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AbstractAbstract
[en] This report presents the directives concerning the obligations and the main characteristics of the nuclear PWR units of 1400 MWe, notified Electricite de France on the 06th of October 1983 by the Industry and Research Department. They reflect the concept of defence in depth
[fr]
Ce rapport presente les directives relatives aux obligations et caracteristiques principales des tranches nucleaires REP de 1400 MWe, notifiees a Electricite de France le 06/10/1983 par le Ministre de l'Industrie et de la Recherche. Elles traduisent le concept de defense en profondeurOriginal Title
Obligations et caracteristiques applicables aux tranches du palier 1400 MWe francais. Adaptation aux tranches des paliers 900 et 1300 MWe
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Oct 1985; 13 p; 9. Intenational conference on modern power stations; Liege (Belgium); 7-11 Oct 1985; CEA-DAS--209
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Report
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AbstractAbstract
[en] Increasing knowledge and lessons learned from starting and operating experience of French nuclear power plants, completed by the experience learned from the operation of foreign reactors, has contributed to the improvement of French PWR design and safety philosophy. Based on a deterministic approach, the French safety analysis was progressively completed by a probabilistic approach, each of them having possibilities and limits. As a consequence of the global risk objective set in 1977 for nuclear reactors, safety analysis was extended to the evaluation of events more complex than the conventional ones, and later to the evaluation of the feasibility of the offsite emergency plans in case of severe accidents
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May 1986; 12 p; KAIF-KNS Conference; Seoul (Republic of Korea); 29 Apr - 2 May 1986; CEA-DAS--244
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Report
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Conte, M.; Brandela, M.
Commissariat a l'Energie Atomique, Centre d'Etudes Nucleaires de Grenoble, 38 (France)1966
Commissariat a l'Energie Atomique, Centre d'Etudes Nucleaires de Grenoble, 38 (France)1966
AbstractAbstract
[en] During sintering in reducing atmospheres, UO2 pellets can be oxidized by gaseous impurities. The effects of temperature cycles, the partial pressure of O2 and the flow rate of the gas over the pellets were investigated. In these atmospheres, the O2 partial pressure during sintering is low at high temperatures, as a consequence of the dissociation rate of the combined water, but below 1000 deg C, it can be high enough to result in a noticeable oxidation of the surface of the pellets during cooling. The crystalline phases which can occur have been identified and two methods of detection have been proposed: a micrographic examination after chemical etching and radiocrystallography. (authors)
[fr]
Lors du frittage industriel du bioxyde d'uranium en atmosphere reductrice (hydrogene ou ammoniac dissocie) la presence d'impuretes oxydantes dans l'atmosphere peut provoquer l'oxydation des pastilles d'UO2; les auteurs ont etudie les phenomenes en faisant varier le cycle de temperature, la pression partielle d'oxygene introduit dans l'hydrogene, la vitesse de passage du gaz sur les pastilles. Dans les atmospheres considerees la pression partielle d'oxygene au-dessus de l'UO2 en cours de frittage est faible a temperature elevee car elle resulte de la dissociation de l'eau formee, mais a t < 1000 degrees C elle, peut etre assez importante pour provoquer une oxydation notable de la surface des pastilles lors du refroidissement. Les phases cristallines susceptibles d'etre formees ont ete reperees et deux methodes de detection proposees: la micrographie apres attaque chimique specifique et la radiocristallographie. (auteurs)Original Title
Etude du risque d'oxydation lors du frittage du bioxyde d'uranium et caracterisation de l'oxygene excedentaire
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May 1966; [36 p.]; 14 refs.
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Report
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Luccio, A.; Conte, M.
Brookhaven National Lab., Upton, NY (United States). Funding organisation: USDOE, Washington, DC (United States)1993
Brookhaven National Lab., Upton, NY (United States). Funding organisation: USDOE, Washington, DC (United States)1993
AbstractAbstract
[en] The spin of a polarized particle in a circular accelerator can be rotated with an arrangement of dipoles with field mutually perpendicular and perpendicular to the orbit. To achieve spin rotation, a given field integral value is required. The device must be designed in a way that the particle orbit is distorted as little as possible. It is shown that wigglers with many periods are suitable to achieve spin rotation with minimum orbit distortions. Wigglers are also more compact than more established structures and will use less electric power. Additional advantages include their use for non distructive beam diagnostics. Results are given for the Relativistic Heavy Ion Collider (RHIC) in the polarized proton mode
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1993; 3 p; International particle accelerator conference; Washington, DC (United States); 17-20 May 1993; CONF-930511--74; CONTRACT AC02-76CH00016; OSTI as DE93014312; NTIS; INIS; US Govt. Printing Office Dep
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AbstractAbstract
No abstract available
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Journal Article
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Nuclear Technology; v. 16(1); p. 143-155
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AbstractAbstract
[en] A sustainable energy economy will be demanding primary energy sources, preferably renewable and mainly domestically available, using energy carriers, such as hydrogen and electricity, able to solve environmental problems and to assure adequate energy security. Instrumental to such goals will be the research and development of storage systems with performance characteristics compatible with major application requirements. Lithium or nickel are replacing lead in batteries, in order to better meet the extremely varying technical and economical requirements in fast growing conventional and new applications. Moreover, few technologies now permit to store hydrogen by modifying its physical state in gaseous or liquid form. The variety of hydrogen needs in the energy systems and in the vehicular sector is justifying the effort on solid state (metal hydrides and carbon nanostructures) or chemical systems (chemical hydrides). In this overview, emphasis is given to the major achievements in the field of electrical energy and hydrogen storage, in relation to the technological goals, which have been proposed in the major public research and collaborative programs throughout the world
Source
EMRS 2003, Symposium C: Nanoscale materials for energy storage; Strasbourg (France); 10-13 Jun 2003; S0921510703005257; Copyright (c) 2003 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.; Country of input: International Atomic Energy Agency (IAEA)
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Journal Article
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Materials Science and Engineering. B, Solid-State Materials for Advanced Technology; ISSN 0921-5107; ; CODEN MSBTEK; v. 108(1-2); p. 2-8
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Conte, M.; Deletre, G.; Henry, J.Y.
CEA Centre d'Etudes Nucleaires de Fontenay-aux-Roses, 92 (France). Dept. d'Analyse de Surete1988
CEA Centre d'Etudes Nucleaires de Fontenay-aux-Roses, 92 (France). Dept. d'Analyse de Surete1988
AbstractAbstract
[en] The safety of nuclear plants depends on the capacity of the systems they are composed to perform the functions they were designed for. The identification and understanding of phenomena liable to degrade this operational capacity thus constitute one of the safety problems for which allowance must be made at the earliest stage of a project. Aging, a natural and hence unavoidable process affecting all the components of an installation, was identified at a very early stage as being one of these phenomena. The investigation and implementation of solutions to the safety problems associated to aging make it necessary to: defining the domain in which the consequences of aging are to be evaluated, identifying the parameters involved, identifying the components sensitive to these parameters, understanding the mechanisms which govern its evolution. The results of qualification tests, and of tests and checks carried out at different stages of construction and operation, as well as allowance for operating experience, constitute the necessary basis for establishing or improving the regulatory requirements. The procedures for validating components and systems of the installation are also drawn up on the basis of these tests. Finally, the actions initiated within the scope of research and development programmes supply the additional data necessary for such validation, and provide the indispensable support for knowledge improvement
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1988; 13 p; International Nuclear power plant aging Symposium; Bethesda, MD (USA); 30 Aug - 1 Sep 1988
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Conte, M.; Luccio, A.U.; Pusterla, M.
Brookhaven National Laboratory (United States). Funding organisation: DOE - Office Of Science (United States)2009
Brookhaven National Laboratory (United States). Funding organisation: DOE - Office Of Science (United States)2009
AbstractAbstract
[en] The general expression of the Stern-Gerlach (SG) force is deduced for a relativistic charged spin-1/2 particle which travels inside a time varying magnetic field. This result was obtained either by means of two Lorentz boosts or starting from Dirac's equation. Then, the utilization of this interaction for attaining the spin states separation is reconsidered in a new example using a new radio-frequency arrangement. On the basis of the previous estimates, we feel ready to propose the time varying SG interaction as a method for attaining a spin state separation of an unpolarized beam of, say (anti)protons, since the energy of particles with opposite spin orientations will differ and beams in the two states can be separated. In a first stage of the study of a sensible practical design, we intend to proceed with numerical simulations. As a first step, we intend to verify the correctness of Eqs.(42) and (43) setting once βph = 2 and then βph = 3, in a cavity where the field line pattern can be realistically controlled. Beyond the verification of the present theory, there is also the aim of studying the effects generated by the spin precession inside the cavity, that we did not yet address in this note. Next, we shall consider a spin splitter scheme based on the lattice of an existing or planned (anti)proton ring endowed with an array of splitting cavities. The principal aim of the latter implementations is to check the mixing effect of the longitudinal phase-plane filamentation, i.e. the actual foe which could frustrate the entire spin splitting process.
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1 May 2009; 13 p; KB0202011; AC02-98CH10886; Available from http://www.bnl.gov/isd/documents/44354.pdf; PURL: https://www.osti.gov/servlets/purl/971605-H80mUW/; 30th Annual Combustion Research Conference; doi 10.2172/971605
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Conte, M.; Gouffon, A.; Moriette, P.
CEA Centre d'Etudes Nucleaires de Fontenay-aux-Roses, 92 (France). Dept. d'Analyse de Surete1984
CEA Centre d'Etudes Nucleaires de Fontenay-aux-Roses, 92 (France). Dept. d'Analyse de Surete1984
AbstractAbstract
[en] Upon the examination of the safety options submitted by EDF (Electricite de France) for a new pressurized water reactor design (N4, 1400 MWe), the French safety authorities decided that the conventionnal list of events to take under consideration should be amended as follows: failure of 1 and 2 steam generator tubes. To meet these objectives, design improvements were decided and new operating criteria were required by the technical specifications. Various preventive measures have been adopted by EDF to reduce tube degradation risks at the design stage, at the secondary feedwater quality level, and concerning also the quality control. The radiological consequences of generator tube integrity failure can be mitigated if the primary coolant activity is low, the tube flow detection is rapid, the release time is short, and the operating procedure is suitable and easily implemented
[fr]
Lors de l'examen des options de surete presentees par EDF pour le nouveau palier a eau pressurisee (N4, 1400 MWe), les autorites de surete francaises ont decide que la liste conventionnelle des situations a prendre en compte devait comprendre les cas de rupture de 1 et 2 tubes de generateur de vapeur. Des ameliorations de conception ont ete decidees et de nouveaux criteres de fonctionnnement ont ete imposes dans les specifications techniques d'exploitation. Pour reduire les risques de degradation des tubes, diverses mesures preventives ont ete prises par Electricite de France au niveau de la conception, de la qualite de l'eau du circuit secondaire, des controles. Les consequences des defauts d'etancheite des tubes de generateur seront d'autant plus limitees que l'activite du fluide primaire sera faible, la detection des defauts des tubes sera rapide, la duree du rejet sera ecourtee et la procedure dont dispose l'operateur sera bien adaptee et facilement applicablePrimary Subject
Source
Oct 1984; 29 p; OCDE specialists meeting on steam generator problems; Stockholm (Sweden); 1-5 Oct 1984; DAS--130
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AbstractAbstract
No abstract available
Original Title
(U,Pu)O2 pellets
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Conference on reactor materials performance; Richland, Washington, USA; 24 Apr 1972; See CONF-720420--.
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Journal Article
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Nuclear Technology; v. 16(1); p. 143-155
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ACTINIDES, BARIUM ADDITIONS, BINARY MIXTURES, CERIUM ADDITIONS, CHEMICAL COMPOSITION, DIFFUSION, FISSION PRODUCTS, FUEL PELLETS, MICROSTRUCTURE, MOLYBDENUM ADDITIONS, PHYSICAL RADIATION EFFECTS, PLUTONIUM OXIDES, QUANTITY RATIO, RUTHENIUM ADDITIONS, SPATIAL DISTRIBUTION, URANIUM DIOXIDE, ZIRCONIUM ADDITIONS
ACTINIDE COMPOUNDS, ALLOYS, BARIUM ALLOYS, CERIUM ALLOYS, CHALCOGENIDES, CRYSTAL STRUCTURE, DISPERSIONS, DISTRIBUTION, ELEMENTS, ISOTOPES, METALS, MIXTURES, MOLYBDENUM ALLOYS, OXIDES, OXYGEN COMPOUNDS, PLUTONIUM COMPOUNDS, RADIATION EFFECTS, RARE EARTH ALLOYS, RUTHENIUM ALLOYS, TRANSURANIUM COMPOUNDS, URANIUM COMPOUNDS, URANIUM OXIDES, ZIRCONIUM ALLOYS
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