely unknown functions. Recent studies have demonstrated that both

  17. Pointing Out Main Factors from Design, Construction and Operating Experience of Existing Nuclear Plants for Assisting in Shaping Future Nuclear Power Programmes; Les principaux criteres degages de l'etude, de la construction et de l'exploitation des centrales nucleaires existantes et leur interet pour l'elaboration des futurs programmes d'energie d'origine nucleaire; Ukazanie osnovnykh faktorov proektirovaniya, stroitel'stva i opyta ehkspluatatsii sushchestvuyutsikh atomnykh ehlektrostantsij, chto dolzhno pomoch' pri sostavlenii budushchikh programm atomnoj ehnergetiki; Principales consideraciones relativas al diseno, construccion y explotacion de centrales nucleares, encaminadas a facilitar la preparacion de programas futuros de energia nucleoelectrica

    Energy Technology Data Exchange (ETDEWEB)

    Dalla Volta, F. [Comitato Nazionale per l' Energia Nucleare, Rome (Italy)

    1963-10-15

    enseignements qui ont ete fournis, aux points de vue technique et economique, par l'etude, la construction et l'exploitation des premieres centrales nucleaires, et qui peuvent etre particulierement utiles pour l'implantation de nouvelles centrales de ce genre dans l'avenir, notamment eu egard aux conditions qui regnent en Italie. La technologie actuelle des reacteurs et les progres qu'elle continue de faire revelent une tendance marquee vers la reduction du cout, non seulement des cycles de combustible, mais aussi des elements de la centrale. Cette evolution se trouve d'ailleurs favorisee par la tendance croissante a construire des centrales plus grandes et par le fait que l'etude du developpement du reseau electrique semble indiquer que, sur le plan economique, il y a plus d' avantage ainstaller des centrales nucleaires plus puissantes que d'augmenter la puissance des centrales classiques. Se fondant sur l'experience acquise concernant l'etu de, la construction et l'essai des divers types de centrales existantes, l'auteur donne un apercu des principaux facteurs dont il convient de tenir compte lors de l'etablissement des programmes futurs. Il insiste sur le probleme de l'isolement, vu les incidences favorables que peut avoir sur le choix du site de la centrale la mise au point d'ecrans de protection tres surs, qui puissent etre construits sans augmentation sensible du prix de revient, en tirant notamment parti, pour resoudre certains aspects de ce probleme, des conditions particulieres qui se trouvent reunies en Italie. Quant a l'experience du fonctionnement de certaines centrales d'un modele eprouve, l'auteur examine dans quelle mesure ces installations peuvent etre construites sans difficulte et satisfaire la demande du reseau; il se refere ici egalement au role croissant qu'il est prevu d'attribuer a l'energie d'origine nucleaire en Italie. Enfin, l'auteur souligne a quel point le rassemblement et l'interpretation des donnees relatives aux trois centrales, qui doivent

  18. Une terreur par l’image

    Directory of Open Access Journals (Sweden)

    Annie DULONG

    2011-09-01

    Full Text Available Si d’autres événements — Hiroshima, la découverte des camps de concentration, la chute du mur de Berlin — ont, au cours du XXe siècle, marqué suffisamment l’imaginaire pour trouver leur réponse dans des œuvres d’art, le 11 septembre 2001 pose la question de la fictionnalisation autrement : il ne s’agit plus tant de combler les manques de la représentation, liés à l’absence d’images ou au délai dans leur dévoilement, mais bien de composer avec l’omniprésence d’une représentation martelée à la télévision et sur Internet. Que cette représentation soit partielle, tronquée et qu’il lui manque la présence des corps, ces grands absents des photographies et des images tournées par les journalistes, ne change rien au fait que c’est avec le trop-plein que les artistes doivent maintenant négocier.Cet article s’intéresse aux romans qui traitent l’événement de front au lieu de l’aborder sur un mode mineur, et a pour objectif de tracer un portrait de la représentation des médias dans les romans du 11 septembre 2001. Ces romans, outre le fait qu’ils traitent des événements de New York, ont comme point commun un personnage, ou décor : les médias, représentés par la télévision, l’Internet, les photographies de presse, interviennent dans les récits d’une manière significative et témoignent de la force brute des images. À travers une étude de certains des mécanismes à l’œuvre dans The Writing on the Wall (Lynne Sharon Schwartz, Extremely Loud and Incredibly Close (Jonathan Safran Foer, Falling Man (Don DeLillo et A Disorder Peculiar to the Country (Ken Kalfus, il s’agira de proposer des réponses à ces quelques questions : quel rôle les médias jouent-ils, et comment participent-ils au récit ? Quelle pression les images exercent-elles sur les personnages ? Que révèlent les personnages enfants dans leur rapport aux médias ? Quelle critique, finalement, les romans

  19. A study of switch circuits for use as safety devices in nuclear reactors; Etude de circuits de commutation destines a la securite des reacteurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-12-15

    The author reviews briefly a few basic assemblies using electromagnetic relays for safety circuits in nuclear reactors; he then studies the use of static relays with a shorter time of response, based on impedance changes in a self-inductance consisting of a coil with a magnetic core having a rectangular hysteresis cycle. The author examines in particular the way in which it functions and the method of determining the parameters. (author) [French] L'auteur apres avoir examine sommairement en revue quelques montages de base des circuits de securite des reacteurs nucleaires utilisant des relais electromecaniques, etudie l'emploi des relais statiques a plus grande vitesse de reponse bases sur la variation d'impedance que presente une self-inductance realisee a l'aide d'une bobine enroulee autour d'un noyau magnetique a cycle d'hysteresis rectangulaire. En particulier, il en examine le mode de fonctionnement et la determination des parametres. (auteur)

  20. Description of methods for making activation detectors for use in nuclear reactors; Description des procedes de fabrication des detecteurs d'activation utilises dans les reacteurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Barbalat, R; Le Coguie, R; Leger, P; Salon, L; Thierry, M [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1968-07-01

    A brief description of methods currently used for making activation detectors, thin films and various deposits used in nuclear reactors. The thicknesses required vary from about a few tenths of a micron to a few tenths of a millimeter. Different techniques are used for fixing the large variety of elements: rolling, moulding, painting, electrolysis, vacuum deposition, thin films, wires, enamels, protective linings, etc. (authors) [French] Expose succinct des procedes actuellement mis en oeuvre pour la realisation des detecteurs d'activation, feuilles minces et depots divers utilises dans les reacteurs nucleaires. La gamme des epaisseurs necessaires s'etendant approximativement des dixiemes de micrometre aux dixiemes de millimetre. La diversite des elements a fixer justifiant les techniques differentes selon les cas: laminage, moulage, peinture, electrolyse, depot sous vide, couches minces, fils, emaux, revetements protecteurs, etc. (auteurs)

  1. Installation and testing of the 150keV high current pulsed accelerator installed at the Service de Physique Nucleaire in Bruyeres-le-Chatel

    International Nuclear Information System (INIS)

    Dandine, Andre; Sinopoli, Louis.

    1976-01-01

    A 150keV accelerator installed at the Service de Physique Nucleaires in Bruyeres-le-Chatel is described which has been equipped especially for the preparation of the nuclear experiments carried out with the EN 7MV tandem Van de Graaff, and for the completion of totally independent experiments. Details of the ion optical arrangement and the pulsing system are presented; unanalysed beams of intensity 1 to 2mA are obtained accelerating either protons or deuterons. In the pulsed mode, at 1.25 MHz or 2.5MHz, the average intensity of the analysed beam is 8 to 10μA and the pulse length is 2ns [fr

  2. Par Pond vegetation status Summer 1995 -- June survey descriptive summary

    International Nuclear Information System (INIS)

    Mackey, H.E. Jr.; Riley, R.S.

    1995-06-01

    The water level of Par Pond was lowered approximately 20 feet in mid-1991 in order to protect downstream residents from possible dam failure suggested by subsidence on the downstream slope of the dam and to repair the dam. This lowering exposed both emergent and nonemergent macrophyte beds to drying conditions resulting in extensive losses. A survey of the shoreline aquatic plant communities in June 1995, three months after the refilling of Par Pond to approximately 200 feet above mean sea level, indicated that much of the original plant communities and the intermediate shoreline communities present on the exposed sediments have been lost. The extensive old-field and emergent marsh communities that were present on the exposed shoreline during the drawdown have been flooded and much of the pre-drawdown Par Pond aquatic plant communities have not had sufficient time for re-establishment. The shoreline does, however, have extensive beds of maidencane which extend from the shoreline margin to areas as deep as 2 and perhaps 3 meters. Scattered individual plants of lotus and watershield are common and may indicate likely directions of future wetland development in Par Pond. In addition, within isolated coves, which apparently received ground water seepage and/or stream surface flows during the period of the Par Pond draw down, extensive beds of waterlilies and spike rush are common. Invasion of willow and red maple occurred along the lake shoreline as well. Although not absent from this survey, evidence of the extensive redevelopment of the large cattail and eel grass beds was not observed in this first survey of Par Pond. Future surveys during the growing seasons of 1995, 1996, and 1997 along with the evaluation of satellite date to map the areal extent of the macrophyte beds of Par Pond are planned

  3. 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

  4. Par Pond vegetation status Summer 1995 -- September survey descriptive summary

    International Nuclear Information System (INIS)

    Mackey, H.E. Jr.; Riley, R.S.

    1995-09-01

    The water level of Par Pond was lowered approximately 20 feet in mid-1991 in order to protect downstream residents from possible dam failure suggested by subsidence on the downstream slope of the dam and to repair the dam. This lowering exposed both emergent and nonemergent macrophyte beds to drying conditions resulting in extensive losses. A survey of the emergent shoreline aquatic plant communities began in June 1995, three months after the refilling of Par Pond to approximately 200 feet above mean sea level and continued with this mid-September survey. Communities similar to the pre-drawdown Par Pond aquatic plant communities are becoming re-established; especially, beds of maidencane, lotus, waterlily, and watershield are now extensive and well established. Cattail occurrence continues to increase, but large beds common to Par Pond prior to the drawdown have not formed. Future surveys during the late growing seasons of 1995, and throughout 1996 and 1997, along with the evaluation of satellite data to map the areal extent of the macrophyte beds of Par Pond, are planned

  5. Par Pond vegetation status Summer 1995 -- October survey descriptive summary

    International Nuclear Information System (INIS)

    Mackey, H.E. Jr.; Riley, R.S.

    1995-11-01

    The water level of Par Pond was lowered approximately 20 feet in mid-1991 in order to protect downstream residents from possible dam failure suggested by subsidence on the downstream slope of the dam and to repair the dam. This lowering exposed both emergent and nonemergent macrophyte beds to drying conditions resulting in extensive losses. A survey of the emergent shoreline aquatic plant communities began in June 1995, three months after the refilling of Par Pond to approximately 200 feet above mean sea level and continued with this late October survey. Communities similar to the pre-drawdown Par Pond aquatic plant communities are becoming re-established; especially, beds of maiden cane, lotus, waterlily, and watershield are now extensive and well established. Cattail occurrence continues to increase, but large beds common to Par Pond prior to the drawdown have not formed. Future surveys throughout 1996 and 1997, along with the continued evaluation of satellite data to map the areal extent of the macrophyte beds of Par Pond, are planned

  6. Special metallurgy - the electrical butt-welding by flashing of sintered magnesium-magnesium oxide composites (1963); Metallurgie speciale - le soudage electrique en bout par etincelage du composite fritte magnesium-magnesie (1963)

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-07-01

    Electrical resistance welding has become quite important since World War II because of the need of a high yield in aeronautical production. Progress has been due in particular to the improvements made in electronically controlled apparatus making possible the automatic control of welding. For the butt-welding of sections requiring either a high production rate or a high quality weld, the flash butt-welding system has been very much developed these last few years. The use of this welding method is of great importance in the field of the bonding of oxidisable metals such as magnesium or aluminium and its alloys, because the welded joint is free from oxides. This study consists of general considerations on the flash-welding process with regard to temperature distribution in the parts during welding, and to electrical phenomena connected with flashing. Besides this general or theoretical section, we have applied the welding process to the bonding of sintered magnesium, a magnesium-magnesium oxide composite, whose use as a structural element in nuclear reactors is considered. (author) [French] Le soudage electrique par resistance a pris un essor important depuis la derniere guerre mondiale a cause du besoin de haut rendement pour la production aeronautique. Les progres ont ete possibles surtout par l'amelioration des appareils de commande electronique qui permettent un controle automatique de la soudure. Pour le soudage bout a bout de profiles, demandant soit un haut debit de fabrication, soit une haute qualite du joint soude, le procede de soudage en bout par etincelage a ete tres developpe ces dernieres annees. Ce mode de soudage a un domaine d'utilisation important dans la liaison des metaux oxydables tels le magnesium ou l'aluminium et ses alliages, du fait de la proprete du joint soude exempt d'oxydes. Cette etude comporte une consideration generale du processus de l'etincelage, quant a la repartition de la temperature dans les pieces pendant le soudage et aux

  7. Special metallurgy - the electrical butt-welding by flashing of sintered magnesium-magnesium oxide composites (1963); Metallurgie speciale - le soudage electrique en bout par etincelage du composite fritte magnesium-magnesie (1963)

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-07-01

    Electrical resistance welding has become quite important since World War II because of the need of a high yield in aeronautical production. Progress has been due in particular to the improvements made in electronically controlled apparatus making possible the automatic control of welding. For the butt-welding of sections requiring either a high production rate or a high quality weld, the flash butt-welding system has been very much developed these last few years. The use of this welding method is of great importance in the field of the bonding of oxidisable metals such as magnesium or aluminium and its alloys, because the welded joint is free from oxides. This study consists of general considerations on the flash-welding process with regard to temperature distribution in the parts during welding, and to electrical phenomena connected with flashing. Besides this general or theoretical section, we have applied the welding process to the bonding of sintered magnesium, a magnesium-magnesium oxide composite, whose use as a structural element in nuclear reactors is considered. (author) [French] Le soudage electrique par resistance a pris un essor important depuis la derniere guerre mondiale a cause du besoin de haut rendement pour la production aeronautique. Les progres ont ete possibles surtout par l'amelioration des appareils de commande electronique qui permettent un controle automatique de la soudure. Pour le soudage bout a bout de profiles, demandant soit un haut debit de fabrication, soit une haute qualite du joint soude, le procede de soudage en bout par etincelage a ete tres developpe ces dernieres annees. Ce mode de soudage a un domaine d'utilisation important dans la liaison des metaux oxydables tels le magnesium ou l'aluminium et ses alliages, du fait de la proprete du joint soude exempt d'oxydes. Cette etude comporte une consideration generale du processus de l'etincelage, quant a la repartition de la temperature dans les pieces

  8. The controlled of the materials by the method of oscillation at the reactor core of Chatillon; Le controle des materiaux par la methode d'oscillation a la pile de Chatillon

    Energy Technology Data Exchange (ETDEWEB)

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

    1955-07-01

    Nuclear controls has for aim to determine the validity of materials intended to be used for the construction of the reactor core. The cross-section of capture of these materials has to be measured while comparing them either to a standard of the same material, either to an element of cross-section supposed known. We studied the disruption of the working of the reactor generated by the periodic introduction of a sample of the studied material. This method is based on the measure of the phase angle of the signal provided by the ionization chamber. This signal results from the composition of a local signal and an aggregate signal due to the effects of diffusion and capture. This method permits the comparison of the capture of 2 samples very dispersive and few capturing as the graphite, the beryllium, the beryllium oxide, with a good precision. It permits to determine the cross-section of capture of elements as magnesium or aluminum. (M.B.) [French] Le controle nucleaire a pour but de determiner la valeur des materiaux destines a etre utilises pour la construction des piles. II s'agit de mesurer la section efficace de capture de ces materiaux en les comparant soit a un echantillon etalon du meme materiau, soit a un element de section efficace supposee connue. On etudie la perturbation du fonctionnement de la pile engendree par l'introduction periodique d'un echantillon du materiau a etudier. Cette methode est basee sur la mesure de l'angle de phase du signal fourni par la chambre d'ionisation. Ce signal resulte de la composition d'un signal local et d'un signal global dus aux effets de diffusion et de capture. Cette methode permet la comparaison de la capture de 2 echantillons de corps tres diffusants et peu capturants comme le graphite,le beryllium, l'oxyde de beryllium, avec une bonne precision. Elle permet par ailleurs de determiner la section efficace de capture de corps tels que le magnesium ou l'aluminium. (M.B.)

  9. Contribution to the study and use of ionisation chambers for nuclear reactor control (1965); Contribution a l'etude et a l'utilisation des chambres d'ionisation pour le controle des reacteurs nucleaires (1965)

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-02-15

    high-power reactors. (author) [French] Les chambres d'ionisation sont actuellement les detecteurs les mieux adaptes au controle des reacteurs nucleaires par des mesures neutroniques. Nous avons cru bon de rappeler quelques generalites concernant la dynamique des reacteurs, les differents procedes de detection des neutrons, le fonctionnement des chambres d'ionisation et les methodes de mesure utilisees. Notre contribution aux techniques de controle des reacteurs consiste d'une part en une tentative de synthese des facteurs intervenant dans le fonctionnement des chambres d'ionisation, l'etude de ces facteurs, et d'autre part l'elaboration de chambres d'ionisation a fission et a bore permettant de suivre la marche d'un reacteur du demarrage jusqu'a la puissance maximale. Dans le domaine des chambres a fission, nous avons en particulier ameliore les techniques de depot d'oxyde d'uranium sur l'aluminium et realise la mise au point de depots par electrolyse sur d'autres metaux: acier inoxydable, cuivre, molybdene, nickel, tantale, titane, kovar, tungstene et beryllium. Nous avons elabore plusieurs types de chambres a fission servant au demarrage des reacteurs: un type de performances moyennes actuellement utilise dans les piles francaises un type a haute sensibilite un type a haute temperature qui a fonctionne jusqu'a 600 deg. C. En ce qui concerne les chambres a bore, nous avons etudie les perturbations apportees dans les mesures par l'exposition des chambres a d'importants flux de neutrons et a un rayonnement {gamma} intense. Cette exposition produit une modification des proprietes des materiaux constitutifs et la production dans les chambres d'un bruit de fond qui peut gener considerablement les mesures neutroniques. Nous avons montre que la technique de compensation permettait de limiter l'importance de ce bruit de fond et d'augmenter ainsi la plage de fonctionnement des chambres d'ionisation classiques destinees aux mesures de puissance. Enfin, nous avons realise deux

  10. Resonance absorption of nuclear gamma radiation; Absorption par resonance des rayons gamma; Rezonansnaya absorbtsiya i rasseyanie yadernogo gamma-izlucheniya; Absorcion por resonancia de las radiaciones gamma en los nucleos

    Energy Technology Data Exchange (ETDEWEB)

    Hanna, S S; Perlow, G J [Argonne National Laboratory, Argonne, IL (United States)

    1962-01-15

    Recoilless emission and absorption of nuclear radiation, as demonstrated by Moessbauer, provides a simple means of studying the interaction of nuclei with electromagnetic radiation and, of greater importance, provides an extremely sensitive tool for the investigation of a large number of physical problems. A very favourable situation arises with the Fe{sup 57} nucleus where resonance absorption may be used as a very sensitive detector of the frequency change of electromagnetic radiation. Resonance absorption in Fe57 has been studied in detail. The strength of the absorption, the line shape, and line shift have all been observed as a function of temperature. The polarization of the radiation has been examined by means of experiments with magnetized sources and absorbers. The hyperfine spectrum of the resonance radiation has been analysed with and without polarization. These studies have led to an interpretation of the hyperfine structure in terms of the properties of the nuclear states and the hyperfine interaction in iron. The effect of an external magnetic field on the hyperfine structure has also been investigated. The resonance absorption in Fe{sup 57} has been used to study the connexion between the time development of the decay of a nuclear state and the spectrum of the observed radiation. Detailed observations are made of the time spectrum of filtered resonance radiation for a variety of conditions. (author) [French] L'emission et l'absorption de rayonnements nucleaires sans recul, phenomenes mis en evidence par Mossbauer, offrent un moyen simple d'etudier l'interaction des noyaux et des rayonnements electromagnetiques et, ce qui est plus important encore, fournissent un instrument extremement sensible pour l'etude d'un grand nombre de problemes de physique. Une situation tres favorable se presente dans le cas du noyau de {sup 57}Fe, ou l'on peut utiliser l'absorption par resonance comme un detecteur tres sensible des changements de frequence des rayonnements

  11. [Ambroise Paré, his death and his historians].

    Science.gov (United States)

    Dumaître, P

    2001-01-01

    Ambroise Paré died December the 20th., 1590. What happened after his death and what are we knowing about his life? Never forgotten, though a lack of care, we were waiting till the XIXth. century to get recollection upon a subject sustained only by accounts of his travels. After Percy, a surgeon who tried to write Paré's biography through the "Biographie universelle ancienne et moderne, de Michaud (1822)" and some second rank authors, Malgaigne is the first who inside a printing of the "Oeuvres complétes de Paré (1840-41)" has a fine look upon the question, though his work is incomplete and allows many mistakes. Doctors Chéreau and Jal, an historian, analysing civil status records, gave new information enlarged by doctors Le Paulmier, Turner and the U.S. native Janet Doe.

  12. Keratometric alterations following the 25-gauge transconjunctival sutureless pars plana vitrectomy versus the conventional pars plana vitrectomy.

    Science.gov (United States)

    Citirik, Mehmet; Batman, Cosar; Bicer, Tolga; Zilelioglu, Orhan

    2009-09-01

    To assess the alterations in keratometric astigmatism following the 25-gauge transconjunctival sutureless pars plana vitrectomy versus the conventional pars plana vitrectomy. Sixteen consecutive patients were enrolled into the study. Conventional vitrectomy was applied to eight of the cases and 25-gauge transconjunctival sutureless vitrectomy was performed in eight patients. Keratometry was performed before and after the surgery. In the 25-gauge transconjunctival sutureless pars plana vitrectomy group, statistically significant changes were not observed in the corneal curvature in any post-operative follow-up measurement (p > 0.05); whereas in the conventional pars plana vitrectomy group, statistically significant changes were observed in the first postoperative day (p = 0.01) and first postoperative month (p = 0.03). We noted that these changes returned to baseline in three months (p = 0.26). Both 25-gauge transconjunctival sutureless and conventional pars plana vitrectomy are effective surgical modalities for selected diseases of the posterior segment. Surgical procedures are critical for the visual rehabilitation of the patients. The post-operative corneal astigmatism of the vitrectomised eyes can be accurately determined at least two months post-operatively.

  13. New Frontiers for Non-Destructive Testing in the Nuclear Age; Perspectives des Essais Non Destructifs a l'Ere Nucleaire; ''Novye rubezhi'' nedestruktivnykh ispytanij v yadernyj vek; Nuevas Posibilidades de los Ensayos No Destructivos en la Era Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Ballard, D. W. [Sandia Laboratory Albuquerque, NM (United States)

    1965-10-15

    suitable for remote television displays and recording. Test parameters, display capabilities, and continuous monitoring systems are discussed. These possibilities have. already been demonstrated in laboratory testing and their use must be extended to production testing if a new level of reliability of components in the nuclear industry is to be achieved. (author) [French] On peut attribuer en grande partie l'extraordinaire developpement des essais non destructifs depuis la deuxieme guerre mondiale aux specifications extremement strictes imposees aux materiaux et produits de l'industrie nucleaire. La complexite des installations et de leurs elements et les incidences financieres des arrets de fonctionnement ont atteint des proportions telles qu'il est imperieux de mettre au point des methodes plus efficaces d'essais non destructifs et de les appliquer tout au long de la duree de vie des produits, depuis leur mise en fabrication jusqu'a leur declassement. En meme temps que, pour tenter de satisfaire aux imperatifs techniques de perfection, on developpe considerablement les possibilites offertes par des methodes d'essais confirmees, comme la radiographie, les ultrasons et l'electromagnetisme, on met au point de nouveaux principes d'essais destines expressement au controle des performances statiques et dynamiques. Le memoire porte sur ces methodes particulierement rapides et sensibles qui ouvrent vraiment de nouvelles perspectives aux essais non destructifs. Au nombre des methodes d'essais les plus recentes discutees dans le memoire figure le controle par les infra- rouges de l'integrite des soudures. Le controle cineradiographique des structures au cours des essais de vibration, pour etudier leur comportement dynamique, est egalement traite. La detection des fuites est extremement importante pour assurer la qualite des elements combustibles. Le memoire decrit une methode de controle des elements combustibles sous gaine, qui est fondee sur l'utilisation d'un gaz radioactif et

  14. Cyclanthaceae no estado do Pará, Brasil Cyclanthaceae in Pará State, Brazil

    Directory of Open Access Journals (Sweden)

    Eduardo da Silva Leal

    2012-12-01

    Full Text Available Cyclanthaceae apresenta distribuição exclusiva na região neotropical sendo bem diversificada nas terras baixas das florestas pluviais tropicais, ocorrendo do sul do México até a Mata Atlântica do sul do Brasil. Consistem de ervas terrestres, epífitas, hemiepífitas ou lianas. O tratamento taxonômico de Cyclanthaceae no Pará foi baseado em coleções de herbário, trabalhos de campo e consulta a bibliografia referente à família. Foram registradas 11 espécies: Asplundia altiscandens E.S. Leal, A. fanshawei (Maguire Harling, A. glandulosa (Gleason Harling, A. heteranthera Harling, A. latifrons (Drude Harling, A. schizotepala Harling, A. xiphophylla Harling, Cyclanthus bipartitus Poit. ex A. Rich., Evodianthus funifer (Poit. Lindm., Ludovia lancifolia Brongn. e Thoracocarpus bissectus (Vell. Harling. São apresentadas chave de identificação, descrições e ilustrações das espécies, além de comentários sobre distribuição geográfica, hábitat e período de floração e frutificação.Cyclanthaceae is a family with a distribution exclusively in the Neotropics and is well diversified in lowland rainforests, occurring from southern Mexico to the Atlantic Forest of southern Brazil. The family consists of terrestrial herbs, epiphytes, hemiepiphytes and lianas. This taxonomic treatment of the Cyclanthaceae from the state of Pará was based on herbarium specimens, fieldwork, and the literature. Eleven species were recorded: Asplundia altiscandens E.S. Leal, A. fanshawei (Maguire Harling, A. glandulosa (Gleason Harling, A. heteranthera Harling, A. latifrons (Drude Harling, A. schizotepala Harling, A. xiphophylla Harling, Cyclanthus bipartitus Poit. ex A. Rich., Evodianthus funifer (Poit. Lindm., Ludovia lancifolia Brongn. and Thoracocarpus bissectus (Vell. Harling. An identification key, descriptions and illustrations of species are presented. Additional information on the geographic distribution, habitat, and flowering and

  15. Canning by the diffusion caused by a heated die; Gainage par diffusion par filiere chauffante

    Energy Technology Data Exchange (ETDEWEB)

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

    1959-07-01

    In this process, the uranium fuel is clad with a zirconium can by passing the element through a die. The operation takes place at a temperature varying between 500 and 1000 deg. C. The heating is obtained by passing low voltage electric current through the can. This process differs from the co-extrusion process in that the uranium is not deformed. The uranium is therefore machined to the final dimensions before canning, it can also be hollow. Two types of processes can be adopted for the extrusion: a) Process in which the binding of the can to the uranium is obtained without diffusion (here the can is at high temperature - subsequently cooled - and the uranium is at a low temperature); b) Process in which uranium-zirconium diffusion is initiated. No matter which process is adopted the element is subsequently heat treated in an over at 800 deg. C in order to obtain the final diffusion. The quality of this diffusion is dependent on the initial state of the surfaces and on the degree of vacuum maintained during the operation. (author) [French] Dans ce procede, la gaine zirconium est plaquee sur le combustible uranium par passage dans une filiere. L'operation a lieu a chaud, a une temperature variant entre 500 et 1000 deg. C. Le chauffage est assure par passage d'un courant basse tension dans la gaine. A la difference du procede de cofilage, l'uranium ne subit pas de deformation durant l'operation. Il est donc prealablement usine aux cotes definitives et peut etre creux. Deux processus sont possibles pendant le passage dans la filiere: a) Obtention d'un frettage de la gaine sur l'uranium sans diffusion (avec une gaine a haute temperature et un tube d'uranium a basse temperature, eventuellement refroidi); b) Obtention d'un commencement de diffusion uranium-zirconium. Quelque soit le processus adopte, la cartouche est ensuite traitee dans un four a 800 deg. C pour obtenir la diffusion definitive. La qualite de celle-ci depend essentiellement des etats de surface initiaux

  16. La projection par plasma : une revue

    Science.gov (United States)

    Fauchais, P.; Grimaud, A.; Vardelle, A.; Vardelle, M.

    are presented in the fields of aeronautics and mechanics. La qualité d'un dépôt projete par plasma dépend de nombreux paramètres que l'on commence à mieux appréhender du fait des progrès de la modélisation et de la métrologie tant des écoulements plasmas que des transferts plasma-particules ou que des conditions d'écrasement et de refroidissement des particules lors de leur impact sur le substrat ou les couches déjà déposées. Les techniques de mesure utilisdes et leurs limitations sont d'abord rappelées tant pour les jets de plasma que pour les particules en vol et l'importance des différents phénomènes intervenant dans les transferts plasma-particules est soulignée : gradients de température et de concentration d'espèces chimiques très élevés autour des particules, effets de propagation de la chaleur, notamment pour les particules céramiques, effet d'évaporation, effet de raréfaction sensible dès la pression atmosphérique. Les problèmes de distribution de taille et de vitesse d'injection des particules sont également abordés car ils conditionnent les distributions de trajectoires et donc le traitement des particules dans le jet de plasma. La génération du plasma montre d'une part 1'influence considérable de l'injection du gaz, de sa nature, du dessin de la chambre d'arc et de la tuyère ainsi que du pompage de l'air ambiant sur la longueur des jets de plasma d'arc et d'autre part les problèmes d'injection pour éviter le couplage avec la décharge dans les jets de plasmas R.E Tout ceci est illustré avec des exemples de dépôt d'alumine, de zircone, de cermet carbure et de nickel. L'écrasement des particules est ensuite abordé avec les problèmes de réactions chimiques, de trempe ultra-rapide et donc de structure cristalline des dépôts, d'adhdsion mais aussi de containtes résiduelles et de leur contrôle via les gradients de température dans les dépôts pendant le tir. Enfin quelques applications actuelles sont pr

  17. Hydrogen production by water dissociation from a nuclear reactor; Production d'hydrogene par dissociation de l'eau a partir d'un reacteur nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-07-01

    This memento presents the production of hydrogen by water decomposition, the energy needed for the electrolysis, the thermochemical cycles for a decomposition at low temperature and the possible nuclear reactors associated. (A.L.B.)

  18. Quantification of ion or atom transfer phenomena in materials implanted by nuclear methods; Quantification de phenomenes de transferts ioniques ou atomiques dans des materiaux implantes par la mise en oeuvre de methodes nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Oudadesse, Hassane [Clermont-Ferrand-2 Univ., 63 - Aubiere (France)

    1998-05-18

    Knowledge of transfer of the constituents of a system from regions of higher to lower concentration is of interest for implanted bio-materials. It allows determining the rate at which this material is integrated in a living material. To evaluate the ossification kinetics and to study the bio-functionality in corals of Ca and Sr, irradiations with a 10{sup 13} n.cm{sup -2}.s{sup -1} was performed, followed by the examination of changes in the localization of these elements. By using PIXE analysis method the distribution of Ca, P, Sr, Zn and Fe in the implant, bone and bone-implant interfaces were determined. Thus, it was shown that resorption of coral in sheep is achieved in 5 months after implantation and is identical to the cortical tissues 4 months after implantation in animals as for instance in hares. We have analyzed the tissues from around the prostheses extracted from patients. The samples were calcined and reduced to powder weighting some milligrams. We have adopted for this study the PIXE analysis method. The samples were irradiated by a proton beam of 3 MeV and about 400 {mu}m diameter. The results show the presence of the elements Ti, Fe, Cr, Ni or Zn according to the type of the implanted prosthesis. This dispersal of the metallic ions and atoms contaminate the tissues. The transfer factors translate the exchanges between bone and the implanted material. The solvatation phenomenon and the electric charge equilibrium explain the transfer order of cations Mg{sup 2+}, Ca{sup 2+} and Sr{sup 2+} and of the anion PO{sub 4}{sup 3-}. We have also determined these factors for the elements Ti, Cr and Ni. An original technique to study the bone bio-functionality was used. Use of phosphate derivatives labelled by {sup 99m}Tc allows obtaining information about the fixation of radioactive tracer. It was found that only after the eighth month at the implantation the neo-formed bone fixes the MDP (methyl diphosphate) labelled by {sup 99m}Tc in a similar way as in the control sample. Starting from this moment the implanted coral becomes bio-functional and it is identified by this type of molecule 100 refs., 48 figs., 29 tabs.

  19. Convention on Nuclear Safety. Second national report on the implementation by france of the obligations of the Convention; Convention sur la surete nucleaire. Deuxieme rapport national sur la mise en oeuvre par la France des obligations de la Convention

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-09-15

    The first national report on the implementation by france of the obligation under the Convention is structured along its Articles. the french Nuclear safety Authority ensured the co ordination of the report, with contributions from other regulators and nuclear operators. this report was distributed at the middle of April 2003 to the other Contracting party (on 3 november to 14, 2003 at the IAEA headquarters. (author)

  20. Purification by molecular sieve of helium used as inert cover gas in nuclear reactors; Epuration de l'helium de couverture des reacteurs nucleaires par adsorption sur tamis moleculaire

    Energy Technology Data Exchange (ETDEWEB)

    Rozenberg, J; Kahan, H [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1967-07-01

    A method carried out at fairly low temperatures (between -50 and -80 deg. C) has been studied for the purification of the helium used as cover gas for heavy water in reactors. The use of the 5A molecular sieve has been adopted because of its superiority over other adsorbents in this temperature range. The particular problems connected with adsorption under dynamic conditions have been dealt with separately. The nitrogen adsorption isotherms have been plotted and the heat of adsorption calculated. (authors) [French] Une methode d'epuration, a temperature moderement basse (comprise entre -50 et -80 deg. C) de l'helium servant de couverture inerte a l'eau lourde des reacteurs a ete etudiee. L'emploi au tamis moleculaire 5A a ete retenu pour la superiorite de celui-ci sur d'autres adsorbants dans ce domaine de temperatures. Les problemes particuliers a l'adsorption en regime dynamique ont ete separement traites. Les isothermes d'adsorption d'azote ont ete tracees et la chaleur d'adsorp. tion calculee. (auteurs)

  1. Doping influence by some transition elements on the irradiation effects in nuclear waste glasses; Influence du dopage par certains elements de transition sur les effets d'irradiation dans des verres d'interet nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Florent, Olivier

    2006-06-15

    High-level waste glasses are submitted to auto-irradiation. Modelling it using external irradiations on simple glasses revealed defects production and non negligible structural changes. This thesis aims at determining the impact of a more complex composition on these effects, especially the influence of adding polyvalent transition metals. Silicate, soda-lime and alumino-borosilicate glasses are doped with different iron, chromium and manganese concentrations then {beta} irradiated at different doses up to 10{sup 9} Gy. Non doped glasses show an increase of their density and polymerisation coupled with a molecular oxygen and point defects production. Adding 0.16 mol% Fe decreases the amount of defects by 85 % and all irradiation effects. A Fe{sup 3+} reduction is also observed by EPR, optical absorption and indirectly by Raman spectroscopy. A higher than 0.32 mol% Fe concentration causes complete blockage of the evolution of polymerisation, density and defect production. The same results are obtained on chromium or manganese doped glasses. An original in situ optical absorption device shows the quick decrease of Fe{sup 3+} amount to a 25 % lower level during irradiation. Stopping irradiation causes a lower decrease of 65 %, suggesting a dynamic (h{sup 0}/e-) consuming equilibrium. He{sup +} and Kr{sup 3+} ions and {gamma} irradiated glasses tend to confirm these phenomena for all kind of irradiation with electronic excitations. (author)

  2. Stress corrosion cracking in the vessel closure head penetrations of French PWR`s; Fissuration par corrosion sous contrainte de penetrations de couvercle de cuve de reacteur nucleaire francais a eau pressurisee

    Energy Technology Data Exchange (ETDEWEB)

    Buisine, D.; Cattant, F.; Champredonde, J.; Pichon, C.; Benhamou, C.; Gelpi, A.; Vaindirlis, M.

    1994-01-01

    During a hydrotest in September 1991, part of the statutory decennial in-service inspection, a leak was detected on the vessel head of Bugey 3, which is one of the first 900 MW 3-loop PWR`s in France. This leak was due to a cracked penetration used for a control rod drive mechanism. The investigations performed identified Primary Stress Corrosion Cracking of Alloy 600 as being the origin of this degradation. So a lot of the same design PWR`s are a concern due to this generic problem. In this case, PWSCC was linked to: - hot temperature of the vessel head; - high residual stresses due to the welding process between peripherical penetrations and the vessel head; - sensitivity of forged Alloy 600 used for penetration manufacturing. This following paper will present the cracked analysis based, in particular, on the main results obtained in France on each of these items. These results come from the operating experience, the destructive examinations and the programs which are running on stress analysis and metallurgical characterizations. (authors). 9 figs., 2 tabs.

  3. Integrated approach of the metabolism and the muscle perfusion in imaging and magnetic resonance spectroscopy; Approche integree du metabolisme et de la perfusion musculaire en imagerie et spectroscopie par resonance magnetique nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Brillault-Salvat, C

    1997-12-16

    Oxygen is necessary to the tissue life. Every step from its transport of the ambient medium to its consumption by cells are essential to the right functioning of organism. The involved phenomena are complex and use numerous different mechanisms. In order to better understand the functioning, it has been developed a non traumatic, non irradiating and quantitative method that allows to measure in the same time several determinants of the tissue oxygenation. (N.C.)

  4. Measuring fission lifetimes with the crystal-blocking technique in mono-crystal, access to nuclear dissipation; Mesures de temps de fission par la technique d'ombre dans les monocristaux: un acces a la dissipation nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Basnary, St

    2002-10-01

    Energy dissipation in nuclear matter may play an important role in the determination of the way through which heavy nuclei des-excite: fission or particle evaporation. An important dissipation should imply longer interval of time during which the nucleus is deformed. In that way the measurement of fission lifetimes may shed light on energy dissipation, but these measurements are very delicate to perform. Most available data on deformation times come from indirect measurements combined with the use of more or less valid models. The crystal-blocking lifetime technique in mono-crystals allows the direct measurement of long fission lifetimes. This technique has been applied to different nuclei situated in the proximity of lead. We have obtained relatively high values: {tau} > 3.10{sup -19} s for both lead and uranium which implies a strong dissipation of energy. The computation of dissipation coefficients has led to the following values: {beta} {approx_equal} 2.10{sup 21} /s for lead and {beta} {>=} 6.10{sup 21} /s for uranium (E{sup *} > 120 MeV). These results show that dissipation effects have to be taken into account in the determination of the deexcitation way. (A.C.)

  5. The thyroid protection in case of nuclear accident by an iodine prophylaxis; La protection de la thyroide en cas d'accident nucleaire par une prophylaxie a l'iode

    Energy Technology Data Exchange (ETDEWEB)

    Carrera, F

    2004-12-15

    The first part of the thesis describes the thyroid functional activity and the place of iodine in organisms, iodine is linked to the thyroid functioning. The second part of the thesis is interested in the ionizing radiation effect in general then on the thyroid. The external irradiation has been essentially studied from the data of the Hiroshima and Nagasaki explosions. The internal contamination of thyroid is known by the use of {sup 131}iodine for medical or diagnostic uses. A mixed contamination is described with the example of the nuclear test in Marshall Islands. Follows a chapter devoted to the thyroid cancers, the most serious thyroid radioinduced pathology. The third part concerns the place of iodine in the nuclear power plants. The functioning of a nuclear power plant is described as well as its radioactive emission in normal operation and in accidental situation. The sanitary impact of a radioactive iodine emission is detailed from a bibliographic synthesis coming from the studies on the development of thyroid cancers appeared after the Chernobylsk disaster. The ingestion of steady iodine constitutes an preventive measure efficient against the arising of these cancers. Its efficiency and innocuousness are discussed. Then a last part summarizes the administrative measures taken in France so that the population can have at her disposal iodine tablets before and in case of accidents. (N.C.)

  6. Report on the environmental and sanitary impacts of the nuclear tests performed by France between 1960 and 1996 and elements of comparison with the tests performed by the other nuclear Powers; Rapport sur les incidences environnementales et sanitaires des essais nucleaires effectues par la France entre 1960 et 1996 et elements de comparaison avec les essais des autres puissances nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Bataille, Ch; Revol, H

    2002-07-01

    This report makes a comprehensive presentation of the French atmospheric and underground nuclear tests performed in Sahara and Polynesia between 1960 and 1996 with their possible impact on the health of populations and personnel and on the environment. A comparison is made with similar tests performed by other nuclear Powers: US (Marshall islands, Nevada), former Soviet union (Semipalatinsk, Novaya Zemlya), UK (several atmospheric test-sites), China, India, Pakistan. (J.S.)

  7. Possibilities of long duration generation of vapour of iodine 131 in the air for its trapping in French activated carbons; Possibilites de generation de longue duree dans l'air de vapeur d'iode 131 en vue de son piegeage par les charbons actifs francais

    Energy Technology Data Exchange (ETDEWEB)

    Billard, F.; Chevalier, G.; Pradel, J.

    1962-12-17

    As previous studies performed on activated carbon showed that it was necessary to possess a long duration iodine generator to determine the scope of application of some advanced theories concerning the trap mechanism of different forms of radio-iodines, the authors present a generator which uses the high temperature oxidation of sodium iodide by an air stream or an oxygen stream. A version of this apparatus using a 5 Curie source is planned to check the operation of a trap of 100.000 m{sup 3}/h with a purification coefficient of 10{sup 4}, and aimed at being mounted on the venting circuit of a nuclear reactor enclosure [French] Les etudes que nous avons effectuees sur les charbons actifs nous ont montre qu'il etait necessaire de posseder un generateur d'iode de longue duree pour preciser le domaine d'application de certaines theories avancees concernant le mecanisme de piegeage des differentes formes de radioiodes. Un generateur utilisant l'oxydation de l'iodure de sodium a chaud par un courant d'air ou d'oxygene est decrit. Une version de cet appareil utilisant une source de 5 curies est prevue pour verifier le bon fonctionnement d'un piege de 100.000 m{sup 3}/h ayant un coefficient d'epuration de 10{sup 4} est destine a etre place sur le circuit de ventilation de l'enceinte d'un reacteur nucleaire. (auteurs)

  8. Radiant-Heat Spray Calcination Studies; Calcination par Pulverisation et Chauffage Radiant; 0418 0421 0421 041b 0415 0414 041e 0412 0410 041d 0418 042f 041d 0410 041a 0410 041b 042c 0426 0418 041d 0410 0422 041e 0420 0410 0425 0424 041e 0420 0421 0423 041d 041e 0427 041d 041e 0413 041e 0422 0418 041f 0410 0421 041d 0410 0413 0420 0415 0412 0410 041d 0418 0415 041c 0422 0415 041f 041b 041e 0412 042b 041c 0418 0417 041b 0423 0427 0415 041d 0418 0415 041c ; Estudios de Calcinacion por Pulverizacion y Calentamiento Radiante

    Energy Technology Data Exchange (ETDEWEB)

    Allemann, R. T.; Moore, R. L.; Upson, U. L. [Hanford Laboratories General Electric Co., Richland, WA (United States)

    1963-02-15

    The radiant-heat spray calcination process for conversion of liquid wastes to solids is described and the design of a one-gallon-per-hour spray calcination unit coupled with a small melt pot, capable of being run separately as a pot calciner, is discussed. The units were designed to test the feasibility of the calcination process with actual Purex plant waste in terms of the process as a unit operation, off-gas treatment, fission-product behaviour, condensate and calcined waste characteristics. The entire system was made to fit into an available 7-1/2 ft x 15 ft x 15 ft tall, manipulator-equipped, shielded cell which is also described. Included in the design discussion are: the resistance heating of the spray calciner column, thermal insulation of the column, spray nozzle, method of nozzle replacement, induction heating of the melt pot, radioactivity scanner for the pot, off-gas processing system including condenser, scrubber and filters, off-gas sampling device, liquid sampling device, wash-down system, feed system, instrumentation and control methods. The experience gained in operating the calciners and associated equipment is discussed. Experimental results presented show the effectiveness of off-gas decontamination and behaviour of gross chemical constituents and some specific fission products. (author) [French] Les auteurs etudient le procede de calcination par pulverisation et chauffage radiant utilise pour transformer les dechets liquides en solides; ils decrivent notamment une installation de calcination par pulverisation (d'une capacite de 1 gallon par heure) accouplee a un petit creuset que l'on peut utiliser separement comme creuset de calcination. Cet ensemble- a ete concu pour etudier la possibilite de calciner des dechets reels resultant du traitement Purex, en tenant compte des facteurs suivants: operations dans un seul appareil, traitement des gaz d'echappement, comportement des produits de fission, caracteristiques du condense et des dechets

  9. Parasitisme de Dacryodes edulis par le genre Tapinanthus ...

    African Journals Online (AJOL)

    SARAH

    31 août 2013 ... Parasitisme de Dacryodes edulis par le genre. Tapinanthus (Loranthaceae) et répartition de la myrmécofaune associée à Logbessou Plateau. (Douala, Cameroun). Massako F1*, Tchatat M2, Mony R3, Ladoh Yemeda CF1, Dibong SD1,4,5. 1Laboratoire de Biologie et Physiologie des Organismes ...

  10. Parasitisme des champs semenciers de cacaoyers par les ...

    African Journals Online (AJOL)

    SARAH

    30 janv. 2015 ... J. Appl. Biosci. Parasitisme des champs semenciers de cacaoyers par les loranthaceae dans la localité de Nkoemvone (sud Cameroun). 7795 to the various clones, Phragmanthera capitata was the most abundant Loranthaceae; the level of parasitism of cacao trees is more important at the cacao trees of ...

  11. Den eneste ene - hvordan etniske minoritetsunge i Danmark danner par

    DEFF Research Database (Denmark)

    Singla, Rashmi

    Rapporten handler om etniske unges måde at danne par på. Rapporten er baseret på en større empirisk undersøgelse gennemført af forfatteren i 2003 og er desuden inspireret af forfatterens egen ph.d.-afhandling: "Ungdom, etnicitet og psychosocial intervention" (2000, Københavns Universitet). Rappor...

  12. Indications and visual outcome of first hundred pars plana ...

    African Journals Online (AJOL)

    Objective: To review the indications and visual outcome of the first one hundred pars plana vitrectomies performed at the newly established surgical retina unit of Makkah Specialist Eye Hospital, Kano, Kano State, Nigeria. Materials and Methods: Aretrospective chart review was performed. Data recorded from the patient ...

  13. Epuration des effluents industriels par électroflottation Belkacem ...

    African Journals Online (AJOL)

    étudié la séparation de quelques métaux lourds tels que le fer, le nickel, ... the separation of some heavy metals such as iron, nickel, copper, zinc, lead and ... généralement basées sur l'adsorption (par ... Différents essais de concentration en.

  14. Predicting spectral and PAR light attenuation in Greenlandic coastal waters

    DEFF Research Database (Denmark)

    Murray, Ciarán; Markager, Stiig; Stedmon, Colin

    (CDOM), phytoplankton pigments and inorganic particles. These differences are due in part to hydrography and to the sources of meltwater: respectively, fjord-terminating and land-terminating glaciers. We present a model to explain the variation in spectral and PAR irradiance in terms of the variation...

  15. Priapisme induit par la chlorpromazine: A propos de deux cas

    Directory of Open Access Journals (Sweden)

    I. Marrag

    2016-06-01

    Le priapisme veineux est une urgence urologique. Il constitue un des effets secondaires des neuroleptiques parmi les quels la chlorpromazine. Cet effet iatrogène, qui est rare mais grave, doit être connu par les cliniciens afin d’être mieux prévenu pour éviter les séquelles érectiles.

  16. La lecture de Merleau-Ponty par Renaud Barbaras

    Czech Academy of Sciences Publication Activity Database

    Pechar, Jiří

    2015-01-01

    Roč. 11, č. 2 (2015), s. 1-6 ISSN 1336-6556 Institutional support: RVO:67985955 Keywords : Merleau-Ponty * Husserl * phenomenology * linguistics of Ferdinand de Saussure Subject RIV: AA - Philosophy ; Religion http://www.ostium.sk/sk/la-lecture-de-merleau-ponty-par-renaud-barbaras/

  17. Par Pond vegetation status summer 1995 - July survey descriptive summary

    International Nuclear Information System (INIS)

    Mackey, H.E. Jr.; Riley, R.S.

    1995-07-01

    A survey of the emergent shoreline aquatic plant, communities began in June 1995, three months after the refilling of Par Pond to approximately 200 feet (61 meters) above mean sea level, and continued with this July survey. Aquatic plant communities, similar to the pre-drawdown Par Pond communities, are becoming reestablished. Beds of maidencane (Panicum hemitomon), lotus (Nelumbo lutea), water lily (Nymphaea odorata), and watershield (Brasenia schreberi) are now extensive and well established. In addition, within isolated coves, extensive beds of water lilies and spike-rush (Eleocharis sp.) are common. Cattail occurrence has increased since refill, but large beds common to Par Pond prior to the drawdown have not formed. Invasion of willow (Salix sp.) and red maple (Acer rubrum) occurred along the lake shoreline during drawdown. The red maples along the present shoreline are beginning to show evidence of stress and mortality from flooding over the past four months. Some of the willows appear to be stressed as well. The loblolly pines (Pinus taeda), which were flooded in all but the shallow shoreline areas, are now dead. Future surveys are planned for the growing seasons of 1995, 1996, and 1997, along with the evaluation of satellite data for mapping the areal extent of the macrophyte beds of Par Pond

  18. fortification des farines tropicales par l'introduction de proteines ...

    African Journals Online (AJOL)

    2Université d'Abomey Calavy, Faculté des Sciences et Techniques, Bénin ... valeur recommandée par le Codex Alimentarius pour ce type de complément alimentaire destiné aux enfants. ..... neurotransmission, coagulation sanguine et.

  19. Induction of the lambda bacteriophage synthesis in Escherichia coli K 12 by polonium alpha rays; Induction de la synthese du bacteriophage lambda chez Escherichia coli K 12 par les rayons alpha du polonium

    Energy Technology Data Exchange (ETDEWEB)

    Devoret, Raymond

    1958-06-15

    This research thesis reports the study of the inducing action of polonium alpha radiations in Escherichia Coli K 12 by using an external irradiation device. This work comprised the development of a method to spread bacteria in layer with a thickness less than 20 microns, and the measurement of the number of α particles falling on the irradiated surface. This measurement has been performed by using a nuclear emulsion and a simple photographic film. It appears that alpha radiations have an inducing action, and that at most 15 per cent of bacteria can be induced. The comparison of the induction curve with the survival curves of lysogen and sensitive stains shows that there is no abortive induction. Thus, it appears that this inducing action is not due to an indirect effect of the irradiated medium [French] Dans ce travail on a etudie l'action inductrice des rayons alphas du polonium chez Escherichia Coli K 12 par un diapoaitif d'irradiation externe. Son utilisation necessitait: - une methode d'etalement des bacteries en couche de moins de 20 microns d'epaisseur; - une mesure du nombre des particules alpha tombant sur la surface etendue irradiee. Les mesures ont ete faites a l'aide d'une emulsion nucleaire et d'un film photographique ordinaire. 1) Les rayons alphas ont une action inductrice. Au plus 15 pc des bacteries peuvent etre induites. 2) La oomparaison de la courbe d'induction et des courbes de survie des souches lysogene et sensible montre qu'il n'y a pas d'inductions abortives. 3) Cette action inductrice n'est pas due a un effet indirect du milieu irradie. (auteur)

  20. Problems presented by the filtration and sampling of aerosols in the atomic energy programme; Problemes poses par la filtration et le prelevement des aerosols dans le cadre de l'energie atomique

    Energy Technology Data Exchange (ETDEWEB)

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

    1959-07-01

    The maximum permissible limits for radioactive aerosols are much lower than those for aerosols encountered in the non-nuclear industries. These limits depend on numerous factors such as: nature of the radiation, half-life, etc. The radioactive aerosols can be prepared by various methods. The filtering of the air in high activity laboratories or in plutonium treatment factories necessitates an installation consisting of: - aspiration filters, - extraction filters of very high efficiency (those used for {alpha} emitter cells: designed to be replaced without incurring contamination risks; those used for {gamma} emitter cells: designed to be replaced by remote control). The filtering in nuclear reactors is also effectuated by filter papers: - the G1 reactor with open circuit: the air coolant is entirely filtered at the entry and on leaving; - the G2, G3 and EDF1 reactors with closed circuits: filtering under pressure of a small portion of the coolant gas. (author) [French] Les limites maxima permises des aerosols radioactifs sont beaucoup plus faibles que celles des aerosols rencontres dans l'industrie classique. Elles dependent de nombreux facteurs tel que: nature du rayonnement, periode radioactive, etc... La formation des aerosols radioactifs est de nature diverse. La filtration des laboratoires de haute activite, ou d'usines d'elaboration de plutonium conduit a des types d'installations comportant: - des filtres d'aspiration; - des filtres d'extraction a rendement extremement eleve (type pour cellules emettrices {alpha} concu pour etre change sans risque de contamination, type pour cellules emettrices {gamma}: concu pour etre change a distance) La filtration des reacteurs nucleaires sont egalement effectuee par des papiers filtres: - reacteur G1 a circuit ouvert: air de refroidissement totalement filtre a l'aspiration et a l'extraction; - reacteurs G2, G3, EDF1: a circuit ferme: filtration sous pression d'une faible partie du gaz de refroidissement. (auteur)

  1. 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

  2. The role of pars flaccida in human middle ear sound transmission.

    Science.gov (United States)

    Aritomo, H; Goode, R L; Gonzalez, J

    1988-04-01

    The role of the pars flaccida in middle ear sound transmission was studied with the use of twelve otoscopically normal, fresh, human temporal bones. Peak-to-peak umbo displacement in response to a constant sound pressure level at the tympanic membrane was measured with a noncontacting video measuring system capable of repeatable measurements down to 0.2 micron. Measurements were made before and after pars flaccida modifications at 18 frequencies between 100 and 4000 Hz. Four pars flaccida modifications were studied: (1) acoustic insulation of the pars flaccida to the ear canal with a silicone rubber baffle, (2) stiffening the pars flaccida with cyanoacrylate cement, (3) decreasing the tension of the pars flaccida with a nonperforating incision, and (4) perforation of the pars flaccida. All of the modifications (except the perforation) had a minimal effect on umbo displacement; this seems to imply that the pars flaccida has a minor acoustic role in human beings.

  3. Concept of transfer functions for a nuclear reactor; Notion de fonction de transfert pour un reacteur nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Dalfes, Abdi [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires. Departement d' Electronique Generale, Service d' Electronique des Reacteurs

    1966-07-01

    The solution to the correlation equations are expressed in terms of the eigenvalues and Eigen-matrices of the transport operator, for a subcritical zero power reactor. This allows to define, for each point of the reactor and for detectors detecting neutrons of given velocities, correlation and transfer functions driven by the same white-noise source. A precise meaning is also given to the importance operator, which is the adjoin of the transport operator. (author) [French] La solution des equations regissant les matrices de correlation est exprimee en fonction des valeurs et matrices propres de l'operateur de transport pour un reacteur sous-critique et de puissance nulle. Ceci permet de definir, en chaque point du reacteur et pour des detecteurs repondant a des neutrons de vitesse definie, des fonctions de correlation et de transfert dont les entrees sont attaquees par une meme source de bruit blanc. Le role joue par l'operateur importance, adjoint de l'operateur de transport, est aussi precise. (auteur)

  4. Apoplejía pituitaria con parálisis del III par craneal: Reporte de caso

    Directory of Open Access Journals (Sweden)

    Miguel Pinto Valdivia

    2011-10-01

    Full Text Available Se describe el caso de un varón de 65 años de edad, sin antecedentes patológicos de importancia, que acudió a emergencia del Hospital Nacional Cayetano Heredia por presentar cefalea intensa y ptosis palpebral izquierda. El examen físico mostró parálisis aislada del III par craneal izquierdo. Los análisis de laboratorio mostraron hiponatremia e hipopituitarismo y la resonancia magnética nuclear un adenoma pituitario con áreas de hemorragia e invasión de los senos cavernosos. El tratamiento incluyó glucocorticoides y descompresión quirúrgica transesfenoidal. La anatomía patológica confirmó el diagnóstico de infarto hemorrágico de un adenoma pituitario. El paciente fue dado de alta con terapia sustitutiva de levotiroxina y prednisona. La ptosis palpebral izquierda se recuperó en forma parcial. La apoplejía pituitaria es un síndrome clínico producido por un proceso expansivo dentro de la silla turca, secundario a hemorragia o infarto de un adenoma pituitario, que se caracteriza por cefalea, déficit visual, oftalmoplejía y alteración del nivel de conciencia. Este proceso expansivo puede comprimir los pares craneales en los senos cavernosos, produciendo diferentes grados de parálisis de los músculos oculomotores. La parálisis aislada del III par craneal es rara.(Rev Med Hered 2011;22:186-189.

  5. Épidémiologie de l'intoxication par envenimation chez les enfants ...

    African Journals Online (AJOL)

    Introduction: L'intoxication par envenimation est l'ensemble des manifestations locales et générales induites par la pénétration dans l'organisme d'une substance toxique produite par un animal venimeux. Le but de notre travail était d'étudier les signes cliniques des intoxications par envenimation chez les enfants de 0 à 15 ...

  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. Soluble urokinase plasminogen activator receptor (suPAR) in acute care

    DEFF Research Database (Denmark)

    Rasmussen, Line Jee Hartmann; Ladelund, Steen; Haupt, Thomas Huneck

    2016-01-01

    for age, sex, Charlson score and C reactive protein. Area under the curve for receiver operating characteristics curve analysis of suPAR for 30-day mortality was 0.84 (95% CI 0.81 to 0.86). Furthermore, in the entire cohort, women had slightly higher suPAR compared with men, and suPAR was associated...

  8. Movement and equipositioning of plasmids by ParA filament disassembly

    DEFF Research Database (Denmark)

    Ringgaard, Simon; van Zon, Jeroen; Howard, Martin

    2009-01-01

    , plasmids consistently migrate behind disassembling ParA cytoskeletal structures, suggesting that ParA filaments pull plasmids by depolymerization. The perpetual cycles of ParA assembly and disassembly result in continuous relocation of plasmids, which, on time averaging, results in equidistribution...

  9. Protease-Activated Receptor 4 (PAR4): A Promising Target for Antiplatelet Therapy.

    Science.gov (United States)

    Rwibasira Rudinga, Gamariel; Khan, Ghulam Jilany; Kong, Yi

    2018-02-14

    Cardiovascular diseases (CVDs) are currently among the leading causes of death worldwide. Platelet aggregation is a key cellular component of arterial thrombi and major cause of CVDs. Protease-activated receptors (PARs), including PAR1, PAR2, PAR3 and PAR4, fall within a subfamily of seven-transmembrane G-protein-coupled receptors (GPCR). Human platelets express PAR1 and PAR4, which contribute to the signaling transduction processes. In association with CVDs, PAR4 not only contributes to platelet activation but also is a modulator of cellular responses that serve as hallmarks of inflammation. Although several antiplatelet drugs are available on the market, they have many side effects that limit their use. Emerging evidence shows that PAR4 targeting is a safer strategy for preventing thrombosis and consequently may improve the overall cardiac safety profile. Our present review summarizes the PAR4 structural characteristics, activation mechanism, role in the pathophysiology of diseases and understanding the association of PAR4 targeting for improved cardiac protection. Conclusively, this review highlights the importance of PAR4 antagonists and its potential utility in different CVDs.

  10. Protease-Activated Receptor 4 (PAR4: A Promising Target for Antiplatelet Therapy

    Directory of Open Access Journals (Sweden)

    Gamariel Rwibasira Rudinga

    2018-02-01

    Full Text Available Cardiovascular diseases (CVDs are currently among the leading causes of death worldwide. Platelet aggregation is a key cellular component of arterial thrombi and major cause of CVDs. Protease-activated receptors (PARs, including PAR1, PAR2, PAR3 and PAR4, fall within a subfamily of seven-transmembrane G-protein-coupled receptors (GPCR. Human platelets express PAR1 and PAR4, which contribute to the signaling transduction processes. In association with CVDs, PAR4 not only contributes to platelet activation but also is a modulator of cellular responses that serve as hallmarks of inflammation. Although several antiplatelet drugs are available on the market, they have many side effects that limit their use. Emerging evidence shows that PAR4 targeting is a safer strategy for preventing thrombosis and consequently may improve the overall cardiac safety profile. Our present review summarizes the PAR4 structural characteristics, activation mechanism, role in the pathophysiology of diseases and understanding the association of PAR4 targeting for improved cardiac protection. Conclusively, this review highlights the importance of PAR4 antagonists and its potential utility in different CVDs.

  11. Par3L enhances colorectal cancer cell survival by inhibiting Lkb1/AMPK signaling pathway

    International Nuclear Information System (INIS)

    Li, Taiyuan; Liu, Dongning; Lei, Xiong; Jiang, Qunguang

    2017-01-01

    Partitioning defective 3-like protein (Par3L) is a recently identified cell polarity protein that plays an important role in mammary stem cell maintenance. Previously, we showed that high expression of Par3L is associated with poor survival in malignant colorectal cancer (CRC), but the underlying mechanism remained unknown. To this end, we established a Par3L knockout colorectal cancer cell line using the CRISPR/Cas system. Interestingly, reduced proliferation, enhanced cell death and caspase-3 activation were observed in Par3L knockout (KO) cells as compared with wildtype (WT) cells. Consistent with previous studies, we showed that Par3L interacts with a tumor suppressor protein liver kinase B1 (Lkb1). Moreover, Par3L depletion resulted in abnormal activation of Lkb1/AMPK signaling cascade. Knockdown of Lkb1 in these cells could significantly reduce AMPK activity and partially rescue cell death caused by Par3L knockdown. Furthermore, we showed that Par3L KO cells were more sensitive to chemotherapies and irradiation. Together, these results suggest that Par3L is essential for colorectal cancer cell survival by inhibiting Lkb1/AMPK signaling pathway, and is a putative therapeutic target for CRC. - Highlights: • Par3L knockout using the CRISPR/Cas system induces apoptosis in colorectal cancer cells. • Par3L interacts with Lkb1 and regulates the activity of AMPK signaling cascade. • Par3L knockout cells are more sensitive to treatment of different chemotherapy drugs and irradiation.

  12. Brésil : La contamination par le mercure en Amazonie | CRDI ...

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

    11 janv. 2011 ... En tentant de déceler la source de la contamination de l'Amazone par le ... par Jean-Rémy Davy Guimaraes de l'Université fédérale de Rio de Janeiro ... ces mattes est circonscrite par la conservation et la restauration en rive.

  13. Gamma Camera with Image Amplifier: Application in Nuclear Medicine; Camera Gamma a Amplificateur d'Image: Application en Medecine Nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Kellershohn, C.; Vernejoul, P. de; Desgrez, A. [CEA, Service Hospitalier Frederic Joliot, Orsay (France); Lequais, J.; Roux, G.; Lansiart, A. [CEA, Centre d' Etudes Nucleaires de Saclay, Gif-Sur-Yvette (France)

    1969-05-15

    cardiac haemodynamics as well as pulmonary ventilation. (author) [French] La camera decrite comprend une optique constituee par une grille de plomb collimatrice a 649 canaux cylindriques de 130 mm de longueur et 5,5 mm de diametre, un detecteur constitue par une mosaieque de 700 cristaux de Nal(Tl) d'un diametre utile de 5, 5 mm et d'une longueur de 20 mm avec une distance entre les axes de 7,5 mm, et un dispositif d'amplification de lumiere constitue par un premier amplificateur d'image n Ring-Operator 9463 de la Compagnie francaise Thomson-Houston dont la photocathode est en contact optique avec le detecteur et qui est lui-meme couple optiquement a un deuxieme amplificateur a grand gain de lumiere P829A de English Electric Valve. Suivant un principe expose pour la premiere fois durant la precedente conference organisee par l'Agence internationale de l'energie atomique sur l'exploration medicale (scanning) ce deuxieme amplificateur peut etre egalement utilise comme un obturateur electronique dont l'ouverture est commandee par un photomultiplicateur selectionnant la lumiere ayant pour origine la source radioactive examinee. Ce dispositif elimine tres efficacement le bruit de fond du premier tube amplificateur. Sur le plan des applications la camera est utilisee sous deux regimes de fonctionnement: d'une part,en mettant en jeu le dispositif d'obturation electronique dont la cadence d'ouverture et de fermeture peut atteindre 10 kHz, le bruit de fond est pratiquement elimine et il est possible de realiser avec des doses traceuses de radioelements conventionnels des images d'organes tels que la thyroiede, le foie, le rein, etc. en des temps de pose tres courts par rapport a la scintigraphie habituelle; d'autre part,en utilisant des radioelements a demi-vie effective tres courte a de tres hautes activites, de l'ordre de plusieurs millicuries Inverted-Question-Mark il n'est plus necessaire de mettre en jeu la suppression du bruit de fond et sa frequence de repetition limitee a

  14. La syphilis congenitale revelee par une fracture spontanee

    Directory of Open Access Journals (Sweden)

    Mounia Lakhdar Idrissi

    2011-11-01

    Full Text Available Alors qu�elle est actuellement oubliee dans les pays developpes, la syphilis congenitale se voit encore chez nous faute du depistage antenatal. Ses formes cliniques sont polymorphes et orientent a tord vers d�autres pathologies surtout en periode neonatale. Le diagnostic n�est donc pas toujours facile. La revelation d�une syphilis congenitale par une fracture spontanee est exceptionnellement decrite. Nous rapportons dans ce travail le cas d�un nourrisson de 2 mois ramene en consultation pour limitation douloureuse des mouvements du bras droit. Le diagnostic est evoque sur les donnees radiologiques et confirme par la serologie syphilitique. Le traitement a repose essentiellement sur l�administration de la penicilline G avec une bonne evolution clinique.

  15. Results of Preliminary Tests of PAR Bunch Cleaning

    CERN Document Server

    Yao, Chihyuan; Grelick, Arthur; Lumpkin, Alex H; Sereno, Nicholas S

    2005-01-01

    A particle accumulator ring (PAR) is used at the Advanced Photon Source (APS) to collect multiple linac bunches and compress them into a 0.3-ns (rms) single bunch for booster injection. A 9.77-MHz fundamental rf system and a 117.3-MHz harmonic rf system are employed for initial beam capture and bunch length compression. Satellite bunches with very low charge form due to rf phase drifts or beam loading change. These satellites, when injected into the booster and then into the storage ring (SR), cause bunch impurity at three buckets from the target bucket. Storage ring and booster bunch cleaning was tried but proved to be difficult due to the top-up mode of operation in the storage ring and tune drift in the booster synchrotron. Recently we implemented a PAR bunch-cleaning system with tune-modulated harmonic rf knockout. Preliminary tests gave a measured SR bunch purity of better than 10

  16. Avis 6 sur la formation à et par la recherche

    OpenAIRE

    Centre de Coopération Internationale en Recherche Agronomique pour le Développement

    2015-01-01

    La formation à et par la recherche s’appuie sur la démarche scientifique, les savoirs, les connaissances à transmettre, tout autant que l’acquisition de compétences en gestion de projet, de capacités au travail en équipe, d’une ouverture d’esprit qui favorisera la créativité. Elle doit permettre de prendre conscience de la responsabilité endossée par la communauté scientifique vis-à-vis de la société et de l’environnement, mais aussi préparer l’avenir professionnel de celle ou de celui qu...

  17. Evaluation of the Stability After Orthodontic Treatment Using PAR Index

    Directory of Open Access Journals (Sweden)

    Chaitra Ramanathan

    2006-01-01

    Full Text Available The aim of the present study is to establish the results using the scores obtained from the methodology that was applied for assessing the stability after 2 years post orthodontic treatment and stability in a sample of 69 individuals. After applying PAR index to the collected group of patients, a series of scores were obtained, which were then needed to be evaluated further to establish the results. The scores were evaluated using the nomogram. A comparison was done between the post treatment and the 2 years post treatment PAR weighting scores to determine if the results were stable after orthodontic treatment. The majority of the orthodontic patients were treated to a good standard and that the results appeared to be stable.

  18. La parálisis cerebral en el contexto escolar /

    OpenAIRE

    González Vara, Azucena

    2012-01-01

    Se analiza el concepto de parálisis cerebral, los diferentes tipos y sus características. También las adaptaciones que se deben realizar a nivel de centro, de aula, y a nivel individual para estos alumnos, conocer los diferentes sistemas alternativos y aumentativos de comunicación y aplicar las ayudas técnicas que precisa este alumnado

  19. Tuberculose lymphonodale cervicale chez les enfants vaccines par ...

    African Journals Online (AJOL)

    La tuberculose ganglionnaire cervicale est une localisation extrapulmonaire relativement fréquente chez l'enfant. Elle pose essentiellement des difficultés de prévention. L'objectif de ce travail est d'étudier les particularités diagnostiques et thérapeutiques chez des enfants vaccinés par le BCG. Matériel et méthodes: Nôtre ...

  20. Traitement De La Peripneumonie Contagieuse Bovine Par L ...

    African Journals Online (AJOL)

    Traitement De La Peripneumonie Contagieuse Bovine Par L'oxyteTracycline Longe Action Et Transmission Experimentale de la Maladie A Partir de Bovins Traites. ... Tous les 14 animaux ont séroconverti et l'analyse post-mortem a montré la présence des lésions chroniques dont des séquestres pulmonaires chez 4 d'entre ...

  1. Adoption d'innovations agricoles par le truchement de services ...

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

    L'agriculture est le fer de lance de nombreuses économies en développement, mais la capacité des petits agriculteurs privés de ressources à adopter des innovations agricoles est freinée par le manque d'accès à des services financiers adéquats. Des experts internationaux estiment qu'il existe un manque à gagner ...

  2. Candido: Uma Leitura Paródica de Candide

    Directory of Open Access Journals (Sweden)

    Maria Gloria Cusumano Mazzi

    2010-12-01

    Full Text Available O presente artigo estuda a leitura paródica que Leonardo Sciascia (1921-1989 faz de Voltaire (1694-1778 mediante o cotejo das obras: o hipertexto Candido ovvero Un sogno fatto in Sicilia (1977 e o hipotexto Candide ou l’optimisme (1759. Apresenta ainda outra possibilidade de leitura, ou seja, Candido como metáfora da própria intertextualidade.

  3. Solution volumes finis polynomiale par morceaux pour les ...

    African Journals Online (AJOL)

    Nous présentons dans ce papier un concept de solution volumes finis continue pour des problèmes de diffusion-convection avec des données régulières. Nous comparons dans certains cas particuliers la solution proposée avec la solution volumes finis classiques (qui est une fonction constante par morceaux) et la ...

  4. Preliminary Analysis For Wolsong Par Effects Using ISACC Calculations

    International Nuclear Information System (INIS)

    Song, Yong Mann; Kim, Dong Ha

    2012-01-01

    In the paper, hydrogen control effects using PARs only are analyzed for severe SBO station blackout (SBO) sequences beyond the design basis accidents in WS-1 which are of CANDU6 type reactor. As a computational tool, the latest version of ISAAC4.3 (Integrated Severe Accident Analysis Code for CANDU), which is a fully integrated and lumped severe accident computer code, is used to simulate hydrogen generation and transport inside the reactor building (R/B) before its failure. For the performance of hydrogen removal, the depletion rate equation of K-PAR developed in Korea is applied. In a CANDU reactor, three areas are identified as sources of hydrogen under severe accidents: fuel-coolant interactions in intact channels, suspended fuel or debris interactions in-calandria tank and debris interactions in-calandria vault. The first two origins provide source for the late ('late' terminology is used because it takes more than one day before calandria tank failure) potential hydrogen combustion before calandria tank failure and all the three origins would provide source for the very late potential hydrogen combustion occurring at or after calaria tank failure. If the hydrogen mitigation system fails, the AICC (adiabatic isochoric complete combustion) burning of highly flammable hydrogen may cause Wolsong R/B failure. So hydrogen induced failure possibility is evaluated, using preliminary ISAAC calculations, under several SBO conditions with and without PAR for both late and very late accident periods

  5. Protease activated receptors (PARS) mediation in gyroxin biological activity

    International Nuclear Information System (INIS)

    Silva, Jose Alberto Alves da

    2009-01-01

    Gyroxin is a serine protease enzyme from the South American rattlesnake (Crotalus durissus terrificus) venom; it is only partially characterized and has multiple activities. Gyroxin induces blood coagulation, blood pressure decrease and a neurotoxic behavior named barrel rotation. The mechanisms involved in this neurotoxic activity are not known. Whereas gyroxin is a member of enzymes with high potential to become a new drug with clinical applications such as thrombin, batroxobin, ancrod, tripsyn and kalicrein, it is important to find out how gyroxin works. The analysis on agarose gel electrophoresis and circular dichroism confirmed the molecules' integrity and purity. The gyroxin intravenous administration in mice proved its neurotoxicity (barrel rotation). In vivo studies employing intravital microscopy proved that gyroxin induces vasodilation with the participation of protease activated receptors (PARs), nitric oxide and Na+K+ATPase. The leukocytes' adherence and rolling counting indicated that gyroxin has no pro inflammatory activity. Gyroxin induced platelet aggregation, which was blocked by inhibitors of PAR1 and PAR4 receptors (SCH 79797 and tcY-NH 2 , respectively). Finally, it was proved that the gyroxin temporarily alter the permeability of the blood brain barrier (BBB). Our study has shown that both the protease-activated receptors and nitric oxide are mediators involved in the biological activities of gyroxin. (author)

  6. Preparation of nuclear purity beryllium oxalate tri-hydrate; Preparation d'oxalate de beryllium trihydrate de purete nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Delcorte, M; Lecocq, A; Rigaud, A [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1964-07-01

    In this report we have gathered the whole of the knowledge acquired by our group during the campaign for preparation of beryllium oxalate we carried out through the first half year of 1962. The reader shall find in the first place information and bibliographic data gathered by Miss OLLIVIER, documentalist of the Section d'Etudes, Recherches et Applications Chimiques. We then describe the original process perfected in the laboratories, and the production techniques we employed for the semi-large operative units. Finally, we publish the results we obtained on one hand on the chemical aspect, in the industrial meaning of the term, which is to-day concerning the ponderal output, on the other hand on the analytical aspect as you can evidently not dissociate the quantity of substance produced from its purity. (authors) [French] Nous avons reuni dans ce document l'ensemble des connaissances acquises par notre groupe pendant la campagne de preparation d'oxalate de beryllium que nous avons effectuee au cours du 1er semestre 1962. Le lecteur y trouvera en premier lieu les renseignements et donnees bibliographiques rassembles par Mlle OLLIVIER, documentaliste a la Section d'Etudes, Recherches et Applications Chimiques. Nous decrivons ensuite le procede original mis au point dans les laboratoires et les techniques de fabrication que nous avons utilisees pour des unites operatoires demi-grand. Pour terminer nous publions les resultats obtenus, d'une part sur le plan chimique, au sens industriel du terme, c'est-a-dire du point de vue rendement ponderal, d'autre part sur le plan analytique puisqu'on ne peut evidemment pas dissocier la quantite de produit fabrique, de sa purete. (auteurs)

  7. A Bipolar Spindle of Antiparallel ParM Filaments Drives Bacterial Plasmid Segregation

    DEFF Research Database (Denmark)

    Gayathri, P; Fujii, T; Møller-Jensen, Jakob

    2012-01-01

    the spindle between ParRC complexes on sister plasmids. Using a combination of structural work and total internal reflection fluorescence microscopy, we show that ParRC bound and could accelerate growth at only one end of polar ParM filaments, mechanistically resembling eukaryotic formins. The architecture...... of ParM filaments enabled two ParRC-bound filaments to associate in an antiparallel orientation, forming a bipolar spindle. The spindle elongated as a bundle of at least two antiparallel filaments, thereby pushing two plasmid clusters toward the poles....

  8. First (18)F-labeled ligand for PET imaging of uPAR

    DEFF Research Database (Denmark)

    Persson, Morten; Liu, Hongguang; Madsen, Jacob

    2013-01-01

    Urokinase-type plasminogen activator receptor (uPAR) is overexpressed in human prostate cancer and uPAR has been found to be associated with metastatic disease and poor prognosis. AE105 is a small linear peptide with high binding affinity to uPAR. We synthesized an N-terminal NOTA......-conjugated version (NOTA-AE105) for development of the first (18)F-labeled uPAR positron-emission-tomography PET ligand using the Al(18)F radiolabeling method. In this study, the potential of (18)F-AlF-NOTA-AE105 to specifically target uPAR-positive prostate tumors was investigated....

  9. Intact and cleaved uPAR forms: diagnostic and prognostic value in cancer

    DEFF Research Database (Denmark)

    Rasch, M.G.; Lund, I.K.; Hoyer-Hansen, G.

    2008-01-01

    identified in tissue and body fluids. It is well-established, that the total amount of all uPAR forms is a strong prognostic marker in different types of cancer. Using immunoassays, measuring the individual uPAR forms, has revealed that the cleaved uPAR forms are even stronger prognostic markers and have...... diagnostic utility. This review will focus on the mechanism of uPAR cleavage and the functional consequences, as well as the clinical applicability of cleaved uPAR forms Udgivelsesdato: 2008...

  10. Nuclear energy; Le nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    This digest document was written by members of the union of associations of ex-members and retired people of the Areva group (UARGA). It gives a comprehensive overview of the nuclear industry world, starting from radioactivity and its applications, and going on with the fuel cycle (front-end, back-end, fuel reprocessing, transports), the nuclear reactors (PWR, BWR, Candu, HTR, generation 4 systems), the effluents from nuclear facilities, the nuclear wastes (processing, disposal), and the management and safety of nuclear activities. (J.S.)

  11. Staff Organization in Nuclear Power Stations; Organisation du personnel des centrales nucleaires; Organizatsiya personala na atomnykh ehlektrostantsiyakh; Organizacion del personal de las centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Scuricini, G. B. [Comitato Nazionale Energia Nucleare, Roma (Italy)

    1963-10-15

    This paper deals with the organization of operating and maintenance staff at nuclear power stations in Italy and manpower variations, either because the plants themselves differ or are organized in some special way. Staff doing jobs for which a specific training is required are given special consideration in the paper. (author) [French] Dans le memoire, on examine l'organisation du personnel d'exploitation et d'entretien des centrales nucleaires italiennes et les differences existant dans les effectifs, differences dues soit aux caracteristiques des centrales memes, soit aux particularites d'organisation des entreprises. Le personnel charge de fonctions determinees pour lesquelles un entrainement special est requis, fait l'objet d'une attention particuliere. (author) [Spanish] En la memoria se examina la organizacion del personal de explotacion y conservacion de las centrales nucleares italianas y las diferencias que existen entre sus efectivos, diferencias que se deben a las caracteristicas de las mismas centrales o a las particularidades de organizacion de las empresas. El autor dedica especial atencion al personal encargado de funciones que requieren una formacion profesional especial. (author) [Russian] Issleduyutsya voprosy organizatsii personala, zanimayushchegosya ehkspluatatsiej ital'yanskikh atomnykh ehlektrostantsij i ukhodom za nimi, a takkhe razlichiya v sostave personala, vytekayushchie libo iz kharakternykh osobennostej samikh stantsij, libo iz osobennostej organizatsii predpriyatij. Osoboe vnimanie udelyaetsya personalu, kotoromu porucheny opredelennye funktsii, trebuyushchie spetsial'noj pod go tovki. (author)

  12. Nuclear magnetic resonance of iron-57 nuclei in local fields in yttrium and iron garnets; Resonance magnetique nucleaire des noyaux du fer 57 dans les champs locaux du grenat d'yttrium et de fer

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-07-01

    We have demonstrated the nuclear resonance of {sup 57}Fe nuclei in the local field of each of the two magnetic sub-lattices of yttrium and iron garnets. The resonance frequencies and the relaxation times have been measured as a function of the temperature. (author) [French] Nous avons mis en evidence la resonance nucleaire des noyaux de {sup 57}Fe dans le champ local de chacun des deux sous-reseaux magnetiques du grenat d'yttrium et de fer. Les frequences de resonances et les temps de relaxation ont ete mesures en fonction de la temperature. (auteur)

  13. Purification by high vacuum fusion and progressive solidification of uranium from electrolytic origin; Purification par fusion sous vide eleve et solidification progressive d'uranium d'origine electrolytique

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-01-15

    grain observed, so-called secondary recrystallisation. in appendix, the method for measuring the electrical resistance by induction (with direct current)is studied from the fundamental and experimental point of view. The author applied it to the particular case of uranium for measuring the low-temperature resistance of the bars from the same which solidified first to the least pure ended the ingot. (author) [French] Dans le cadre de recherches generales sur la purification de l'uranium par fusion de zone, on a entrepris de determiner le degre de purification que l'on pourrait atteindre par une simple solidification progressive a vitesse et direction soigneusement controlees d'un uranium de purete nucleaire courante. Cet uranium de purete intermediaire fournirait un materiau de depart approprie au mode de purification ultime qu'est la fusion a zone verticale, dite ''flottante''. Dans ce but, des lingots d'uranium d'origine electrolytique ont ete refondus sous vide (2 a 5 x 10{sup -6} mm) dans une longue nacelle en UO{sub 2} apres une monte lente en temperature pour eliminer le maximum de gaz et d'impuretes volatiles. Ce degazage et cette volatilisation d'impuretes sont completes par maintien prolonge a haute temperature du bais liquide. Celui-ci est ensuite solidifie d'une extremite a l'autre de la nacelle par deplacement a vitesse lente et constante du front de solidification de facon a obtenir une repartition des impuretes selon les lois etablies par PFANN. Differentes methodes experimentales ont permis de montrer que le metal solidifie en premier lieu est nettement plus pur que celui de la partie solidifie a l'extremite opposee du lingot. Le degre de purification du metal en tete du lingot a ete apprecie, soit quantitativement par mesure du rapport des resistivites electriques a la temperature ambiante et a celle de l'azote liquide, soit qualitativement par l'examen de la structure micrographique et par l'etude de la recristallisation du metal. D'une part, le metal

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-07-01

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

  15. Dynamic Filament Formation by a Divergent Bacterial Actin-Like ParM Protein.

    Directory of Open Access Journals (Sweden)

    Anthony J Brzoska

    Full Text Available Actin-like proteins (Alps are a diverse family of proteins whose genes are abundant in the chromosomes and mobile genetic elements of many bacteria. The low-copy-number staphylococcal multiresistance plasmid pSK41 encodes ParM, an Alp involved in efficient plasmid partitioning. pSK41 ParM has previously been shown to form filaments in vitro that are structurally dissimilar to those formed by other bacterial Alps. The mechanistic implications of these differences are not known. In order to gain insights into the properties and behavior of the pSK41 ParM Alp in vivo, we reconstituted the parMRC system in the ectopic rod-shaped host, E. coli, which is larger and more genetically amenable than the native host, Staphylococcus aureus. Fluorescence microscopy showed a functional fusion protein, ParM-YFP, formed straight filaments in vivo when expressed in isolation. Strikingly, however, in the presence of ParR and parC, ParM-YFP adopted a dramatically different structure, instead forming axial curved filaments. Time-lapse imaging and selective photobleaching experiments revealed that, in the presence of all components of the parMRC system, ParM-YFP filaments were dynamic in nature. Finally, molecular dissection of the parMRC operon revealed that all components of the system are essential for the generation of dynamic filaments.

  16. Proteinase-Activated Receptor 1 (PAR1 regulates leukemic stem cell functions.

    Directory of Open Access Journals (Sweden)

    Nicole Bäumer

    Full Text Available External signals that are mediated by specific receptors determine stem cell fate. The thrombin receptor PAR1 plays an important role in haemostasis, thrombosis and vascular biology, but also in tumor biology and angiogenesis. Its expression and function in hematopoietic stem cells is largely unknown. Here, we analyzed expression and function of PAR1 in primary hematopoietic cells and their leukemic counterparts. AML patients' blast cells expressed much lower levels of PAR1 mRNA and protein than CD34+ progenitor cells. Constitutive Par1-deficiency in adult mice did not affect engraftment or stem cell potential of hematopoietic cells. To model an AML with Par1-deficiency, we retrovirally introduced the oncogene MLL-AF9 in wild type and Par1-/- hematopoietic progenitor cells. Par1-deficiency did not alter initial leukemia development. However, the loss of Par1 enhanced leukemic stem cell function in vitro and in vivo. Re-expression of PAR1 in Par1-/- leukemic stem cells delayed leukemogenesis in vivo. These data indicate that Par1 contributes to leukemic stem cell maintenance.

  17. Proteinase-Activated Receptor 1 (PAR1) regulates leukemic stem cell functions.

    Science.gov (United States)

    Bäumer, Nicole; Krause, Annika; Köhler, Gabriele; Lettermann, Stephanie; Evers, Georg; Hascher, Antje; Bäumer, Sebastian; Berdel, Wolfgang E; Müller-Tidow, Carsten; Tickenbrock, Lara

    2014-01-01

    External signals that are mediated by specific receptors determine stem cell fate. The thrombin receptor PAR1 plays an important role in haemostasis, thrombosis and vascular biology, but also in tumor biology and angiogenesis. Its expression and function in hematopoietic stem cells is largely unknown. Here, we analyzed expression and function of PAR1 in primary hematopoietic cells and their leukemic counterparts. AML patients' blast cells expressed much lower levels of PAR1 mRNA and protein than CD34+ progenitor cells. Constitutive Par1-deficiency in adult mice did not affect engraftment or stem cell potential of hematopoietic cells. To model an AML with Par1-deficiency, we retrovirally introduced the oncogene MLL-AF9 in wild type and Par1-/- hematopoietic progenitor cells. Par1-deficiency did not alter initial leukemia development. However, the loss of Par1 enhanced leukemic stem cell function in vitro and in vivo. Re-expression of PAR1 in Par1-/- leukemic stem cells delayed leukemogenesis in vivo. These data indicate that Par1 contributes to leukemic stem cell maintenance.

  18. Post-Construction Testing of the Elk River, Hallam and Piqua Power Reactor Plants; Essais apres construction des centrales nucleaires d'Elk River, de Hallam et de Piqua; Predehkspluatatsionnoe ispytanie Ehlk-riverskoj, Khehlpemskoj i Pikuaskoj ehnergeticheskikh reaktornykh ustanovok; Ensayos posteriores a la construccion de las centrales nucleoelectricas de Elk River, Hallam y Piqua

    Energy Technology Data Exchange (ETDEWEB)

    Pursel, C. A. [United States Atomic Energy Commission, Argonne, IL (United States)

    1963-10-15

    numerous, observed or suspected, deficiencies or malfunctions of components which led to additional testing and analyses. In some instances, repair or modification of components was necessary to correct fabrication or engineering errors. Major problem areas are discussed: Elk River Reactor. Discovery of cracks in portions of the reactor vessel surface cladding led to extensive investigations and analyses and required some repairs and vessel modifications. Insufficient steam separation capacity required replacement and modification of some reactor vessel internal hardware. Hallam Nuclear Power Facility. Entrainment of the helium cover gas led to modifications of the secondary sodium loops. Failure of a tube in the intermediate (sodium to sodium) heat exchanger led to analyses to determine the cause of failure followed by removal and repair of the heat exchanger. Piqua Nuclear Power Facility. Chemical cleaning of the piping system damaged several valves which required mere repair or replacement. Leaks in the organic coolant and steam tracing systems caused repeated delays. After completion of the necessary repairs and modifications, the actual performance characteristics of each of the three reactors closely matched design predictions. (author) [French] Les resultats des essais apres construction de trois centrales nucleaires, dans le cadre du programme de demonstration des centrales nucleaires de la Commission de l'energie atomique des Etats-Unis (CEA-EU), permettront peut-etre de faire certaines generalisations concernant cette phase de la construction et de l'exploitation des centrales. Ces trois centrales, le reacteur de puissance d'Elk River (ERR), la centrale nucleaire de Hallam (HNPF), et la centrale nucleaire de Piqua (PNPF), appartiennent a trois filieres differentes: reacteur a eau bouillante a circulation naturelle, reacteur a graphite et a sodium et reacteur ralenti et refroidi par un fluide organique. La periode des essais apres construction a commence a la fin

  19. Separation of Graphitic Line in Debyegram of the Reactor Graphite; Separation de la raie graphitique dans le debyegramme du graphite nucleaire; Otdelenie linii grafita v debaiegramme reaktornogo grafita; Separacion de la linea grafitica en el diagrama de debye del grafito nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Pandic, B. [Institut Rudjer Boskovio, Zagreb, Yugoslavia (Croatia)

    1963-11-15

    The author sets forth a method for the determination of crystallite dimensions L{sub c} in reactor graphite. The method consists of the mathematical correction of the diffraction profile (002) obtained by means of a Philips diffractometer with scintillation counter. During the work CuK{sub {beta}} radiation is used. The convenience of using CuK{sub {beta}} radiation rather than that of a CuK{sub {alpha}} doublet is discussed. All instrumental errors except that of the sample adsorption are eliminated using corresponding slits. Sample adsorption is corrected mathematically. Highly symmetrical lines of graphitic and non-graphitic phase could be analytically separated from such corrected line profiles. Experimental error in the determination of the half-height and half-width of these lines does not exceed 5%. (author) [French] On a elabore une methode pour determiner la hauteur moyenne L{sub c} des cristallites du graphite nucleaire. Il s'agit d'une methode mathematique de correction du profil de la raie de diffraction (002), obtenu par le diffractometre Philips avec un compteur a scintillation. On a discute les avantages des rayons CuK{sub {beta}} par rapport au doublet CuK{sub {alpha}}. Le choix des ouvertures elimine toutes les erreurs, sauf l'erreur d'absorption dans les echantillons, que l 'on ecarte mathematiquement. Les raies de diffraction pures et tres symetriques des phases graphitique et non graphitique peuvent etre separees du profil corrige de cette facon. L'incertitude dans la mesure de la demi-largeur de ces raies n'est pas superieure a 5%. (author) [Spanish] El autor de la memoria expone un metodo para determinar la altura media Lc de las cristalitas del grafito nuclear. Consiste en corregir matematicamente el perfil de la linea de difraccion (002) obtenido con un difractometro Philips y un contador de centelleo. En la memoria se explican las ventajas que la radiacion CuK{sub {beta}} ofrece sobre el doblete CuK{sub {alpha}} Si se elige correctamente la

  20. The double par locus of virulence factor pB171: DNA segregation is correlated with oscillation of ParA

    DEFF Research Database (Denmark)

    Ebersbach, G; Gerdes, K; Charbon, Gitte Ebersbach

    2001-01-01

    Prokaryotic plasmids and chromosomes encode partitioning (par) loci that segregate DNA to daughter cells before cell division. Recent database analyses showed that almost all known par loci encode an ATPase and a DNA-binding protein, and one or more cis-acting regions where the proteins act. All...

  1. Preparation and properties of carbonaceous products prepared by the cracking of natural gas; Fabrication et proprietes de corps carbones prepares par craquage de gaz naturel

    Energy Technology Data Exchange (ETDEWEB)

    Blum, P L; Bochirol, L; Rappeneau, J; Cornuault, P; Blanchard, R; Moreau, C [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

    1964-07-01

    . Plusieurs voies ont ete etudiees: 1 - En utilisant comme supports des graphites industriels de qualite courante (densite voisine de 1,50) on obtient des corps d'une densite proche de 1,80. Leur porosite ouverte (6 a 7 pour cent) est inferieure a celle des graphites traditionnels, et plusieurs de leurs proprietes sensiblement egales ou superieures a celles resultant habituellement d'une double inpregnation au brai. 2 - L'utilisation comme supports de demi-produits ('cuits') cycle traditionnel de fabrication des graphites ne conduit pas a des resultats satisfaisants. On en donne les raisons principales. 3 - Un procede nouveau, dit 'BB5', a ete mis au point. Il part, directement des matieres de corps pulverulentes (coke de petrole ou graphite) mises en forme au moyen d'un liant dispersable dans l'eau. Les supports ainsi constitues permettent, du fait de leur structure poreuse, de tirer le meilleur parti de la densification par craquage, en dessous de 1000 deg. C: du gaz naturel. Les produits obtenus, composes a parts a peu pres egales de la matiere de corps et de pyrocarbone, peuvent avoir des densites depassant 1,90. Leur porosite ouverte, tres faible, peut etre rendue pratiquement nulle, leur impermeabilite etant alors excellente (k = 10{sup -8} cm{sup 2}sec{sup -1}). Ils sont egalement remarquables par leur resistance elevee a la compression, qui peut se situer entre 15 et 20 kg/mm{sup 2} pour les versions ne subissant pas un traitement final de graphitation. On indique quelques exemples d'applications possibles, dans le domaine, nucleaire, des materiaux ainsi prepares. (auteurs)

  2. The behaviour of some polyatomic gases in nuclear reactors; Le comportement de quelques gaz polyatomiques dans les reacteurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

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

    1958-07-01

    'influence des radiations. La radiolyse de NH{sub 3}, procede par un mecanisme complexe, et la cinetique obeit a une loi d'ordre 2,5 environ qui augmente avec le taux de decomposition. La decomposition de l'hydrogene sulfure est notablement plus rapide que celle de NH{sub 3}. Le seul produit gazeux de la reaction est l'hydrogene. Le soufre, qui se depose sur les parois des ampoules, est nettement perceptible a l'oeil. On a obtenu jusqu'ici des decompositions allant jusqu'a 84 pour cent. L'influence de la reaction {sup 32}S (n, p) {sup 32}P est consideree. La decomposition radiochimique du protoxyde d'azote N{sub 2}O se fait avec des rendements eleves. La reaction est compliquee des ses debuts par la formation d'oxydes superieurs de l'azote que nous identifions et mesurons. Le methane donne par decomposition radiochimique des quantites d'hydrocarbures superieurs. Certains de ces systemes gazeux pourraient trouver des applications dans la mesure de fortes doses de rayonnement. Ce probleme est discute en conclusion. (auteur)

  3. ParABS Systems of the Four Replicons of Burkholderia cenocepacia: New Chromosome Centromeres Confer Partition Specificity†

    Science.gov (United States)

    Dubarry, Nelly; Pasta, Franck; Lane, David

    2006-01-01

    Most bacterial chromosomes carry an analogue of the parABS systems that govern plasmid partition, but their role in chromosome partition is ambiguous. parABS systems might be particularly important for orderly segregation of multipartite genomes, where their role may thus be easier to evaluate. We have characterized parABS systems in Burkholderia cenocepacia, whose genome comprises three chromosomes and one low-copy-number plasmid. A single parAB locus and a set of ParB-binding (parS) centromere sites are located near the origin of each replicon. ParA and ParB of the longest chromosome are phylogenetically similar to analogues in other multichromosome and monochromosome bacteria but are distinct from those of smaller chromosomes. The latter form subgroups that correspond to the taxa of their hosts, indicating evolution from plasmids. The parS sites on the smaller chromosomes and the plasmid are similar to the “universal” parS of the main chromosome but with a sequence specific to their replicon. In an Escherichia coli plasmid stabilization test, each parAB exhibits partition activity only with the parS of its own replicon. Hence, parABS function is based on the independent partition of individual chromosomes rather than on a single communal system or network of interacting systems. Stabilization by the smaller chromosome and plasmid systems was enhanced by mutation of parS sites and a promoter internal to their parAB operons, suggesting autoregulatory mechanisms. The small chromosome ParBs were found to silence transcription, a property relevant to autoregulation. PMID:16452432

  4. 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.)

  5. Serum suPAR in patients with FSGS: trash or treasure?

    Science.gov (United States)

    Maas, Rutger J H; Deegens, Jeroen K J; Wetzels, Jack F M

    2013-07-01

    The urokinase-type plasminogen activator receptor (uPAR) has important functions in cell migration. uPAR can be shed from the cell membrane resulting in soluble uPAR (suPAR). Further cleavage gives rise to shorter fragments with largely unknown functions. Recent studies have demonstrated that both overexpression of uPAR on podocytes and the administration of suPAR cause proteinuria in mice. The common pathogenic mechanism involves the activation of podocyte β3-integrin. Increased activation of β3-integrin is also observed in patients with focal and segmental glomerulosclerosis (FSGS). These observations form the basis for the hypothesis that suPAR may be the circulating factor causing FSGS. A recent study fosters this idea by demonstrating increased suPAR levels in the serum of patients with FSGS and reporting an association with recurrence after transplantation and response to plasmapheresis. However, this study was heavily biased, and subsequent studies have given conflicting results. Although the experimental work is very suggestive, at present there is no proof that any known human suPAR fragment causes FSGS in humans. We therefore suggest that the measurement of suPAR using currently available assays has absolutely no value at the present time in decision-making in routine clinical practice.

  6. PAR-2 expression in the gingival crevicular fluid reflects chronic periodontitis severity

    Directory of Open Access Journals (Sweden)

    Henrique FUKUSHIMA

    Full Text Available Abstract Recent studies invest