Simulation-based dynamic probabilistic risk assessment of an internal flooding-initiated accident in nuclear power plant using THALES2 and RAPID

Author:

Kubo Kotaro1ORCID,Zheng Xiaoyu1,Tanaka Yoichi1,Tamaki Hitoshi1,Sugiyama Tomoyuki1ORCID,Jang Sunghyon2,Takata Takashi2,Yamaguchi Akira2

Affiliation:

1. Japan Atomic Energy Agency, Naka-gun, Ibaraki, Japan

2. The University of Tokyo, Tokyo, Japan

Abstract

Probabilistic risk assessment (PRA) is a method used to assess the risks associated with large and complex systems. However, the timing at which nuclear power plant structures, systems, and components are damaged is difficult to handle explicitly if the risk of an external event is evaluated using conventional PRA based on event trees and fault trees. A methodology coupling thermal-hydraulic analysis with external event simulations using Risk Assessment with Plant Interactive Dynamics (RAPID) is therefore proposed to overcome this limitation. A flood propagation model based on Bernoulli’s theorem was applied to represent internal flooding in the turbine building of the pressurized water reactor. Uncertainties were also taken into account, including the flow rate of the floodwater source and the failure criteria for the mitigation systems. The simulated recovery actions included the operator isolating the floodwater source and using a drainage pump; these actions were modeled using several simplifications. Overall, the results indicate that combining isolation and drainage can reduce the conditional core damage probability upon the occurrence of flooding by approximately 90%.

Funder

Information Technology Center at the University of Tokyo

Publisher

SAGE Publications

Subject

Safety, Risk, Reliability and Quality

Reference47 articles.

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2. Schroeder J, Henry D, Ma Z. SPAR model structural efficiencies, INL/EXT-13-28528, Idaho National Laboratory, 2013.

3. Quantitative common cause failure modeling for auxiliary feedwater system involving the seismic-induced degradation of flood barriers

4. Jang S, Suzuki T, Yamaguchi A. Dynamic level 1 PRA of seismic-induced internal flooding in nuclear power plant, In: Proceedings 13th international conference on probabilistic safety assessment and management (PSAM13), 2016, Seoul, Korea.

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