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Development and Application of a Sensitivity and Uncertainty Analysis Framework for Safety Analysis of Molten Salt Reactors

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  • Haijun Liu

    (School of Physical Science and Technology, ShanghaiTech University, Shanghai 201210, China
    Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, China)

  • Rui Li

    (Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, China)

  • Xiandi Zuo

    (Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, China)

  • Maosong Cheng

    (Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, China
    University of Chinese Academy of Sciences, Beijing 100049, China)

  • Shichao Chen

    (Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, China)

  • Zhimin Dai

    (School of Physical Science and Technology, ShanghaiTech University, Shanghai 201210, China
    Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, China
    University of Chinese Academy of Sciences, Beijing 100049, China)

Abstract

To provide reliable safety margins in reactor design and safety analysis, the best estimate plus uncertainty (BEPU) analysis, which is recommended by the International Atomic Energy Agency (IAEA), has drawn increasing attention worldwide. In order to systematically evaluate the sensitivity and uncertainty in the design and safety analysis of molten salt reactors (MSRs), a sensitivity and uncertainty analysis framework has been developed by integrating the reactor system safety analysis code RELAP5-TMSR with the data analysis code RAVEN. The framework is tested using the transient scenarios of the molten salt reactor experiment (MSRE): reactivity insertion accident (RIA) and station blackout (SBO). The testing results demonstrate that the proposed framework effectively conducts sensitivity and uncertainty analysis. Sensitivity analyses identify key input parameters, including the primary exchanger parameters, air radiator parameters, initial temperatures, delayed neutron parameters and volumetric heat capacity of the INOR-8 alloy. Uncertainty quantification provides 95% confidence intervals for the figures of merit (FOMs) and the steady-state and RIA scenarios remained within safety limits. The developed framework enables automated, efficient, and high-capacity sensitivity and uncertainty analysis across multiple parameters and transient scenarios. The systematic analysis provides sensitivity indicators and uncertainty distributions, offering quantitative insights into the safety margins and supporting the design and safety analysis of MSRs.

Suggested Citation

  • Haijun Liu & Rui Li & Xiandi Zuo & Maosong Cheng & Shichao Chen & Zhimin Dai, 2025. "Development and Application of a Sensitivity and Uncertainty Analysis Framework for Safety Analysis of Molten Salt Reactors," Energies, MDPI, vol. 18(9), pages 1-25, April.
    • Handle: RePEc:gam:jeners:v:18:y:2025:i:9:p:2179-:d:1641570
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    References listed on IDEAS

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    1. Helton, J.C. & Johnson, J.D. & Sallaberry, C.J. & Storlie, C.B., 2006. "Survey of sampling-based methods for uncertainty and sensitivity analysis," Reliability Engineering and System Safety, Elsevier, vol. 91(10), pages 1175-1209.
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