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Development and verification of a neutronics-thermal hydraulics coupling code with unstructured meshes neutron transport model
NUCLEAR ENERGY SCIENCE AND ENGINEERING | 更新时间：2024-10-25
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    • Development and verification of a neutronics-thermal hydraulics coupling code with unstructured meshes neutron transport model

      封面论文
    • “In the field of nuclear reactor simulation, researchers have developed the unstructured grid nuclear thermal coupling program MORPHY, which has been validated for its accuracy and descriptive ability through benchmark questions such as TWIGL, providing a new tool for core nuclear thermal coupling analysis.”
    • NUCLEAR TECHNIQUES   Vol. 46, Issue 3, Article number: 030601(2023)

    • DOI：10.11889/j.0253-3219.2023.hjs.46.030601    

      CLC： TL327

    • Received：19 August 2022，

      Revised：23 November 2022，

      Published：15 March 2023

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  • YANG Mingrui,SUN Qizheng,LUO Chixu,et al.Development and verification of a neutronics-thermal hydraulics coupling code with unstructured meshes neutron transport model[J].NUCLEAR TECHNIQUES,2023,46(03):030601-030601. DOI： 10.11889/j.0253-3219.2023.hjs.46.030601.

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