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Volume 45 Issue 3
Jun.  2024
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Ni Man, Zhao Jun, Qian Hongtao, Zhang Jiajia, Gong Yu, Xiao Jun. Study on Risk-informed SSC Safety Classification of High Temperature Gas-cooled Reactor[J]. Nuclear Power Engineering, 2024, 45(3): 193-198. doi: 10.13832/j.jnpe.2024.03.0193
Citation: Ni Man, Zhao Jun, Qian Hongtao, Zhang Jiajia, Gong Yu, Xiao Jun. Study on Risk-informed SSC Safety Classification of High Temperature Gas-cooled Reactor[J]. Nuclear Power Engineering, 2024, 45(3): 193-198. doi: 10.13832/j.jnpe.2024.03.0193

Study on Risk-informed SSC Safety Classification of High Temperature Gas-cooled Reactor

doi: 10.13832/j.jnpe.2024.03.0193
  • Received Date: 2023-06-19
  • Rev Recd Date: 2023-10-15
  • Publish Date: 2024-06-13
  • Risk-informed safety classification is based on probabilistic safety analysis (PSA), which optimizes the traditional deterministic safety classification, thus improving the management requirements of safety classification of nuclear power plants and further enhancing the safety and economy of nuclear power plants. Based on the concept of risk-informed, this paper puts forward the safety classification process of high temperature gas-cooled reactor, and takes the accident discharge system of steam generator (SG) as an example to carry out the risk-informed safety classification study. The results show that the safety SG electromagnetic discharge valve can be classified as safety-related but with low-risk, which means that there is still room for optimization of the safety classification of the system, and can provide reference for the safety classification of structures, systems and components (SSC) in nuclear power plants in the future.

     

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  • [1]
    宫宇,王宝祥,詹文辉,等. 风险指引型安全分级及应用研究[J]. 核安全,2020, 19(5): 41-48.
    [2]
    邓伟,王怡明,杨健,等. 风险指引型方法在“华龙一号”机组设备分级的试点研究[J]. 核科学与工程,2021, 41(3): 515-520. doi: 10.3969/j.issn.0258-0918.2021.03.009
    [3]
    SCHINZEL G E. Experiences gained in implementing a broad-based risk-informed application[C]//Proceedings of the 12th International Conference on Nuclear Engineering. Arlington: ASME, 2004.
    [4]
    NRC. Risk-informed categorization and treatment of structures, systems and components for nuclear power reactors: 10 CFR 50.69[S]. Unite State: Nuclear Regulatory Commission, 2002: 946-948 .
    [5]
    NEI. 10 CFR 50.69 SSC categorization guideline:NEI-00-04[S]. Washington: Nuclear Energy Instutute, 2005:15-68.
    [6]
    国家核安全局. 高温气冷堆核电站示范工程安全审评原则[R]. 北京: 国家核安全局,2008.
    [7]
    姜卓尔,赵军,王海涛,等. 高温气冷堆地震丧失厂外电的风险评价[J]. 原子能科学技术,2021, 55(10): 1814-1820. doi: 10.7538/yzk.2020.youxian.0673
    [8]
    TRUE D, FLEMING K, PARRY G, et al. PSA applications guide. Final report: EPRI-TR-105396[R]. Palo Alto: Electric Power Research Institute, 1995.
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