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Shin, Y.W.; Chung, H.; Choi, U.S.; Wiedermann, A.H.; Ockert, C.E.
Argonne National Lab., IL (USA); ATResearch Associates, Glen Ellyn, IL (USA); Department of Energy, Washington, DC (USA)1984
Argonne National Lab., IL (USA); ATResearch Associates, Glen Ellyn, IL (USA); Department of Energy, Washington, DC (USA)1984
AbstractAbstract
[en] Leaks in LMFBR steam generators cannot entirely be prevented; thus the steam generators and the intermediate heat transport system (IHTS) of an LMFBR must be designed to withstand the effects of the leaks. A large-scale leak which might result from a sudden break of a steam generator tube, and the resulting sodium-water reaction (SWR) can generate large pressure pulses that propagate through the IHTS and exert large forces on the piping supports. This paper discusses computer programs for analyzing long-term flow and thermal effects in an LMFBR secondary system resulting from large-scale steam generator leaks, and the status of the development of the codes
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Jul 1984; 3 p; 8. international conference on structural mechanics in reactor technology; Brussels (Belgium); 19-23 Aug 1985; Available from NTIS, PC A02/MF A01 as DE85000079
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Report
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Conference
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