NUCLEAR TECHNIQUES, Volume. 46, Issue 3, 030601(2023)

Development and verification of a neutronics-thermal hydraulics coupling code with unstructured meshes neutron transport model

Mingrui YANG, Qizheng SUN, Chixu LUO, Donghao HE, Xiaojing LIU, and Tengfei ZHANG*
Author Affiliations
  • School of Nuclear Science and Engineering, Shanghai Jiao Tong University, Shanghai 200240, China
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    References(21)

    [18] Finnemann H, Galati A. NEACRP 3-D LWR core transient benchmark, final specification[R](1991).

    [19] Barber D A, Miller R M, Joo H G et al. A generalized interface module for the coupling of spatial kinetics and thermal-hydraulics codes[R]. Los Alamos National Lab(1999).

    [22] Finnemann H, Bauer H, Galati A et al. Results of LWR core transient benchmarks[R](1993).

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    Mingrui YANG, Qizheng SUN, Chixu LUO, Donghao HE, Xiaojing LIU, Tengfei ZHANG. Development and verification of a neutronics-thermal hydraulics coupling code with unstructured meshes neutron transport model[J]. NUCLEAR TECHNIQUES, 2023, 46(3): 030601

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    Paper Information

    Category: Research Articles

    Received: Aug. 19, 2022

    Accepted: --

    Published Online: Apr. 17, 2023

    The Author Email:

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

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