NUCLEAR TECHNIQUES, Volume. 46, Issue 11, 110603(2023)

Validation of an in-house system analysis code for heat pipe cooled reactor

Pan WU, Zeyu OUYANG, Yu ZHU, and Jianqiang SHAN*
Author Affiliations
  • School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an 710049, China
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    References(19)

    [13] YUAN Hongqiu, HU Dapu. High-order end floating method - for solving point reactor neutron kinetics equations[J]. Nuclear Power Engineering, 16, 124-128(1995).

    [14] TAO Wenquan[M]. Numerical heat transfer(2001).

    [15] WU Hongchun[M]. Nuclear reactor physics(2014).

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    Pan WU, Zeyu OUYANG, Yu ZHU, Jianqiang SHAN. Validation of an in-house system analysis code for heat pipe cooled reactor[J]. NUCLEAR TECHNIQUES, 2023, 46(11): 110603

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    Paper Information

    Category: Research Articles

    Received: Apr. 5, 2023

    Accepted: --

    Published Online: Dec. 23, 2023

    The Author Email:

    DOI:10.11889/j.0253-3219.2023.hjs.46.110603

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