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Volume 43 Issue 3
Jun.  2022
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Shi Jin, Guo Donghai. Research on Optimization of Post-72h Procedures for Passive Nuclear Power Plant[J]. Nuclear Power Engineering, 2022, 43(3): 185-189. doi: 10.13832/j.jnpe.2022.03.0185
Citation: Shi Jin, Guo Donghai. Research on Optimization of Post-72h Procedures for Passive Nuclear Power Plant[J]. Nuclear Power Engineering, 2022, 43(3): 185-189. doi: 10.13832/j.jnpe.2022.03.0185

Research on Optimization of Post-72h Procedures for Passive Nuclear Power Plant

doi: 10.13832/j.jnpe.2022.03.0185
  • Received Date: 2021-04-26
  • Accepted Date: 2021-04-26
  • Rev Recd Date: 2022-04-11
  • Publish Date: 2022-06-07
  • Post-72h procedures are special procedures for passive nuclear power plants. In order to evaluate the necessity and sufficiency of post-72 h procedures for passive nuclear power plants, and optimize and improve their weak links, this study analyzes the overall logic of the design basis and operating procedure system for passive nuclear power plants in demonstration projects. Based on the content and structure of the post-72 h procedures, this study proposes a general method for evaluating the necessity and sufficiency of the post-72 h procedures, the possible risk items in the process of procedure implementation are identified by using the logical block diagram of procedure implementation, and some optimization suggestions are put forward according to the rules of the demonstration project. The analysis results show that the post-72 h procedures are sufficient and necessary for the safe operation of passive nuclear power plants; their expressions are related to the procedure architecture; Clarifying the priority of procedure operation path and reducing procedure jump can improve the efficiency of procedure implementation. The relevant optimization suggestions can provide technical reference for the long-term safe operation of passive nuclear power plants after accidents.

     

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  • [1]
    国家核安全局. 核动力厂运行安全规定: HAF 103—2004[S]. 北京: 国家核安全局, 2004: 1-25.
    [2]
    叶道权. 三门核电AP1000运行规程特点及管理浅析[C]//中国核学会. 中国核科学技术进展报告(第四卷)——中国核学会2015年学术年会论文集第3册(核能动力分卷(下)). 北京: 中囯原子能出版社, 2015: 135-139.
    [3]
    国家核安全局. 核动力厂设计安全规定: HAF 102—2016[S]. 北京: 国家核安全局, 2016: 1-62.
    [4]
    施锦. 核电厂运行规程整定值研究[J]. 核动力工程,2017, 38(2): 134-139.
    [5]
    阎昌琪, 曹夏昕. 核反应堆安全传热[M]. 哈尔滨: 哈尔滨工程大学出版社, 2010: 79.
    [6]
    Institute of Nuclear Power Operations. Human performance tools for workers: INPO 06-002[R]. Atlanta: INPO, 2006.
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