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AbstractAbstract
[en] The use of Th in a pressurized water reactor (PWR) with no modifications in the core lattice parameters, leads to a core design having the following advantages in U utilization and safety over the low enriched U. (a) The U ore demand to support a reactor over its life (30 yr) is reduced by as much as 32% of that of standard PWRs and separative work by 11%. (b) Safety related parameters are generally within the range of values expected for U cycle cores. The consequences of transient and postulated accidents are therefore expected to be no more serious than those for U for which safety requirements have been satisfied. (author)
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AbstractAbstract
[en] An overview of the authors personal view is presented on open questions in regard to still required research and development work for the thorium fuel cycle before its application in a technical-industrial scale may be tackled. For a better understanding, all stations of the back-end of the thorium fuel cycle are briefly illustrated and their special features discussed. They include storage and transportation measures, all steps of reprocessing, as well as the entire radioactive waste treatment. Knowledge gaps are, as far as they are obvious, identified and proposals put forward for additional worthwile investigations. (orig.)
[de]
Es wird eine Darstellung der nach Meinung des Autors noch offenen Fragestellungen im Bereich der Forschung und Entwicklung fuer den Thoriumbrennstoffkreislauf gegeben, bevor eine Umsetzung in den technisch-industriellen Massstab in Angriff genommen werden kann. Zur Veranschaulichung werden alle Stationen der Entsorgung kurz beschrieben und ihre Besonderheiten diskutiert. Sie umfassen Lager- und Transportvorgaenge, die gesamte Wiederaufarbeitung sowie die radioaktive Abfallbehandlung. Kenntnisluecken werden, soweit augenscheinlich, identifiziert und Vorschlaege fuer nuetzliche weiterfuehrende Untersuchungen gemacht. (orig.)Original Title
Wiederaufarbeitung im Thoriumbrennstoffkreislauf
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Jan 1984; 91 p
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AbstractAbstract
No abstract available
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ANS annual meeting; San Diego, CA, USA; 18 Jun 1978; See CONF-780622--. Published in summary form only.
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Transactions of the American Nuclear Society; v. 28 p. 342-343
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Milgram, M.S.
Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs1984
Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs1984
AbstractAbstract
[en] The characteristics of various advanced fuel cycles possible in CANDU reactors are compared
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Jan 1984; 20 p; Also published in Energy Newsletter vol. 4(3) Oct 1983.
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AbstractAbstract
No abstract available
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Veziroglu, T.N. (ed.); Miami Univ., Coral Gables, FL (USA). Clean Energy Research Inst; p. 497-499; 1977; p. 497-499; Alternative energy sources symposium; Miami Beach, FL, USA; 5 - 7 Dec 1977
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AbstractAbstract
[en] The following possibilities are examined for stretching the nuclear fuel supply: (1) fast breeder reactors, (2) thorium cycle, (3) heavy water reactors, (4) better isotope separation, and (5) electronuclear boosting
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Bogart, S.L. (ed.); Department of Energy, Washington, DC (USA). Office of Fusion Energy; p. 63-81; Jul 1978; p. 63-81; 2. DMFE hybrid reactor meeting; Washington, DC, USA; 2 - 3 Nov 1977
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AbstractAbstract
No abstract available
Original Title
Der Thorium-Brennstoffkreisprozess
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Fuel cycle conference '78; New York, NY; 5 - 8 Mar 1978; Short communication only.
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Archiv fuer Energiewirtschaft; v. 33(1); p. 36-45
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AbstractAbstract
[en] Continued development of thorium cycles for the CANDU reactor appears to offer advantages in both the short and long term. Their development will enhance confidence in the availability of nuclear fuel supplies at an acceptable cost, and the need for fissile breeding systems will be deferred for several decades. Conversely, development of thorium cycles is a necessary prelude to developing CANDU-LMFBR symbiotic systems optimized to exploit the potential of both systems. Finally, development of this cycle will significantly extend the technological lifetime of CANDU. This cycle will provide a degree of flexibility of response which will be needed to deal with the wide spectrum of possible energy futures
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Vogt, E.W.; Ludgate, G.A. (TRIUMF, Vancouver, BC (Canada)) (eds.); Canadian Nuclear Association, Toronto, ON (Canada); 388 p; ISBN 0-919307-30-2; 
; 1983; p. 139-144; 4. Pacific Basin nuclear conference; Vancouver, BC (Canada); 11-15 Sep 1983
; 1983; p. 139-144; 4. Pacific Basin nuclear conference; Vancouver, BC (Canada); 11-15 Sep 1983
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AbstractAbstract
No abstract available
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Veziroglu, T.N. (ed.); Miami Univ., Coral Gables, FL (USA). Clean Energy Research Inst; p. 501-503; 1977; p. 501-503; Alternative energy sources symposium; Miami Beach, FL, USA; 5 - 7 Dec 1977
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AbstractAbstract
No abstract available
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ANS annual meeting; San Diego, CA, USA; 18 Jun 1978; See CONF-780622--. Published in summary form only.
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Journal Article
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Transactions of the American Nuclear Society; v. 28 p. 336-337
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