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AbstractAbstract
[en] The LOCA analysis code for the supercritical-water-cooled reactors is developed and validated. The LOCAs of SCLWR and SCFBR are analyzed. By the probabilistic safety assessment, the optimization of safety system will be carried out and the overall probabilistic risk will be estimated. (J.P.N.)
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Tokyo Univ., Tokai, Ibaraki (Japan). Nuclear Engineering Research Lab; 73 p; Mar 1996; p. 6-10; 5. workshop on advanced nuclear reactor, Yayoi Research Group; Tokyo (Japan); 4 Mar 1996
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Report
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