Study on HRA Method in Seismic PSA of Nuclear Power Plants

Wang H; ing

Volume 41 Issue 4

Aug. 2020

Turn off MathJax

Article Contents

Abstract

References

Article Navigation > Nuclear Power Engineering > 2020 > 41(4): 116-121

Wang H, ing. Study on HRA Method in Seismic PSA of Nuclear Power Plants[J]. Nuclear Power Engineering, 2020, 41(4): 116-121.

Citation:

Wang H, ing. Study on HRA Method in Seismic PSA of Nuclear Power Plants[J]. Nuclear Power Engineering, 2020, 41(4): 116-121.

Wang H, ing. Study on HRA Method in Seismic PSA of Nuclear Power Plants[J]. Nuclear Power Engineering, 2020, 41(4): 116-121.

Citation:

Wang H, ing. Study on HRA Method in Seismic PSA of Nuclear Power Plants[J]. Nuclear Power Engineering, 2020, 41(4): 116-121.

PDF( 0 KB)

Study on HRA Method in Seismic PSA of Nuclear Power Plants

Wang H,
ing

Publish Date: 2020-08-15

Abstract

Abstract

External event Human Reliability Analysis (HRA) is different from the HRA in the internal event level PSA. Therefore, based on the investigation of the development history and method defects of the HRA of external events, the technical standards of the reliability analysis of external events at home and abroad are studied, and the human events in the seismic PSA of a nuclear power plant are taken as the research object. The method study illustrates the difference between the seismic HRA and the internal events HRA, the process of the seismic human response, and the analysis method of the human reliability under the earthquake, so that the analysis results obtained are closer to the actual situation of the external event, and it can provide a technical basis for the development of external event PSA.
- External events,
- Seismic probabilistic safety assessment (PSA),
- Human reliability,
- Method

FullText(HTML)

References(0)

References

Relative Articles

[1]	Zheng Tengjiao, Zhang Jiajia, Hou Jie, Xu Yunlong, Xu Qingqing. Research on the Application of IDHEAS Human Event Dependency Analysis Method[J]. Nuclear Power Engineering, 2024, 45(6): 213-219. doi: 10.13832/j.jnpe.2024.06.0213
[2]	Wei Wentao, Li Meifu, Zhu Dahuan, Zhong Mingjun, Guo Yongjin, Du Zhengyu, Jiang Xiaowei. Research on Reliability Evaluation Method of Nuclear Energy System Based on Dynamic Bayesian Network[J]. Nuclear Power Engineering, 2023, 44(S2): 109-114. doi: 10.13832/j.jnpe.2023.S2.0109
[3]	Wang Wenhui, Wan Anping, Deng Chaojun, Gong Zhipeng, Zhang Hongliang, Ye Yanghan, Wang Pengfei, Liu Canxian, Li Yuezhang. Reliability Evaluation Method of Bolts of Reactor Internals in High-neutron-fluence-rate Region Based on XGBoost[J]. Nuclear Power Engineering, 2022, 43(5): 154-162. doi: 10.13832/j.jnpe.2022.05.0154
[4]	Zhang Yongfa, Jiang Lizhi, Cai Qi, Liu Xiaoya, Jiao Meng. Reliability Evaluation of Passive System for Nuclear Power Plant Based on Improved Multi-Level Cross Entropy Method[J]. Nuclear Power Engineering, 2021, 42(4): 186-190. doi: 10.13832/j.jnpe.2021.04.0186
[5]	Chen Shuai, Zhang Li, Qing Tao, Lin Yaozu, Li Linfeng, Chen Chao. Assessment Model of Operator’s Implementation Reliability for Portable Equipment in Nuclear Power Plants[J]. Nuclear Power Engineering, 2020, 41(4): 128-134.
[6]	Li Lusu, Su Xiaoyan, Qian Hong, Zhou Jie. Research on Dependence Assessment in Human Reliability Analysis of Nuclear Power Plants[J]. Nuclear Power Engineering, 2020, 41(3): 147-152. doi: 10.13832/j.jnpe.2020.03.0147
[7]	Zhao Xinwen, Guo Haikuan, Cai Qi, Deng Chunrui. Reliability of Passive Residual Heat Removal System Based on PSA[J]. Nuclear Power Engineering, 2020, 41(4): 122-127.
[8]	Wang Baosheng, Tang Xiuhuan, Bao Lihong, Zhu Lei, Sun Peiwei. Research of Functional Reliability Evaluation Method for Passive Systems Based on Data Mining Technology[J]. Nuclear Power Engineering, 2020, 41(2): 78-83.
[9]	Wang Baosheng, Tang Xiuhuan, Zhu Lei, Bao Lihong, Shan Jianqiang. Application of Functional Reliability Assessment Method in Reliability Analysis of XAPR Reactor Core Natural Circulation[J]. Nuclear Power Engineering, 2019, 40(2): 161-166. doi: 10.13832/j.jnpe.2019.02.0161
[10]	Zhang Wenguang, Yang Chenggang, Sun Zhan, Zhang Yue. Discussion on Reviewing of Reliability Assurance Program for Nuclear Power Plants[J]. Nuclear Power Engineering, 2018, 39(6): 141-145. doi: 10.13832/j.jnpe.2018.06.0141
[11]	Qin Feng, Zhu Guixia, Qiao Zhen, Guo Longzhang. Study on Classification Method for NPP Equipment Reliability Based on AP913[J]. Nuclear Power Engineering, 2017, 38(6): 103-106. doi: 10.13832/j.jnpe.2017.06.0103
[12]	Guo Haikuan, Zhao Xinwen, CAi Qi, Zhang Yongfa, Huang Liqin. Integrating Reliability of Passive Residual Heat Removal System for AP1000 into Probabilistic Safety Assessment[J]. Nuclear Power Engineering, 2017, 38(6): 9-13. doi: 10.13832/j.jnpe.2017.06.0009
[13]	Liu Ying, Yang Ming. Evaluation of Nuclear Safety-Critical Software Reliability of DCS[J]. Nuclear Power Engineering, 2016, 37(1): 143-147. doi: 10.13832/j.jnpe.2016.01.0143
[14]	CHEN Le, XIE Meng, PEI Qilin, DAI Xun, XU Chunrong. Reliability of Test and Measurement for Hydride Reorientation[J]. Nuclear Power Engineering, 2015, 36(1): 55-59. doi: 10.13832/j.jnpe.2015.01.0055
[15]	Gao Weiguang. Research of Reliability Statistical Method for Equipment of Fangjiashan Nuclear Power Plant[J]. Nuclear Power Engineering, 2015, 36(S1): 99-102. doi: 10.13832/j.jnpe.2015.S1.0099
[16]	CHI Miao, YANG Ming, SHI Liping. Methodology Study on Safety-Critical Software Reliability Evaluation of Digital I＆C Systems at Nuclear Power Plants[J]. Nuclear Power Engineering, 2015, 36(1): 177-181. doi: 10.13832/j.jnpe.2015.01.0177
[17]	REN Shu-hong, XUE Fei, YU Weiwei, TI Wen-xin, LIU Xiao-tian. Reliability Residual-Life Prediction Method for Thermal Aging Based on Performance Degradation[J]. Nuclear Power Engineering, 2013, 34(5): 96-99.
[18]	WU Guangjiang, WANG Yong, SHANG Yanlong, YAN Canbin. Reliability Analysis of Repairable System Based on GO-FLOW Methodology[J]. Nuclear Power Engineering, 2012, 33(2): 25-29.
[19]	YU Shaojie, ZHAO Jun, TONG Jiejuan. Application of DFM in Human Reliability Analysis[J]. Nuclear Power Engineering, 2011, 32(4): 77-82.
[20]	YANG Ming, ZHANG Zhijian. Study on Quantitative Reliability Analysis by Multilevel Flow Models for Nuclear Power Plants[J]. Nuclear Power Engineering, 2011, 32(4): 72-76.