Application of PSA Technology in Technical Requirements Optimization of Nuclear Power Plant

被引:1
|
作者
Yu, Xipeng [1 ]
Yang, Zhi [1 ]
机构
[1] Suzhou Nucl Power Res Inst, Nucl Safety & Operat Technol Ctr, Suzhou, Jiangsu, Peoples R China
来源
2022 4TH INTERNATIONAL CONFERENCE ON SYSTEM RELIABILITY AND SAFETY ENGINEERING, SRSE | 2022年
关键词
probabilistic safety analysis; risk-informed; technical requirements; incremental conditional probability;
D O I
10.1109/SRSE56746.2022.10067287
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Probabilistic safety analysis (PSA) technology has become the mainstream analysis method in the world to support the daily risk management and safety decision-making in nuclear power plants. A series of regulatory guidelines issued by the US Nuclear Regulatory Commission are used to guide the application for change of technical specifications, effectively improving the reliability of equipment. As for the unavailability of REA boration or RCV charging line, a nuclear power plant in China has optimized the transfer process of corresponding event procedures. In this paper, the risk-informed analysis technology is applied to analyze and determine whether the technical requirements related to the events could be optimized.
引用
收藏
页码:133 / 138
页数:6
相关论文
共 50 条
  • [31] OPTIMIZATION OF A NUCLEAR POWER PLANT BY HYBRID COMPUTER
    KOVACS, JJ
    COMPUTERS AND AUTOMATION, 1968, 17 (07): : 26 - &
  • [32] Development and Application of Guided Wave Technology for Buried Piping Inspection in Nuclear Power Plant
    Pei Kuang-Chih
    Shyu Hung-Fa
    Lee Ping-Hung
    Toung Jean-Chung
    2015 IEEE INTERNATIONAL ULTRASONICS SYMPOSIUM (IUS), 2015,
  • [33] The application of virtual reality technology to the conical roof lifting for the AN 000 nuclear power plant
    Shen Yang
    Shen Hongwei
    PROCEEDINGS OF THE 21ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2013, VOL 2, 2014,
  • [34] APPLICATION OF VIRTUAL REALITY TECHNOLOGY IN HUMAN FACTORS VERIFICATION OF NUCLEAR POWER PLANT DESIGN
    Hao, Dong
    Fan, YanFang
    Bai, BingHe
    PROCEEDINGS OF 2024 31ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, VOL 4, ICONE31 2024, 2024,
  • [35] Discussion on Application of FPGA Technology in Safety Instrument and Control System of Nuclear Power Plant
    Yang, Jing-Yuan
    Wu, Qi
    Wang, Xin-Yu
    Han, Shao-Hua
    NUCLEAR POWER PLANTS: INNOVATIVE TECHNOLOGIES FOR INSTRUMENTATION AND CONTROL SYSTEMS, 2018, 455 : 94 - 101
  • [36] DEVELOPMENT OF NUCLEAR POWER TECHNICAL SCHOOL IN RHEINSBERG-TRAINING-AND-EXPERIMENTAL-NUCLEAR-POWER-PLANT
    FLACH, G
    HIERSEMA.R
    KERNENERGIE, 1971, 14 (05): : 159 - &
  • [37] Application of CSA to loading pattern optimization problems for reload core in nuclear power plant
    Hu, Yuying
    Liao, Hongkuan
    Li, Qing
    Yu, Yingrui
    He, Caiyun
    Li, Tianya
    Chen, Feifei
    ANNALS OF NUCLEAR ENERGY, 2024, 203
  • [38] REQUIREMENTS TO REGULATIONS OF NUCLEAR-POWER PLANT EQUIPMENTS CONTROL
    IMRE, B
    ENERGIA ES ATOMTECHNIKA, 1976, 29 (11): : 496 - 497
  • [39] Code Requirements for Fuel Handling Equipment at Nuclear Power Plant
    Chang, Sang-Gyoon
    Kang, Tae-Kyo
    Kim, Jong-Min
    Jung, Jong-Pil
    JOURNAL OF NUCLEAR FUEL CYCLE AND WASTE TECHNOLOGY, 2022, 20 (01): : 119 - 126
  • [40] Teamwork competence requirements in nuclear power plant control rooms
    Skjerve, A. B.
    Kaarstad, M.
    Holmgren, L.
    SAFETY, RELIABILITY AND RISK ANALYSIS: BEYOND THE HORIZON, 2014, : 401 - 408