NUCLEAR TECHNIQUES, Volume. 46, Issue 6, 060603(2023)

Application of SARAX code system on the calculation of complex unstructured geometry core

Bowen XIAO1, Youqi ZHENG1、*, Yongping WANG1, Liang QIAO2, Yushan TAO2, and Xiaoyue LIU1
Author Affiliations
  • 1Xi'an Jiaotong University, Xi'an 710049, China
  • 2Nuclear Power Institute of China, Chengdu 610041, China
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    References(27)

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    [9] Moller J Y, Lautard J J. MINARET, a deterministic neutron transport solver for nuclear core calculations[C].

    [10] FU Lianxiang, YANG Shulin. Programming report for numerical solution of two dimensional neutron transport equation[R]. Technical Report IAPCAM-99-102(1999).

    [17] LU Haoliang. Nodal methods for the neutron diffusion and transport equations in triangular meshes[D](2007).

    [20] XIE Zhongsheng, DENG Li[M]. Numerical calculation method of neutron transport theory(2005).

    [23] QIAO Liang. Neutron transport parallel calculation method in sodium-cooled fast reactor applied with uncertainty analysis and nuclear data adjustment research[D](2021).

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    Bowen XIAO, Youqi ZHENG, Yongping WANG, Liang QIAO, Yushan TAO, Xiaoyue LIU. Application of SARAX code system on the calculation of complex unstructured geometry core[J]. NUCLEAR TECHNIQUES, 2023, 46(6): 060603

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    Paper Information

    Category: Research Articles

    Received: Oct. 9, 2022

    Accepted: --

    Published Online: Jul. 5, 2023

    The Author Email:

    DOI:10.11889/j.0253-3219.2023.hjs.46.060603

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