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Uncertainty analysis of loss of coolant flow accident in lead–bismuth reactor using subchannel code
NUCLEAR ENERGY SCIENCE AND ENGINEERING | 更新时间：2024-10-25
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    • Uncertainty analysis of loss of coolant flow accident in lead–bismuth reactor using subchannel code

    • “In the field of reactor thermal engineering, the SUBCHANFLOW program can improve computational reliability and provide reference for design through uncertainty analysis methods.”
    • NUCLEAR TECHNIQUES   Vol. 47, Issue 8, Article number: 080603(2024)

    • DOI：10.11889/j.0253-3219.2024.hjs.47.080603    

      CLC： TL425

    • Received：07 November 2023，

      Revised：13 January 2024，

      Published：15 August 2024

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  • WANG Kai,YANG Junkang,ZHAO Pengcheng.Uncertainty analysis of loss of coolant flow accident in lead–bismuth reactor using subchannel code[J].NUCLEAR TECHNIQUES,2024,47(08):080603-080603. DOI： 10.11889/j.0253-3219.2024.hjs.47.080603.

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HE Zhaozhong
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Related Institution

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