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Technical Paper

An Integral Form of the Variational Nodal Method

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Pages 141-151 | Published online: 28 Jul 2017

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Read on this site (6)

Yunzhao Li, Zhipeng Li, Hongchun Wu & Youqi Zheng. (2018) Improved Variational Nodal Method Based on Symmetry Group Theory. Nuclear Science and Engineering 190:2, pages 134-155.
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Tengfei Zhang, Yongping Wang, E. E. Lewis, M. A. Smith, W. S. Yang & Hongchun Wu. (2017) A Three-Dimensional Variational Nodal Method for Pin-Resolved Neutron Transport Analysis of Pressurized Water Reactors. Nuclear Science and Engineering 188:2, pages 160-174.
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E. E. Lewis, M. A. Smith & G. Palmiotti. (2009) A New Paradigm for Local-Global Coupling in Whole-Core Neutron Transport. Nuclear Science and Engineering 161:3, pages 279-288.
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A. I. Zhukov. (2008) Use of Local Variation Method for Nuclear Design Calculations. Nuclear Science and Engineering 159:1, pages 48-55.
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S. Van Criekingen, E. E. Lewis & R. Beauwens. (2006) Mixed-Hybrid Transport Discretization Using Even and Odd P Expansions. Nuclear Science and Engineering 152:2, pages 149-163.
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W. S. Yang, M. A. Smith, G. Palmiotti & E. E. Lewis. (2005) Interface Conditions for Spherical Harmonics Methods. Nuclear Science and Engineering 150:3, pages 257-266.
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Articles from other publishers (7)

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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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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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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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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O. Safarzadeh. (2016) Physical probability table applied to response matrix-collision probability method for direct whole-core transport calculations. Annals of Nuclear Energy 89, pages 99-108.
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O. Safarzadeh, A. Minuchehr & A.S. Shirani. (2013) Heterogeneous reactor core transport technique using response matrix and collision probability methods. Annals of Nuclear Energy 62, pages 137-143.
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Yousry Azmy & Enrico SartoriE. E. Lewis. 2010. Nuclear Computational Science. Nuclear Computational Science 85 115 .

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