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Nuclear Science and Engineering Volume 197, 2023 - Issue 6
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Technical Papers

High-Fidelity Neutron Transport Solution of High Temperature Gas-Cooled Reactor by Three-Dimensional Linear Source Method of Characteristics

Kaijie ZhuTsinghua University, Institute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Beijing100084, ChinaView further author information
,
Boran KongTsinghua University, Institute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Beijing100084, ChinaView further author information
,
Han ZhangTsinghua University, Institute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Beijing100084, ChinaCorrespondence[email protected]
ORCID Iconhttps://orcid.org/0000-0002-7619-3756View further author information
ORCID Icon,
Jiong GuoTsinghua University, Institute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Beijing100084, ChinaView further author information
&
Fu LiTsinghua University, Institute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Beijing100084, ChinaView further author information
Pages 1174-1196 | Received 27 Jun 2022, Accepted 01 Nov 2022, Published online: 16 Dec 2022

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Read on this site (2)

Marco Tiberga & Simone Santandrea. (2024) A Novel High-Order Surface Characteristics Scheme for the Neutron Transport Equation in 2D Unstructured Meshes. Nuclear Science and Engineering 198:4, pages 853-897.
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Boran Kong, Longfei Xu & Baiwen Li. Convergence Study of 2D Transport Method for Multigroup k-Eigenvalue Problems with High-Order Scattering Source Using Fourier Analysis. Nuclear Science and Engineering 0:0, pages 1-19.
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Articles from other publishers (1)

Kaijie Zhu, Qinrong Dou, Han Zhang, Boran Kong, Zhaoyuan Liu, Jiong Guo & Fu Li. (2024) The deterministic neutron transport calculation for the HTR-PM by the three-dimensional method of characteristics code ARCHER. Annals of Nuclear Energy 197, pages 110286.
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