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Study on hydrogen migration behavior in small leakage accident of steam generator of sodium-cooled fast reactor
NUCLEAR ENERGY SCIENCE AND ENGINEERING | 更新时间：2024-10-25
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    • Study on hydrogen migration behavior in small leakage accident of steam generator of sodium-cooled fast reactor

    • “Experts in sodium cooled fast reactors have established a one-dimensional calculation model for small leakage sodium water reactions, providing reference for the layout of secondary loop small leakage detection systems.”
    • NUCLEAR TECHNIQUES   Vol. 42, Issue 1, (2019)

    • DOI：10.11889/j.0253-3219.2019.hjs.42.010603    

      CLC： TL36

    • Received：08 November 2018，

      Revised：13 December 2018，

      Published：10 January 2019

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  • DENG Xinjie,CAO Xuewu.Study on hydrogen migration behavior in small leakage accident of steam generator of sodium-cooled fast reactor[J].NUCLEAR TECHNIQUES,2019,42(01):69-73. DOI： 10.11889/j.0253-3219.2019.hjs.42.010603.

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