NUCLEAR TECHNIQUES, Volume. 48, Issue 1, 010603(2025)

Development of neutron diffusion and transport algorithms based on finite volume method

Wei LI1, Xiaojing LIU2,3, Xiang CHAI2,3, and Pengcheng ZHAO4、*
Author Affiliations
  • 1School of Resource Environment and Safety Engineering, University of South China, Hengyang 421001, China
  • 2School of Mechanical Engineering, Shanghai Jiao Tong University, Shanghai 200240, China
  • 3Shanghai Digital Nuclear Reactor Technology Intergration Innovation Center, Shanghai 200240, China
  • 4School of Nuclear Science and Technology, University of South China, Hengyang 421001, China
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    References(31)

    [7] Jasak H[M]. Error analysis and estimation for the finite volume method with applications to fluid flows(1996).

    [11] ZHANG Penghe. Research and application on difference schemes in discrete ordinates method[D](2015).

    [14] ZHANG Yining. Application of RBF meshfree method in numerical calculation of neutron diffution in nuclear reactor core[D](2016).

    [21] Stepanek J, Auerbach T, Halg W. Calculation of four thermal reactor benchmark problems in X-Y geometry[J]. Nuclear Science and Engineering, 83, 1-16(1983).

    [23] Li H L, Wu H C, Cao L Z et al. Research on the triangular mesh SN method for neutron transport equation[J]. Nuclear Power Engineering, 8-13(2006).

    [27] Cavarec C, Perron J F, Verwaerde D et al. Benchmark calculations of pin power distribution within assembies[R](1994).

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    Wei LI, Xiaojing LIU, Xiang CHAI, Pengcheng ZHAO. Development of neutron diffusion and transport algorithms based on finite volume method[J]. NUCLEAR TECHNIQUES, 2025, 48(1): 010603

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    Paper Information

    Category: NUCLEAR ENERGY SCIENCE AND ENGINEERING

    Received: Feb. 28, 2024

    Accepted: --

    Published Online: Feb. 26, 2025

    The Author Email: ZHAO Pengcheng (赵鹏程)

    DOI:10.11889/j.0253-3219.2025.hjs.48.240037

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