Wilmer, P.C.
9th Pacific Basin Nuclear Conference. Nuclear energy, science and technology - Pacific partnership. Proceedings Volume 11994
9th Pacific Basin Nuclear Conference. Nuclear energy, science and technology - Pacific partnership. Proceedings Volume 11994
AbstractAbstract
[en] The UK has a tradition of reprocessing originating in the early weapons programme and all irradiated fuel from the Magnox reactors. In this presentation, specific consideration is given to the fuel used in the Advanced Gas Cooled Reactor and the competing irradiated fuel management strategies of early reprocessing in British Nuclear Fuel's Thermal Oxide Reprocessing Plant (THORP) at Sellafield or the alternative of long term storage followed by direct disposal. The fuel management strategy for the first UK's Pressurised Water Reactor , Sizewell B, is also discussed. The following issues are considered: Plant technology and the effect on back-end strategy; Nuclear Electric's commercial approach to the changing UK business environment; the storage of the irradiated fuel; dry storage; safety; public perception; proliferation; safeguards; bilateral trade agreements; the experience of THORP and the issues it raised concerning two stage licensing. 2 figs
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Source
Institution of Engineers, Canberra, ACT (Australia). Funding organisation: 9000297AU; 9000324AU; 452 p; Apr 1994; p. 199-204; The Institution of Engineers Australia; Canberra (Australia); 9. Pacific Basin Nuclear Conference; Sydney (Australia); 1-6 May 1994
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Book
Literature Type
Conference
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ALLOYS, DEVELOPED COUNTRIES, ENERGY SOURCES, ENRICHED URANIUM REACTORS, EUROPE, FUELS, GAS COOLED REACTORS, GRAPHITE MODERATED REACTORS, INFORMATION, MAGNESIUM ALLOYS, MAGNESIUM BASE ALLOYS, MATERIALS, NUCLEAR FACILITIES, NUCLEAR FUELS, REACTOR MATERIALS, REACTORS, STORAGE, WASTE MANAGEMENT, WASTE STORAGE
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AbstractAbstract
[en] The use of nuclear fuel in CEGB and SSEB Magnox reactors over a period of twenty years is reviewed in relation to the operational requirements of safety, reliability and economy. AGR experience to date, although more limited than Magnox is also considered. The currently perceived scope for introducing further changes to fuel element design whilst retaining overall cost effectiveness is presented. The importance of post-irradiation examination in supporting nuclear power station operation is noted. (author)
Primary Subject
Source
British Nuclear Energy Society, London; European Nuclear Society, Petit-Lancy (Switzerland); 547 p; ISBN 0 7277 0231 9; ; 1985; v. 1 p. 1-5; British Nuclear Energy Society; London (UK); Nuclear fuel performance conference; Stratford-upon-Avon (UK); 25-29 Mar 1985; Price Pound60.00
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Book
Literature Type
Conference
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