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Bruneder, H.; Haubert, P.
Organization for Economic Co-Operation and Development, Winfrith (United Kingdom)1965
Organization for Economic Co-Operation and Development, Winfrith (United Kingdom)1965
AbstractAbstract
[en] Physics and optimisation studies of large (1250 MW; 10 MW/m3) Plutonium-fuelled reactors are carried out. Either Uranium-238 or Thorium is considered as fertile material. Complete core replacement is assumed. (author)
Primary Subject
Source
Apr 1965; 51 p; Country of input: International Atomic Energy Agency (IAEA); Document from Juelich Preservation Project; 9 refs., figs., tabs.
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Report
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ACTINIDE NUCLEI, ACTINIDES, ALPHA DECAY RADIOISOTOPES, DEVELOPED COUNTRIES, ELEMENTS, EUROPE, EVEN-EVEN NUCLEI, GAS COOLED REACTORS, GERMAN FR ORGANIZATIONS, GRAPHITE MODERATED REACTORS, HEAVY NUCLEI, ISOTOPES, MATERIALS, METALS, NATIONAL ORGANIZATIONS, NUCLEI, RADIOISOTOPES, REACTORS, SPONTANEOUS FISSION RADIOISOTOPES, TEMPERATURE RANGE, TRANSURANIUM ELEMENTS, URANIUM ISOTOPES, WESTERN EUROPE, YEARS LIVING RADIOISOTOPES
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AbstractAbstract
No abstract available
Original Title
PWR
Primary Subject
Source
Transactions of the American Nuclear Society 1976 international meeting; Washington, DC, USA; 14 Nov 1976; Published in summary form only.
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Journal Article
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Conference
Journal
Transactions of the American Nuclear Society; v. 24 p. 225-226
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AbstractAbstract
No abstract available
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Source
1974; 10 p; Panel on plutonium utilization in thermal power reactors; Karlsruhe, F.R. Germany; 25 Nov 1974; 2 refs.
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Report
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Conference
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AbstractAbstract
No abstract available
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Secondary Subject
Source
Kerntechnische Gesellschaft im Deutschen Atomforum e.V., Bonn (Germany, F.R.); p. 425-426; 1977; ZAED; Eggenstein-Leopoldshafen, Germany, F.R; Reactor congress 1977; Mannheim, Germany, F.R; 29 Mar 1977; AED-CONF--77-013-106; 5 refs. Short communication only.
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Book
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Conference
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AbstractAbstract
No abstract available
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Journal Article
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Progress Report
Journal
Nuclear Engineering International; v. 15(173); p. 811-817
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Bairiot, H.; Haubert, P.; Vanden Bemden, E.
Proceedings of joint topical meeting on commercial nuclear fuel technology today
Proceedings of joint topical meeting on commercial nuclear fuel technology today
AbstractAbstract
[en] After more than one year operation of the Belgonucleaire Pu Fuel Production Plant at Dessel, Belgium, the authors outline their conclusions regarding the cost of Pu recycling in water cooled reactors. The paper analyses the Pu recycling cost penalty in 3 specific cases. An analysis of the Pu value is also given for the three cases. It is concluded that the Pu fuel production penalty varies according to the three referenced cases from 180 to 70 percent of the total cost of U235 enriched fuel and that the corresponding Pu value varies from 6 to 11 dollars per g Pusub(f) on the basis of 15 dollars per lb U3O8 and enrichment at 42.1 dollars per SWU. (author)
Secondary Subject
Source
American Nuclear Society, Hinsdale, Ill.; Canadian Nuclear Association, Toronto, Ontario; p. 9-23; nd; Joint topical meeting on commercial nuclear fuel technology today; Toronto, Ontario, Canada; 28 Apr 1975
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Report
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Conference
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INIS VolumeINIS Volume
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AbstractAbstract
No abstract available
Original Title
Le nucleaire face au probleme de l'energie
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Journal Article
Journal
Journal des Ingenieurs; v. 23(3); p. 15-21
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AbstractAbstract
[en] During the past few years the facilities for the manufacture of plutonium fuels for LWR's have been scaled up from laboratories attached to nuclear research centres to more or less independent plants. Simultaneously, the quantity of plutonium fuel inserted at one time in a reactor is being increased from a few elements to the amount corresponding to self-generated recycle and even more. Plutonium fuel is therefore now subject to the same economic constraints as enriched uranium fuel; it has to be designed and manufactured accordingly; and is subject to market fluctuations difficult to foresee. Actually, the main problem of plutonium recycle in LWR's is not the competition of fast breeders but the fact that the large quantities which have been or are being produced cannot be utilized due to a lack of adequate reprocessing capacity
Primary Subject
Source
International Atomic Energy Agency, Vienna (Austria); p. 69-76; 1975; Panel on plutonium utilization in thermal power reactors; Karlsruhe, F.R. Germany; 25 Nov 1974; IAEA-PL--632/5
Record Type
Report
Literature Type
Conference
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Country of publication
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Bemden, Vanden E.; Waegh, F. de; Haubert, P.
Peaceful uses of atomic energy. Proceedings of the fourth international conference, jointly sponsored by the UN and the IAEA and held in Geneva, 6-16 September 1971. Vol. 81972
Peaceful uses of atomic energy. Proceedings of the fourth international conference, jointly sponsored by the UN and the IAEA and held in Geneva, 6-16 September 1971. Vol. 81972
AbstractAbstract
No abstract available
Original Title
Procedes de fabrication du combustible au plutonium pour FBR et prospective des couts
Primary Subject
Source
United Nations, New York (USA); International Atomic Energy Agency, Vienna (Austria); Proceedings series; 15 v.; v. 8 p. 295-309; 1972; IAEA/UN; Vienna; 4. international conference on the peaceful uses of atomic energy; Geneva, Switzerland; 6 Sep 1971; A/CONF.49/P--274; Microfiche of preprint available from INIS Clearinghouse.
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Book
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Conference
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Fossoul, E.; Haubert, P.; Hirschberg, D.; Morlet, E.
Plutonium as a Reactor Fuel. Proceedings of a Symposium on the Use of Plutonium as a Reactor Fuel1967
Plutonium as a Reactor Fuel. Proceedings of a Symposium on the Use of Plutonium as a Reactor Fuel1967
AbstractAbstract
[en] The introduction, at an increasing rate, of power reactors using slightly enriched uranium will inevitably lead to the production of considerable quantities of plutonium over the next decade. Fast reactors will not be capable of absorbing this material before 1980. The question thus arises of whether one should store the plutonium far future use in fast reactors, recycle it in existing thermal reactors, or try to sell it. The problem has been studied for an electric power generating system that does not foresee selling the plutonium produced by its reactors and does not buy plutonium outside, which enables a good approximation to be made and eliminates the major unknown quantity represented by the future market price of plutonium. Assuming within this system a programme that provides for the construction of power reactors of a given type and capacity at specific dates, the utilization of the plutonium produced can be optimized by linear programming techniques so as to minimize the discounted total cost of the power generated over a given period. A later stage consists in optimizing, by various techniques, not only the utilization but also the production of plutonium by appropriate selection of the power reactor types to be constructed. (author)
[fr]
L'implantation, a un rythme croissant, de centrales nucléaires à uranium légèrement enrichi entraînera la production inéluctable d'une quantité importante de plutonium au cours de la prochaine décennie. Les réacteurs à neutrons rapides ne seront capables d'absorber cette production qu'après 1980. La question se pose donc de savoir s'il est préférable de stocker le plutonium en vue de son utilisation ultérieure dans les réacteurs à neutrons rapides plutôt que de le recycler dans les réacteurs actuels à neutrons thermiques ou d'essayer de le vendre. Ce problème a été étudié dans le cadre d'un système de production d'énergie électrique qui ne prévoirait pas la vente du plutonium produit par ses réacteurs nucléaires ni son acquisition à l'extérieur, ce qui permet de faire une bonne approximation et d'éliminer la grande inconnue du prix de marché du plutonium dans les décennies à venir. Etant donné pour ce système une politique d'implantation de centrales nucléaires, c'est-à-dire un ensemble de décisions d'installer des centrales de type et de puissance donnés à des dates données, les techniques de programmation linéaire permettent d'optimiser l'utilisation du plutonium produit de façon à minimiser le coût total actualisé de la production cumulée d'énergie électrique pendant une période déterminée. Une étape ultérieure est l'optimisation, par des techniques différentes, non seulement de l'utilisation mais aussi de la production de plutonium, et cela en choisissant les types de réacteurs à installer dans les différentes centrales. (author)Original Title
Prospective d'Utilisation du Plutonium dans les Reacteurs
Primary Subject
Secondary Subject
Source
International Atomic Energy Agency, Vienna (Austria); 876 p; Sep 1967; p. 767-776; Symposium on the Use of Plutonium as a Reactor Fuel; Brussels (Belgium); 13-17 Mar 1967; IAEA-SM--88/18; ISSN 0074-1884; ; 2 refs., 23 figs., 2 tabs.
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Book
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Conference
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