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Improvement and validation of the delayed neutron precursor transport model in RELAP5 code for liquid fuel molten salt reactor
NUCLEAR ENERGY SCIENCE AND ENGINEERING | 更新时间：2024-10-25
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    • Improvement and validation of the delayed neutron precursor transport model in RELAP5 code for liquid fuel molten salt reactor

    • “New progress has been made in the safety analysis of liquid fuel molten salt reactors. Based on the one-dimensional delayed neutron precursor nuclear transport model and the second-order Godunov numerical method, the RELAP5/Mod 4.0 point reactor model has been extended, providing a solution for the safety analysis of liquid fuel molten salt reactors.”
    • NUCLEAR TECHNIQUES   Vol. 44, Issue 6, Article number: 060603(2021)

    • DOI：10.11889/j.0253-3219.2021.hjs.44.060603    

      CLC： TL426

    • Received：21 January 2021，

      Revised：28 April 2021，

      Published：15 June 2021

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  • LI Rui,CHENG Maosong,DAI Zhimin.Improvement and validation of the delayed neutron precursor transport model in RELAP5 code for liquid fuel molten salt reactor[J].NUCLEAR TECHNIQUES,2021,44(06):89-97. DOI： 10.11889/j.0253-3219.2021.hjs.44.060603.

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