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McWethy, L.M.; Pearce, K.L.; Rector, D.R.
Westinghouse Hanford Co., Richland, WA (USA)1988
Westinghouse Hanford Co., Richland, WA (USA)1988
AbstractAbstract
[en] The Experimental Breeder Reactor No. II (EBR-II) irradiation test Uninstrumented Fueled Accelerated (UFAC)-1 of seven encapsulated thermionic test pins was analyzed with the code COBRA-SFS. The model predicted coolant and material temperatures for three conditions of interest: steady state full power, response to the unlikely loss of flow transient, and decay heat cooling by forced down flow of argon. Modeling assumptions and a summary of results are included. 1 ref., 12 figs., 3 tabs
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Sep 1988; 37 p; Available from NTIS, PC A03/MF A01; 1 as DE89002138; Portions of this document are illegible in microfiche products.
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Report
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ACCIDENTS, BREEDER REACTORS, COMPUTER CODES, ENERGY TRANSFER, EPITHERMAL REACTORS, EXPERIMENTAL REACTORS, FAST REACTORS, FBR TYPE REACTORS, FUEL ELEMENTS, LIQUID METAL COOLED REACTORS, LMFBR TYPE REACTORS, POWER REACTORS, REACTOR ACCIDENTS, REACTOR COMPONENTS, REACTORS, RESEARCH AND TEST REACTORS, SAFETY, SODIUM COOLED REACTORS
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