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Kim, J. K.; Park, S. H.; Sin, C. H.; Park, K. C.; Lee, J. H.
Proceedings of the KNS autumn meeting2000
Proceedings of the KNS autumn meeting2000
AbstractAbstract
[en] Fast neutron fluence was evaluated for KNGR RPV using Monte Carlo code, MCNP and 3-D discrete ordinates code, TORT. The power distributions were calculated by ROCS code. Number density of 38 assemblies and reactor composition materials were calculated by using CASMO run, and the weighted fission spectrum from U-235 and Pu-239 was used as neutron source for MCNP and TORT. BUGLE96 was used for nuclear interaction data in TORT run and continuous nuclear interaction data was in MCNP run. As a result, the both runs give maximum values near 34 .deg. C, and TORT gives 3.19x1010 and MCNP gives 2.769x1010
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Korean Nuclear Society, Taejon (Korea, Republic of); [CD-ROM]; Oct 2000; [9 p.]; 2000 autumn meeting of the KNS; Taejon (Korea, Republic of); 26-27 Oct 2000; Available from KNS, Taejon (KR); 10 refs, 6 figs, 1 tab
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