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AbstractAbstract
[en] In the present study, the capability of the thermal-hydraulic codes, RELAP5/MOD3.2.2 gamma, in predicting the steam-water interaction and the related ECC delivery to lower plenum under downcomer injection condition during refill phase is evaluated using the experimental data of the UPTF Test 21A. The facility is modeled in detail, and the test condition simulated for code calculations. The calculation result is compared with the applicable measurement data and discussed for the pressure response, ECC bypass behavior, lower plenum delivery, global water mass distribution, and local behavior in downcomer
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Source
Korean Nuclear Society, Taejon (Korea, Republic of); [CD-ROM]; Oct 2000; [10 p.]; 2000 autumn meeting of the KNS; Taejon (Korea, Republic of); 26-27 Oct 2000; Available from KNS, Taejon (KR); 8 refs, 8 figs, 1 tab
Record Type
Miscellaneous
Literature Type
Conference; Numerical Data
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