• Title/Summary/Keyword: Nuclear Safety

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The Improvement of China's Nuclear Safety Supervision Technical Support Ability

  • Han Wu;Guoxin Yu;Xiangyang Zheng;Keyan Teng
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.20 no.4
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    • pp.523-531
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    • 2022

  • The International Atomic Energy Agency (IAEA) entails independent decision-making for the safety supervision of civil nuclear facilities. To evaluate and review the safety of nuclear facilities, the national regulatory body usually consults independent institutions or external committees. Technical Support Organizations (TSOs) include national laboratories, research institutions, and consulting organizations. Support from professional organizations in other countries may also be required occasionally. Most of the world's major nuclear power countries adopt an independent nuclear safety supervision model. Accordingly, China has continuously improved upon the construction of such a system by establishing the National Nuclear Safety Administration (NNSA) as the decision-making department for nuclear and radiation safety supervision, six regional safety supervision stations, the Nuclear and Radiation Safety Center (NSC), a nuclear safety expert committee, and the National Nuclear and Radiation Safety Supervision Technology R&D Base, which serves as the test, verification, and R&D platform for providing consultation and technical support. An R&D system, however, remains to be formed. Future endeavors must focus on improving the technical support capacity of these systems. As an enhancement from institutional independence to capability independence is necessary for ensuring the independence of China's nuclear safety regulatory institution, its regulatory capacity must be improved in the future.

  • https://doi.org/10.7733/jnfcwt.2022.037 인용 PDF KSCI

Safety Review Experience of Computerized Logic System for YGN 3 and 4

  • Yun, Won-Young;Kim, Dae-Il;Koh, Jong-Soo;Kim, Bok-Ryul;Oh, Sung-Hun;Lim, Jang-Hyun
    • Proceedings of the Korean Nuclear Society Conference
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    • 1995.05a
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    • pp.602-607
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    • 1995

  • This article presents safety review experience of microprocessor-based Interposing Logic System(ILS) of Engineering Safety Feature Actuation System(ESFAS). The ILS is the first application of computerized logic design to safety system in Korean nuclear power plants without verification of the system reliability by proven technology concept. As a result of evaluation for the ILS, Korea Institute of Nuclear Safety(KINS) concluded that the microprocessor-based ILS is not acceptable in some features detailed enough to defend against software common mode failures(CMF). Therefore, we required licensee to install hardwired interlock signal configuration and a Hardwired Backup Panel to control safety-related equipment. We believe that the microprocessor-based ILS with the hardwired backup panel and inter-connection of interlock signal by hardwired configuration will improve the plant safety.

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A rapid modeling method and accuracy criteria for common-cause failures in Risk Monitor PSA model

  • Zhang, Bing;Chen, Shanqi;Lin, Zhixian;Wang, Shaoxuan;Wang, Zhen;Ge, Daochuan;Guo, Dingqing;Lin, Jian;Wang, Fang;Wang, Jin
    • Nuclear Engineering and Technology
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    • v.53 no.1
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    • pp.103-110
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    • 2021

  • In the development of a Risk Monitor probabilistic safety assessment (PSA) model from the basic PSA model of a nuclear power plant, the modeling of common-cause failure (CCF) is very important. At present, some approximate modeling methods are widely used, but there lacks criterion of modeling accuracy and error analysis. In this paper, aiming at ensuring the accuracy of risk assessment and minimizing the Risk Monitor PSA models size, we present three basic issues of CCF model resulted from the changes of a nuclear power plant configuration, put forward corresponding modeling methods, and derive accuracy criteria of CCF modeling based on minimum cut sets and risk indicators according to the requirements of risk monitoring. Finally, a nuclear power plant Risk Monitor PSA model is taken as an example to demonstrate the effectiveness of the proposed modeling method and accuracy criteria, and the application scope of the idea of this paper is also discussed.

  • https://doi.org/10.1016/j.net.2020.06.021 인용 PDF KSCI

Geological Safety Evaluation and Monitoring of Nuclear Facility Sites in South Korea

  • Lee, Hyunwoo;Woo, Hyeon Dong;Chun, Hyun Ju;Im, Chang-Bock
    • The Journal of Engineering Geology
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    • v.24 no.4
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    • pp.609-613
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    • 2014

  • The Korean Peninsula, located at the southeastern tip of the Eurasian Plate, is known to be tectonically stable, and no critical evidence has yet been found that would override the safety design of nuclear facilities in South Korea. Because a nuclear power plant, like other major social overhead capital facilities, could cause great damage to both the environment and society through an unexpected tectonic event, even one of extremely low probability, like the Fukushima accident, a defense-in-depth safety approach is required in geological and geotechnical site safety evaluation for nuclear projects. This paper introduces the regulatory procedures that are in place to confirm nuclear site safety and site monitoring (e.g., earthquakes and groundwater) systems applied to nuclear facilities in order to reduce inherent uncertainties within the site safety review of geological and seismological issues related with a NPP project.

  • https://doi.org/10.9720/kseg.2014.4.609 인용 PDF KSCI KPUBS HTML