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Nuclear Science and Engineering Volume 188, 2017 - Issue 2
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Technical Papers

A Three-Dimensional Variational Nodal Method for Pin-Resolved Neutron Transport Analysis of Pressurized Water Reactors

Tengfei ZhangShanghai Jiao Tong University, School of Nuclear Science and Engineering, Shanghai, ChinaCorrespondence[email protected]
,
Yongping WangXi’an Jiaotong University, Department of Nuclear Engineering, Xi’an, Shaanxi, China
,
E. E. LewisNorthwestern University, Department of Mechanical Engineering, Evanston, Illinois
,
M. A. SmithArgonne National Laboratory, Nuclear Engineering Division, 9700 South Cass Avenue, Lemont, Illinois
,
W. S. YangPurdue University, School of Nuclear Engineering, West Lafayette, Indiana
&
Hongchun WuXi’an Jiaotong University, Department of Nuclear Engineering, Xi’an, Shaanxi, China
Pages 160-174 | Received 10 May 2017, Accepted 29 Jun 2017, Published online: 07 Aug 2017

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Yongping Wang, Yunzhao Li, Tengfei Zhang, E. E. Lewis, M. A. Smith, W. S. Yang & Hongchun Wu. (2019) Generalized Partitioned Matrix Acceleration for Variational Nodal Diffusion Method. Nuclear Science and Engineering 193:6, pages 652-662.
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Articles from other publishers (25)

Dan Wang, Wei Xiao, Zhaohui Du & Tengfei Zhang. (2023) An adaptive time stepping stiffness confinement method for solving reactor dynamics equations. Frontiers in Energy Research 11.
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Qizheng Sun, Wei Xiao, Xiangyue Li, Han Yin, Tengfei Zhang & Xiaojing Liu. (2023) A variational nodal formulation for multi-dimensional unstructured neutron diffusion problems. Nuclear Engineering and Technology 55:6, pages 2172-2194.
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Wei Xiao, Han Yin, Xiao-Jing Liu, Hui He & Teng-Fei Zhang. (2023) On the transient models of the VITAS code: applications to the C5G7-TD pin-resolved benchmark problem. Nuclear Science and Techniques 34:2.
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Tengfei Zhang, Wei Xiao, Han Yin, Qizheng Sun & Xiaojing Liu. (2022) VITAS: A multi-purpose simulation code for the solution of neutron transport problems based on variational nodal methods. Annals of Nuclear Energy 178, pages 109335.
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Wei Xiao, Qizheng Sun, Xiaojing Liu, Hui He, Donghao He, Qingquan Pan & Tengfei Zhang. (2022) Application of stiffness confinement method within variational nodal method for solving time-dependent neutron transport equation. Computer Physics Communications 279, pages 108450.
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Tengfei Zhang & Zhipeng Li. (2022) Variational nodal methods for neutron transport: 40 years in review. Nuclear Engineering and Technology 54:9, pages 3181-3204.
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Changyuan Liu. (2022) Doppler broadening using discrete cosine transform and kernel reconstruction for spatially variable media. Annals of Nuclear Energy 174, pages 109150.
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Han Yin, Tengfei Zhang, Donghao He & Xiaojing Liu. (2022) A quasi-transport integral variational nodal method for homogeneous nodes based on the 2D/1D method. Computer Physics Communications 274, pages 108290.
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Lou Lei, Chai Xiaoming, Yao Dong, Wang Lianjie, Li Mancang, Chen Liang, Liu Xiaoli, Zhang Hongbo, Li Sinan, Tang Xiao & Zhou Nan. (2022) Theoretically Modified Optical Length Research on the Physical Boundary of the Double-Heterogeneous System. Frontiers in Energy Research 9.
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Chen Zhao, Xingjie Peng, Hongbo Zhang, Wenbo Zhao, Zhang Chen, Junjie Rao, Kun Liu, Zhaohu Gong, Wei Zeng & Qing Li. (2021) A New Numerical Nuclear Reactor Neutronics Code SHARK. Frontiers in Energy Research 9.
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Le Kang, Chen Hao, Qiang Zhao & Yunlin Xu. (2021) The Advanced Multilevel Predictor-Corrector Quasi-Static Method for Pin-Resolved Neutron Kinetics Simulation. Frontiers in Energy Research 9.
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Lei Lou, Xingjie Peng, Xiaoming Chai, Dong Yao, Mancang Li, Lianjie Wang & Liang Chen. (2021) The Ring RPT Method for DH Systems Containing Dispersed Particle-Type of Fuel and Burnable Poisons. Frontiers in Energy Research 9.
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Kun Zhuang, Wen Shang, Ting Li, Jiangtao Yan, Sipeng Wang, Xiaobin Tang & Yunzhao Li. (2021) Variational nodal method for three-dimensional multigroup neutron diffusion equation based on arbitrary triangular prism. Annals of Nuclear Energy 158, pages 108285.
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Sherly Ray, S.B. Degweker & Umasankari Kannan. (2020) Few-group diffusion theory parameters from lattice calculations using leakage corrected collision probabilities. Annals of Nuclear Energy 145, pages 107492.
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Guang-Chun Zhang, Jie Liu, Liang-Zhi Cao, Hong-Chun Wu & Xian-Bao Yuan. (2020) Neutronic calculations of the China dual-functional lithium–lead test blanket module with the parallel discrete ordinates code Hydra. Nuclear Science and Techniques 31:8.
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Kai Huang, Liangzhi Cao, Hongchun Wu, Xuedong Fu, Yangjun Ying & Shengdong Zhu. (2020) Variable coefficient depletion equations – Efficient calculation method. Annals of Nuclear Energy 140, pages 107100.
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Yunzhao Li, Tao He, Boning Liang, Hongchun Wu, Jiahe Bai & Jiewei Yang. (2020) Development and verification of PWR-core nuclear design code system NECP-Bamboo: Part III: Bamboo-Transient. Nuclear Engineering and Design 359, pages 110462.
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Yongping Wang, Chen Zhao, Hongchun Wu & Liangzhi Cao. (2020) Comparison of the performance of heterogeneous variational nodal method and 2D/1D-MOC on pin-resolved neutron transport calculations of PWR. Annals of Nuclear Energy 138, pages 107227.
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Liang Liang, Qian Zhang, Peitao Song, Zhijian Zhang, Qiang Zhao, Hongchun Wu & Liangzhi Cao. (2020) Overlapping communication and computation of GPU/CPU heterogeneous parallel spatial domain decomposition MOC method. Annals of Nuclear Energy 135, pages 106988.
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Kai Huang, Xuedong Fu, Yangjun Ying & Shengdong Zhu. (2020) Variable coefficient depletion equations – Reference solution based on Rational Approximation Methods. Annals of Nuclear Energy 135, pages 106909.
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Yongping Wang, Tengfei Zhang, E.E. Lewis, W.S. Yang, M.A. Smith & Hongchun Wu. (2019) Three-dimensional variational nodal method parallelization for pin resolved neutron transport calculations. Progress in Nuclear Energy 117, pages 102991.
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Tengfei Zhang & Jinbiao Xiong. (2019) A hybrid acceleration method to pin-by-pin calculations using the heterogeneous variational nodal method. Annals of Nuclear Energy 132, pages 723-733.
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Tengfei Zhang, Jinbiao Xiong, Luguo Liu, Zhipeng Li & Kun Zhuang. (2019) Development and implementation of an integral variational nodal method to the hexagonal geometry nuclear reactors. Annals of Nuclear Energy 131, pages 210-220.
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Ephraim Nissan. (2019) An Overview of AI Methods for in-Core Fuel Management: Tools for the Automatic Design of Nuclear Reactor Core Configurations for Fuel Reload, (Re)arranging New and Partly Spent Fuel. Designs 3:3, pages 37.
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Tengfei Zhang, Hongchun Wu, Liangzhi Cao & Yunzhao Li. (2018) An improved variational nodal method for the solution of the three-dimensional steady-state multi-group neutron transport equation. Nuclear Engineering and Design 337, pages 419-427.
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