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LOCA analysis of BWR-4/Mark-I nuclear power plant with TRACE
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LOCA analysis of BWR-4/Mark-I nuclear power plant with TRACE

J.-J. Huang, S.-W. Chen, J.-R. Wang, C. ShihH.-T. Lin
Kerntechnik, 卷.86(2), 頁碼.128-142
04/2021

摘要

Radiation Nuclear and High Energy Physics Nuclear Energy and Engineering Materials Science (all) Safety Risk Reliability and Quality
This study established an RCS-Containment coupled model that integrates the reactor coolant system (RCS) and the containment system by using the TRACE code. The coupled model was used in both short-term and long-term loss of coolant accident (LOCA) analyses. Besides, the RELAP5/CONTAN model that only contains the containment system was also developed for comparison. For short-term analysis, three kinds of LOCA scenarios were investigated: the recirculation line break (RCLB), the main steam line break (MSLB), and the feedwater line break (FWLB). For long-term analysis, the dry-well and suppression pool temperature responses of the RCLB were studied. The analysis results of RELAP5/CONTAN and TRACE models are benchmarked with those of FSAR and RELAP5/GOTHIC models, and it appears that the results of the above four models are consistent in general trends.

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