A rapid modeling method and accuracy criteria for common-cause failures in Risk Monitor PSA model |
Zhang, Bing
(State Key Laboratory of Nuclear Power Safety Monitoring Technology and Equipment, China Nuclear Power Engineering Co., Ltd.)
Chen, Shanqi (Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences) Lin, Zhixian (Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences) Wang, Shaoxuan (Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences) Wang, Zhen (Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences) Ge, Daochuan (Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences) Guo, Dingqing (School of Mechanical Engineering, Shanghai Jiao Tong University) Lin, Jian (State Key Laboratory of Nuclear Power Safety Monitoring Technology and Equipment, China Nuclear Power Engineering Co., Ltd.) Wang, Fang (Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences) Wang, Jin (Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences) |
1 | Y.J.B. Lee, T.J. Lin, S.F.M. Liang, Accuracy enhancement in estimation of the initiating event frequencies in risk monitor application on Kuosheng NPP, Ann. Nucl. Energy 76 (2015) 40-47. DOI |
2 | T.E. Wierman, D.M. Rasmuson, A. Mosleh, Common-Cause Failure Database and Analysis System: Event Data Collection, Classification, and Coding. NUREG/CR-6268, U.S. Nuclear Regulatory Commission, 2007. |
3 | A. Mosleh, D.M. Rasmuson, F.M. Marshall, Guidelines on Modeling Common-Cause Failures in Probabilistic Risk Assessment. NUREG/CR-5485, U.S. Nuclear Regulatory Commission, 1998. |
4 | M. Hari Prasad, G. Vinod, V.V.S. Sanyasi Rao, Risk management of NPPs using risk monitors, International Journal of System Assurance Engineering and Management 6 (2) (2015) 191-197. DOI |
5 | J.K. Vaurio, Importance measures in risk-informed decision making: ranking, optimisation and configuration control, Reliab. Eng. Syst. Saf. 96 (11) (2011) 1426-1436. DOI |
6 | F. Wang, J.Q. Wang, J. Wang, Y.Z. Li, L.Q. Hu, Y.C. Wu, Risk monitor RiskAngel for risk-informed applications in nuclear power plants, Ann. Nucl. Energy 91 (2016) 142-147. DOI |
7 | J. Wang, F. Wang, S.Q. Chen, J.Q. Wang, L.Q. Hu, Y. Yin, et al., Fault-tree-based instantaneous risk computing core in nuclear power plant risk monitor, Ann. Nucl. Energy 95 (2016) 35-41. DOI |
8 | H. Yoshikawa, T. Nakagawa, Development of plant DiD Risk Monitor system for NPPs by utilizing UML modelling technology, Ifac Papersonline 49 (19) (2016) 397-402. |
9 | J.Q. Wang, F. Wang, J. Wang, S.Q. Chen, L.Q. Hu, Y.Z. Li, et al., A new importance assessment method for risk-informed SSC categorization, Int. J. Energy Res. 42 (4) (2018) 1779-1786. DOI |
10 | A. O'Connor, A. Mosleh, A general cause based methodology for analysis of common cause and dependent failures in system risk and reliability assessments, Reliab. Eng. Syst. Saf. 145 (2016) 341-350. DOI |
11 | X. He, J. Tong, J. Chen, Maintenance risk management in Daya Bay nuclear power plant: PSA model, tools and applications, Prog. Nucl. Energy 49 (1) (2007) 103-112. DOI |
12 | M. Zhang, Z. Zhang, A. Mosleh, S. Chen, Common cause failure model updating for risk monitoring in nuclear power plants based on alpha factor model, Proc. Inst. Mech. Eng. O J. Risk Reliab. 231 (3) (2017) 209-220. |
13 | C.H. Shepherd, F.J. Yllera, B. Kaufer, D.W. Henneke, D. Gaynor, J. Sedlak, et al., Risk monitors - the state of the art in their development and use at nuclear power plants - produced on behalf of IAEA and OECD/NEA WGRisk, in: Nuclear Energy Agency of the OECD (NEA), 2004, p. 250. |
14 | Z.G. Ma, H. Yoshikawa, T. Nakagawa, M. Yang, Knowledge-based software design for Defense-in-Depth risk monitor system and application for AP1000, J. Nucl. Sci. Technol. 54 (5) (2017) 552-568. DOI |
15 | Office of Nuclear Regulatory Research, An Approach for Plant-specific, Risk-Informed Decisionmaking: Technical Specifications, Regulatory Guide 1.177, U.S. Nuclear Regulatory Commission, 2011. |
16 | F.M. Marshall, D.M. Rasmuson, A. Mosleh, Common-cause Failure Parameter Estimations. NUREG/CR-5497, U.S. Nuclear Regulatory Commission, 1998. |
17 | S. Chen, J. Wang, F. Wang, J. Wang, L. Hu, Asymmetrical common-cause failures analysis method applied in fusion reactors, J. Fusion Energy 35 (2) (2016) 221-228. DOI |
18 | H. Schoonakker, M. van der Borst, in: A. Mosleh, R.A. Bari (Eds.), Treatment of Common Cause Failures in Risk Monitoring, Springer-Verlag London Ltd, Godalming, 1998, pp. 437-442. |
19 | X. Dai, M. Yang, B. Zou, H. Lu, Hierarchical modeling of GO-FLOW models for online risk monitoring of nuclear power plants, in: 2017 25th International Conference on Nuclear Engineering, ICONE, American Society of Mechanical Engineers (ASME), Shanghai, China, 2017. July 2, 2017 - July 6, 2017. |
![]() |