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Sung, Haejung; Lee, Sang Ik; Park, Ju-Hyun; Choi, Tong-Soo
Proceedings of the KNS 2016 Autumn Meeting2016
Proceedings of the KNS 2016 Autumn Meeting2016
AbstractAbstract
[en] U.S. Nuclear Regulatory Commission (US-NRC) has been reviewing the design certification application for APR1400 submitted by Korea Electric Power Corporation (KEPCO). The main concern about cold leg top slot break is that cladding temperature might be increased by core uncover due to four loop seal reformation following flooding of safety injection water. An integral effect test for cold leg top slot break was performed by KAERI (Korea Atomic Energy Research Institute) using ATLAS (Advanced Thermal-Hydraulic Test Loop for Accident Simulation), which is a scaled down experimental facility for APR1400. In this study, RELAP5/MOD3.3/Patch04 is assessed by experimental result of ATLAS cold leg top slot break. Also, thermal hydraulic phenomena by four loop seals reformation is observed by RELAP5 result. The RELAP5/MOD3.3/Patch04 is assessed by the experimental result of ATLAS cold leg top slot break. The top slot break is described by offtake model, and the mass flow rate is fairly well estimated. The RELAP5 well predicts the correlation between general trend and four loop seal reformation. The pressure of the core region and the cladding temperature tends to increase during four loop seal reformation due to steam path blockage on four loop seals. It is presumed that the code cannot estimate two phase phenomena by loop seal clearing as same as experiments. In terms of cladding temperature, loop seal reformation due to loop seal elevation of APR1400 does not need to be the issue, since the void fraction at the active top core is maintained over 0.4
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Korean Nuclear Society, Daejeon (Korea, Republic of); [1 CD-ROM]; Oct 2016; [4 p.]; 2016 Autumn Meeting of the KNS; Kyungju (Korea, Republic of); 26-28 Oct 2016; Available from KNS, Daejeon (KR); 2 refs, 7 figs, 2 tabs
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Miscellaneous
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Conference
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