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Rastoin, J.
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Service des Etudes Mecaniques et Thermiques
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Service des Etudes Mecaniques et Thermiques
AbstractAbstract
[en] The different nuclear reactor types (present and future), the possible uses of these reactors (electricity, heat production) and the chemical and metallurgical problems to be solved are discussed
[fr]
On presente les differentes filieres de reacteurs nucleaires (filieres actuelles et futures, les possibles utilisations de ces reacteurs (production d'electricite, de chaleur) et les problemes de chimie et metallurgie a resoudreOriginal Title
Les reacteurs nucleaires. Politique generale et choix des filieres
Primary Subject
Source
1975; 12 p; 1. Meeting of the solid-state chemistry and metallurgy prospective group; Paris, France; 21 Jan 1975
Record Type
Report
Literature Type
Conference
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Country of publication
Publication YearPublication Year
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Brisbois, J.; Ko, P.; Rastoin, J.
Commissariat a l'Energie Atomique - CEA, Departement des Etudes de Piles Service d'Etudes de Protections de Piles (France)
Commissariat a l'Energie Atomique - CEA, Departement des Etudes de Piles Service d'Etudes de Protections de Piles (France)
AbstractAbstract
[en] While the highest reachable neutron energy is about 1 KeV with resonant detectors, and the lowest reachable energy is about 2 MeV with usual threshold detectors, the authors report the search for a neutron detector which could be efficient on this whole range. After an overview of detection principles and mechanisms, they outline that only nuclides of which isomers have an adequate decay period and a sufficient cross section for the (n,n') reaction can practically be used. As rhodium seems to exhibit the required qualities, the authors present the rhodium nuclear properties (activation cross section), the method and equipment for a preliminary study, report and discuss preliminary results, and evoke future work
Original Title
Etude du detecteur de rhodium pour la dosimetrie des neutrons rapides
Primary Subject
Source
12 Dec 1962; 34 p; 22 refs.; Available from the INIS Liaison Officer for France, see the 'INIS contacts' section of the INIS website for current contact and E-mail addresses: http://www.iaea.org/inis/Contacts/
Record Type
Miscellaneous
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AbstractAbstract
[en] Full text: Natural uranium plate used for shielding studies. The paper describes a study carried out to investigate the characteristics of a fast-neutron source, viz. the natural-uranium plate in NAlADE I. This plate, which is 2 cm thick, is fed by a stream of thermal neutrons leaving the reflector of EL-1. The intensity, spectrum and angular distribution of the neutrons leaving the plate were calculated by means of a Monte-Carlo method and by analytical techniques. The computed data were compared, with experimental data obtained with activation detectors. Natural uranium rod in a graphite reactor. On the basis of the fission distribution obtained by means of measurements of fine structure in thermal neutrons, calculations were made with a Monte-Carlo method and with analytical techniques of the spectrum and intensity of the fast neutrons leaving the rod. With this primary source calculations were then made of neutron attenuation in the graphite, fine structure in fast neutrons in a reactor cell and the source corresponding to the lateral walls of the channel, which is partly responsible for neutron leakage in perforated reflectors. (author)
Primary Subject
Secondary Subject
Source
International Atomic Energy Agency, Vienna (Austria); 171 p; Oct 1964; p. 160; Panel on reactor shielding; Vienna (Austria); 9-13 Mar 1964; Abstract only
Record Type
Book
Literature Type
Conference
Country of publication
ACTINIDES, ACTIVATION ANALYSIS, BARYONS, CALCULATION METHODS, CARBON, CHEMICAL ANALYSIS, DISTRIBUTION, ELEMENTARY PARTICLES, ELEMENTS, EXPERIMENTAL REACTORS, FERMIONS, HADRONS, HEAVY WATER COOLED REACTORS, HEAVY WATER MODERATED REACTORS, IRRADIATION REACTORS, ISOTOPE PRODUCTION REACTORS, MATERIALS, METALS, MINERALS, NATURAL URANIUM REACTORS, NEUTRONS, NONDESTRUCTIVE ANALYSIS, NONMETALS, NUCLEONS, RADIATION FLUX, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, SPECTRA, TANK TYPE REACTORS, THERMAL REACTORS, URANIUM
Publication YearPublication Year
Reference NumberReference Number
Related RecordRelated Record
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] It is pointed out that in the relative near future, the substitution of oil and gas by nuclear energy will be necessary. Special features of the fuel cycle of future reactor types are discussed. It will be necessary to recycle all produced plutonium, no matter if in conventional or advanced light water reactors or in breeders. The introduction of breeders will be a further necessity in the not all to distant future
Original Title
Les reacteurs du future et leur cycle de combustible
Primary Subject
Source
Schweizerische Vereinigung fuer Atomenergie, Bern (Switzerland); vp; 1989; p. R3-1-R3-13; Schweizerische Vereinigung fuer Atomenergie; Bern (Switzerland); SVA-information meeting: modern nuclear power plants; SVA-Informationstagung: Moderne Kernkraftwerke; Zuerich-Oerlikon (Switzerland); 19 Oct 1989; SVA, Postfach 5032, CH-3001 Bern
Record Type
Book
Literature Type
Conference
Country of publication
Publication YearPublication Year
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Brisbois, J.; Rastoin, J.
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Dept. des Etudes Mecaniques et Thermiques
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Dept. des Etudes Mecaniques et Thermiques
AbstractAbstract
[en] With the abandonment of the development of steam cycle reactors which, in fact, represent the technology available now, the introduction of high temperature power generating reactors is now put back in the medium or long term with respect to two applications specific to this type of reactor, namely generating electricity by helium turbine and coal gasification. A first question arises, incidentally in the same terms as previously; will high temperature power generating reactors have enough advantages to be introduced on the market in competition with the systems already in place (PWR, BWR, heavy water reactors) or being developed (FBR). The second question is to know when coal gasification reactor will be introduced on a commercial basis. Technically speaking, providing the target is not too ambitious, a protopype could see the light of day at the start of the 90s, thereby leading to a commercial introduction around the year 2000. This target means that the nations concerned should start a close cooperation in coal gasification and in nuclear technology at one and the same time. The easiest way, it would seem, is to concentrate the effort on the production of hydrogen by methane reforming which is the common trunk of several uses on the one end, and has the least amount of technological difficulty on the other. At least, this is the current prevailing position in France which will be discussed shortly with Germany
[fr]
Avec l'abandon du developpement des reacteurs a cycle vapeur qui representent, en fait, la technologie disponible aujourd'hui, l'introduction des reacteurs a haute temperature est maintenant reportee a moyen ou long terme sur deux applications specifiques a ce type de reacteur: la production d'electricite par turbine a helium et la gazeification du charbon. Une premiere question se pose, dans les memes termes d'ailleurs qu'elle s'est posee precedemment: les reacteurs electrogenes H.T.R. auront-ils des merites suffisants pour etre introduits sur le marche en competition avec les filieres en place (PWR, BWR, reacteurs a eau lourde) ou en developpement (FBR). La deuxieme question est de savoir a quelle date se fera l'introduction commerciale des reacteurs pour la gazeification du charbon. Sur le plan technique, a condition de ne pas avoir d'objectif trop ambitieux, un prototype pourrait voir le jour au debut des annees 90, ce qui conduirait a une introduction commerciale au debut des annees 2000. Cet objectif implique que les nations interessees mettent en oeuvre une etroite cooperation a la fois dans le domaine de la gazeification du charbon et de la technologie nucleaire. La voie la plus facile semble-t-il est de focaliser l'effort sur la production d'hydrogene par reformage du methane qui, d'une part est le tronc commun de plusieurs applications et, d'autre part, comporte le moins de difficulte technologique. C'est du moins la position qui prevaut actuellement en France et qui sera discutee prochainement avec l'AllemagneOriginal Title
La filiere des reacteurs a haute temperature
Primary Subject
Source
1979; 29 p; Meeting of French engineers and scientists on reactor systems not developed in France; Paris, France; 26 Jan 1979
Record Type
Report
Literature Type
Conference
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Publication YearPublication Year
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Rastoin, J.; Gelin, P.
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Service des Etudes Mecaniques et Thermiques
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Service des Etudes Mecaniques et Thermiques
AbstractAbstract
No abstract available
Primary Subject
Source
1974; 12 p; 13. Nuclear energy conference; Milan, Italy; 12 Dec 1974
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
ENRICHED URANIUM REACTORS, GAS COOLED REACTORS, GRAPHITE MODERATED REACTORS, IRRADIATION REACTORS, ISOTOPE PRODUCTION REACTORS, POOL TYPE REACTORS, POWER REACTORS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, THERMAL REACTORS, TRAINING REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
Publication YearPublication Year
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Rastoin, J.
AEA Technology, Risley (UK)
AEA Technology, Risley (UK)
AbstractAbstract
[en] Known world reserves of oil and natural gas may only last another 50 years and therefore nuclear energy will become more important in the future. Industrialised countries should also be encouraged to conserve their oil reserves to make better use of them and share them with less developed countries. France already produces 30% or more of its primary energy from uranium in the form of nuclear generated electricity. France has therefore accumulated considerable expertise in all aspects of the nuclear fuel cycle. Each stage of the fuel cycle, extraction, enrichment, fuel fabrication, fissile material utilisation, reprocessing and waste storage is discussed. The utilisation of fissile material is the most important stage and this is considered in more detail under headings: increase in burn-up, spectral shift, plutonium utilisation including recycling in pressurized water reactors and fast reactors and utilisation of reprocessed uranium. It is concluded that nuclear power for electricity production will be widely used throughout the world in the future. (UK)
Primary Subject
Source
1990; 16 p; ASPEA Information Session meeting on modern nuclear power stations; Zurich (Switzerland); 19 Oct 1989; Translated from French.
Record Type
Report
Literature Type
Conference; Translation
Report Number
Country of publication
ACTINIDES, BREEDER REACTORS, DEVELOPED COUNTRIES, ELEMENTS, ENRICHED URANIUM REACTORS, EPITHERMAL REACTORS, EUROPE, FAST REACTORS, MANAGEMENT, METALS, POWER, POWER REACTORS, REACTORS, RESOURCES, SEPARATION PROCESSES, STORAGE, THERMAL REACTORS, WASTE MANAGEMENT, WASTE STORAGE, WATER COOLED REACTORS, WATER MODERATED REACTORS
Publication YearPublication Year
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Rastoin, J.; Brisbois, J.
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Dept. des Etudes Mecaniques et Thermiques
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Dept. des Etudes Mecaniques et Thermiques
AbstractAbstract
[en] After discussing the state of development of natural uranium graphite-gas cooled reactors in France, the current program focused on electricity generating high temperature reactors and the future program based on heat generating applications are presented
Primary Subject
Source
1978; 39 p; Annual national meeting of the American Nuclear Society; San Diego, CA, USA; 18 - 23 Jun 1978
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Report
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Conference
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INIS IssueINIS Issue
AbstractAbstract
No abstract available
Primary Subject
Source
American Nuclear Society, Oak Ridge, Tenn.; American Nuclear Society, Hinsdale, Ill; p. 115-127; 1974
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Report
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Conference
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INIS IssueINIS Issue
AbstractAbstract
[en] A survey is presented of the various steps in the nuclear fuel cycle in France. They include exploration of uranium, uranium enrichment, fuel fabrication, optimization in utilisation of fissile materials by enlarging the fuel irradiation level and spectrum variation, utilisation of plutonium and reprocessed uranium, spent fuel reprocessing and waste storage
Primary Subject
Secondary Subject
Source
Wittman, F.H. (ed.) (Swiss Federal Institute of Technology, Lausanne (Switzerland). Laboratory for Building Materials); 207 p; ISBN 90 6191 738 7; 
; 1987; p. 25-32; Balkema; Rotterdam (Netherlands); 9. International conference on structural mechanics in reactor technology (SMIRT 9); Lausanne (Switzerland); 17-21 Aug 1987
; 1987; p. 25-32; Balkema; Rotterdam (Netherlands); 9. International conference on structural mechanics in reactor technology (SMIRT 9); Lausanne (Switzerland); 17-21 Aug 1987
Record Type
Book
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Conference
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Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
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