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AbstractAbstract
[en] The present study is to assess the applicability of the best-estimate thermal-hydraulic codes, MARS 1.4, for analysis of thermal-hydraulic behavior in PWRs during natural circulation conditions. The code simulates a BETHSY test 4.1a, which was conducted in the integral test facility of BETHSY. The test represents the cooling states of the primary cooling system under two-phase natural circulation and reflux condensation mode with conditions corresponding to the residual power, 2 % of the rated core power value, and a constant pressure of 6.8 MPa at the secondary system. Based on MARS calculations, the major thermal-hydraulic behavior during natural circulation is evaluated and the differences between the experimental and calculated results are identified
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Korean Nuclear Society, Taejon (Korea, Republic of); [CD-ROM]; Oct 2000; [13 p.]; 2000 autumn meeting of the KNS; Taejon (Korea, Republic of); 26-27 Oct 2000; Available from KNS, Taejon (KR); 11 refs, 12 figs, 1 tab
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Miscellaneous
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Conference
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