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Wilson, C.L.; Hesson, G.M.; Pilger, J.P.; King, L.L.; Panisko, F.E.
Pacific Northwest Lab., Richland, WA (United States). Funding organisation: Nuclear Regulatory Commission, Washington, DC (United States)1993
Pacific Northwest Lab., Richland, WA (United States). Funding organisation: Nuclear Regulatory Commission, Washington, DC (United States)1993
AbstractAbstract
[en] This is a report on one of a series of experiments to simulates a loss-of-coolant accident (LOCA) using full-length fuel rods for pressurized water reactors (PWR). The experiments were conducted by Pacific Northwest Laboratory (PNL) under the LOCA simulation Program sponsored by the US Nuclear Regulatory Commission (NRC). The major objective of this program was causing the maximum possible expansion of the cladding on the fuel rods from a short-term adiabatic temperature transient to 1200 K (1700 F) leading to the rupture of the cladding; and second, by reflooding the fuel rods to determine the rate at which the fuel bundle is cooled
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Source
Sep 1993; 104 p; CONTRACT AC06-76RL01830; Available from OSTI as DE94000499; NTIS; US Govt. Printing Office Dep
Record Type
Report
Report Number
Country of publication
ACCIDENTS, ENERGY TRANSFER, ENRICHED URANIUM REACTORS, FAILURES, FUEL ELEMENTS, HEAVY WATER COOLED REACTORS, HEAVY WATER MODERATED REACTORS, IRRADIATION REACTORS, ISOTOPE PRODUCTION REACTORS, NATURAL URANIUM REACTORS, POWER REACTORS, REACTOR ACCIDENTS, REACTOR COMPONENTS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, SAFETY, TANK TYPE REACTORS, TEST FACILITIES, TEST REACTORS, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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