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Campbell, T.K.; Guenther, R.J.; Jenson, E.D.
Pacific Northwest Lab., Richland, WA (USA)1989
Pacific Northwest Lab., Richland, WA (USA)1989
AbstractAbstract
[en] Results from this study are a part of spent fuel characterizations being conducted by the Materials Characterization Center (MCC) project at Pacific Northwest Laboratory on a variety of spent uranium oxide fuels designated as Approved Testing Materials (ATMs). These ATMs have a variety of burnup levels, fission gas releases, and include fuel from both pressurized water and boiling water reactor designs. The purpose of this work is to provide a source of well-characterized spent fuel for testing in the US Department of Energy Office of Civilian Radioactive Waste Management (OCRWM) repository programs and potentially other programs. Details of these characterization studies for some of the ATMs are available. 7 refs., 8 figs., 1 tab
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Mar 1989; 20 p; 91. annual meeting of the American Ceramic Society; Indianapolis, IN (USA); 23-27 Apr 1989; CONF-890421--4; Available from NTIS, PC A03/MF A01 - OSTI; 1 as DE89011217; Portions of this document are illegible in microfiche products.
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Report
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Conference
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ACTINIDE COMPOUNDS, CHALCOGENIDES, ENERGY SOURCES, ENRICHED URANIUM REACTORS, FUEL ELEMENTS, FUELS, ISOTOPES, MANAGEMENT, MATERIALS, NUCLEAR FUELS, OXIDES, OXYGEN COMPOUNDS, POWER REACTORS, RADIOACTIVE MATERIALS, REACTOR COMPONENTS, REACTOR MATERIALS, REACTORS, THERMAL REACTORS, URANIUM COMPOUNDS, WASTE DISPOSAL, WASTES, WATER COOLED REACTORS, WATER MODERATED REACTORS
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