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Development of flow blockage model for core heat transfer and its application in QUENCH experiment
NUCLEAR ENERGY SCIENCE AND ENGINEERING | 更新时间：2024-10-25
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    • Development of flow blockage model for core heat transfer and its application in QUENCH experiment

    • “In a pressurized water reactor coolant loss accident, the deformation of the fuel rod causes blockage of the flow channel, which affects the heat transfer in the core. Researchers improved the channel blockage model and verified its correctness through ISAA-FRTMB simulation experiments to study the impact of cladding deformation on the accident process.”
    • NUCLEAR TECHNIQUES   Vol. 46, Issue 7, Article number: 070606(2023)

    • DOI：10.11889/j.0253-3219.2023.hjs.46.070606    

      CLC： TL333

    • Received：29 March 2022，

      Revised：20 February 2023，

      Published：15 July 2023

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  • GAO Pengcheng,ZHANG Bin,YANG Hao,et al.Development of flow blockage model for core heat transfer and its application in QUENCH experiment[J].NUCLEAR TECHNIQUES,2023,46(07):070606. DOI： 10.11889/j.0253-3219.2023.hjs.46.070606.

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