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BEPU Analysis in LBLOCA Safety Review Calculation

Author

Listed:
  • Wei Sun

    (School of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an 710049, China
    Nuclear and Radiation Safety Center, Ministry of Ecology and Environment of the People’s Republic China (MEE), Beijing 100082, China)

  • Chao Xu

    (Nuclear and Radiation Safety Center, Ministry of Ecology and Environment of the People’s Republic China (MEE), Beijing 100082, China)

  • Yi-Zhen Wang

    (Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Collaborative Innovation Center of Advance Nuclear Energy Technology, Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing 100084, China)

  • Sui-Zheng Qiu

    (School of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an 710049, China)

  • Yu-Sheng Liu

    (Nuclear and Radiation Safety Center, Ministry of Ecology and Environment of the People’s Republic China (MEE), Beijing 100082, China)

  • Hao Fu

    (Nuclear and Radiation Safety Center, Ministry of Ecology and Environment of the People’s Republic China (MEE), Beijing 100082, China)

Abstract

Deterministic safety analysis (DSA) is essential for nuclear power plant licensing. The conservative method followed CFR50 Appendix K, which will lead to a large margin. As one of the DSA methodologies, best estimate plus uncertainty (BEPU) generates more realistic results that can be used in the license application of nuclear power plants (NPPs). However, uncertainty evaluation of parameters is needed in BEPU. In this article, the safety regulatory focuses on the large break loss of coolant accident (LBLOCA) of an advanced PWR. The BEPU analysis is mainly performed by TRACE V5.0 patch 4 code, and the uncertainty analysis is conducted based on DAKOTA code. For correlation coefficients analysis, the sample size is enlarged reasonably. According to the results, this NPP meets the acceptance criteria effectively in LBLOCA with enough margin. By statistic assessment, the set of PCTs calculated has typical normal distribution characters. Based on BEPU, the uncertainties of parameters are studied. Additionally, the influence of sample size on the correlation of parameters is considered too. It could be seen that more samples could permit a more accurate estimation for Spearman partial correlation coefficient (abbreviated as SPCC). The conclusions of this article can provide technical support for the subsequent review of the safety analysis report and the design changes of NPPs.

Suggested Citation

  • Wei Sun & Chao Xu & Yi-Zhen Wang & Sui-Zheng Qiu & Yu-Sheng Liu & Hao Fu, 2021. "BEPU Analysis in LBLOCA Safety Review Calculation," Sustainability, MDPI, vol. 13(24), pages 1-13, December.
    • Handle: RePEc:gam:jsusta:v:13:y:2021:i:24:p:14042-:d:706427
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    References listed on IDEAS

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    1. Seungkook Roh & Jae Young Choi, 2020. "Exploring Signals for a Nuclear Future Using Social Big Data," Sustainability, MDPI, vol. 12(14), pages 1-16, July.
    2. Andrea Di Ronco & Francesca Giacobbo & Guglielmo Lomonaco & Stefano Lorenzi & Xiang Wang & Antonio Cammi, 2020. "Preliminary Analysis and Design of the Energy Conversion System for the Molten Salt Fast Reactor," Sustainability, MDPI, vol. 12(24), pages 1-17, December.
    3. Ewelina Chajduk & Paweł Kalbarczyk & Jakub Dudek & Marta Pyszynska & Anna Bojanowska-Czajka & Zbigniew Samczyński, 2020. "Development of Analytical Procedures for Chemical Characterization of Substrates for the Production of TRISO Coated Particles as Nuclear Fuel in High Temperature Gas-Cooled Reactors," Sustainability, MDPI, vol. 12(17), pages 1-13, September.
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