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Thomas, K.E.; Hakkila, E.A.; Menlove, H.O.; Hong, J.S.
Los Alamos National Lab., NM (United States). Funding organisation: USDOE, Washington, DC (United States)1993
Los Alamos National Lab., NM (United States). Funding organisation: USDOE, Washington, DC (United States)1993
AbstractAbstract
[en] This report discusses the fuel cycle options under consideration for the Direct Use of PWR Spent Fuel in CANDU Reactors (DUPIC) satisfy the need to maximize the energy output of nuclear fuel while minimizing the potential for proliferation of separated plutonium. Several options have been considered including repacking options and thermal processing. Los Alamos has completed preliminary investigations of the safeguards aspects of the different processing options and the need for measurement development. Future safeguards activities will focus on the thermal-mechanical process selected for further development
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1993; 5 p; Global '93: future nuclear systems - emerging fuel cycles and waste disposal options; Seattle, WA (United States); 12-17 Sep 1993; CONF-930913--20; CONTRACT W-7405-ENG-36; Available from OSTI as DE93018560; NTIS; INIS; US Govt. Printing Office Dep
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Report
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Conference
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ACTINIDES, ELEMENTS, ENERGY SOURCES, ENRICHED URANIUM REACTORS, FUELS, HEAVY WATER MODERATED REACTORS, MATERIALS, METALS, POWER REACTORS, PRESSURE TUBE REACTORS, REACTOR MATERIALS, REACTORS, SEPARATION PROCESSES, THERMAL REACTORS, TRANSURANIUM ELEMENTS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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