Risk Assessment of Test Cycle Change of Important Equipment in Nuclear Power Plant

被引:0
作者
Yu, Xipeng [1 ,2 ]
Dai, Hongwei [1 ,2 ]
机构
[1] Suzhou Nucl Power Res Inst Co Ltd, Nucl Safety & Operat Technol Ctr, Suzhou, Peoples R China
[2] Natl Engn Res Ctr ChinaNucl Power Plant Safety &, Suzhou, Peoples R China
来源
2024 6TH ASIA ENERGY AND ELECTRICAL ENGINEERING SYMPOSIUM, AEEES 2024 | 2024年
关键词
probabilistic safety analysis; hydro test pump diesel generator system; incremental risk; nuclear power plant; test cycle;
D O I
10.1109/AEEES61147.2024.10544950
中图分类号
TM [电工技术]; TN [电子技术、通信技术];
学科分类号
0808 ; 0809 ;
摘要
Probabilistic safety analysis (PSA) has become the main method in the world to quantitatively calculate the reactor risk increment when the nuclear power plant equipment is not available and to support the nuclear power plant in making risk decisions. When analyzing the periodic test data of the hydro test pump diesel generator system (LLS001AP) in a domestic nuclear power plant, it is found that the number of start-up failures of the hydro test pump diesel generator set is significantly increased compared with the previous one. To cooperate with the maintenance profession to find out the cause of the fault, the nuclear power plant needs to increase the frequency of the periodic test of the hydro test pump diesel generator system. In this paper, probability safety analysis technology is used to analyze and judge whether the frequency of periodic tests of the hydro test pump diesel generator system can be increased. Ensure safe and stable operation of the nuclear reactor after changing the frequency of periodic tests.
引用
收藏
页码:378 / 382
页数:5
相关论文
共 50 条
  • [31] Planning a fuel run with a fixed operating cycle of a nuclear power plant
    Oshkanov, NN
    ATOMIC ENERGY, 2001, 91 (06) : 1035 - 1036
  • [32] A Bayesian Network Approach for Modeling Dependent Seismic Failures in a Nuclear Power Plant Probabilistic Risk Assessment
    Segarra, Jonathan DeJesus
    Bensi, Michelle
    Modarres, Mohammad
    RELIABILITY ENGINEERING & SYSTEM SAFETY, 2021, 213
  • [33] Assessment of the radiological impact of a decommissioned nuclear power plant in Italy
    Petraglia, A.
    Sabbarese, C.
    De Cesare, M.
    De Cesare, N.
    Quinto, F.
    Terrasi, F.
    D'Onofrio, A.
    Steier, P.
    Fifield, L. K.
    Esposito, A. M.
    RADIOPROTECTION, 2012, 47 (02) : 285 - 297
  • [34] Assessment of the floor response spectra of the Ignalina nuclear power plant
    Bausys, R
    Dundulis, G
    Kacianauskas, R
    Markauskas, R
    Stupak, S
    Uspuras, E
    EARTHQUAKE RESISTANT ENGINEERING STRUCTURES V, 2005, 81 : 809 - +
  • [35] Safety Assessment Framework for Nuclear Power Plant Decommissioning Workers
    Kim, Hyungjun
    Lee, Donghyun
    Lee, Choong Wie
    Kim, Hee Reyoung
    Lee, Seung Jun
    IEEE ACCESS, 2019, 7 : 76305 - 76316
  • [36] Requalification Experimental Study on Life Extension of Electrical Instrument Equipment in Nuclear Power Plant
    Chen Q.
    Guo X.
    Gao X.
    Qiu X.
    Wang G.
    Duan X.
    Zhao C.
    Jiang S.
    Hedongli Gongcheng/Nuclear Power Engineering, 2022, 43 (05): : 217 - 222
  • [37] Project Construction and Important Technical Innovation for Qinshan Phase Ⅲ (PHWR) Nuclear Power Plant
    Third Qinshan Nuclear Power Co.Ltd
    EngineeringSciences, 2007, (04) : 98 - 117
  • [38] Vibration Monitoring of Nuclear Power Plant Containment Buildings During the Integrated Leakage Rate Test for Structural Condition Assessment
    Eiras, J. N.
    Payan, C.
    Rakotonarivo, S.
    Spalvier, A.
    Garnier, V
    JOURNAL OF NONDESTRUCTIVE EVALUATION, DIAGNOSTICS AND PROGNOSTICS OF ENGINEERING SYSTEMS, 2022, 5 (03):
  • [39] Assessment and design of nuclear power plant structures under external explosions
    Dong, Z. F.
    Ma, L. L.
    Jia, J. Y.
    Wu, H.
    Jia, P. C.
    ANNALS OF NUCLEAR ENERGY, 2023, 180