Discrete Ordinates Method for Three-Dimensional Neutron Transport Equation Based on Unstructured-Meshes
|更新时间:2025-12-08
|
Discrete Ordinates Method for Three-Dimensional Neutron Transport Equation Based on Unstructured-Meshes
Vol. 41, Issue 3, Pages: 363-366(2007)
作者机构:
西安交通大学能源与动力工程学院,西安,710049
作者简介:
基金信息:
DOI:
CLC:TP301
Online First:10 March 2007,
Published:2007
稿件说明:
移动端阅览
巨海涛 1, 吴宏春 1, 姚栋 2, et al. Discrete Ordinates Method for Three-Dimensional Neutron Transport Equation Based on Unstructured-Meshes[J]. 2007, 41(3): 363-366.
DOI:
巨海涛 1, 吴宏春 1, 姚栋 2, et al. Discrete Ordinates Method for Three-Dimensional Neutron Transport Equation Based on Unstructured-Meshes[J]. 2007, 41(3): 363-366.DOI:
Discrete Ordinates Method for Three-Dimensional Neutron Transport Equation Based on Unstructured-Meshes
A discrete ordinates method for three-dimensional neutron transport equation based on unstructured-meshes was derived from the first-order neutron transport equation. A set of differential equations about the spatial variables were obtained. It avoids the singularity in void regions from the second-order form of the equation
which implies the inversion of the total cross-section. The differential equations were solved iteratively using the least-squares finite element method. For the symmetric stiffness matrix
the fast iteration method can be used. A three-dimensional transport calculation code was programmed. The triangular prism and the tetrahedron elements were used in the calculation. The numerical results of some benchmark problems show that this method can be used in unstructured-meshes and can give high precise result. For most problems
the error is less than 0.3% for the eigenvalue and 3.0% for the angular flux
respectively.
关键词
Keywords
references
谢仲生, Dorning J J. 三维中子输运方程离散纵标节块数值解法[J]. 核科学与工程, 1986, 6(4):311-322.
Xie Zhongsheng, Dorning J J. A discrete nodal method for three-dimensional neutron transport numerical calculations[J]. Chinese Journal of Nuclear Science and Engineering, 1986, 6(4):311-322.
Wu Hongchun, Xie Zhongsheng, Zhu Xuehua. The nodal discrete-ordinate transport calculation of anisotropy scattering problem in three-dimensional Cartesian geometry[J].Nuclear Power Engineering, 1994, 15(2):138-141.
Varin E, Samba G. Spherical harmonics finite element transport equation solution using a least-squares approach[J]. Nucl Sci Eng, 2005, 151(2): 167-183.
Wareing T A, McGhee J M, Morel J E, et al. Discontinuous finite element Sn methods on three-dimensional unstructured grids[J]. Nucl Sci Eng, 2001, 138(3): 256-268.
Warsa J S, Wareing T A, Morel J E. Fully consistent diffusion synthetic acceleration of linear discontinuous Sn transport discretizations on unstructured tetrahedral meshes[J]. Nucl Sci Eng, 2002, 141(3): 236-251.
Manteuffel T A, Ressel K J, Starke G. Least-squares finite-element solution of the neutron transport equation in diffusive regimes[J]. Siam J Numer Anal, 1998, 35(2): 806-835.
Manteuffel T A, Ressel K J. A boundary functional for the lease-squares finite-element solution of neutron transport problems[J]. Siam J Numer Anal, 2000, 37(2): 556-586.
Takeda T, Ikeda H. 3-D neutron transport benchmarks. Technical Report OECD/NEA Committee on Reactor Physics(NEACRP-L-330)[R]. Osaka, Japan:Department of Nuclear Engineering. 1991.
Issa J G, Riyait N S, Goddard A J H, et al. Multigroup application of the anisotropic FEM code FELTRAN to one, two, three-dimensional and R-Z problems[J]. Prog Nucl Eng, 1986, 18(1):251-264.