Discrete ordinates method for three-dimensional
neutron transport equation based on unstructured-meshes

doi:10.1007/s11708-008-0024-3

Front. Energy

2008, Vol. 2

Issue (2) : 179-182 https://doi.org/10.1007/s11708-008-0024-3

Discrete ordinates method for three-dimensional neutron transport equation based on unstructured-meshes

JU Haitao¹, WU Hongchun¹, YAO Dong², XIAN Chunyu²

1.School of Energy and Power Engineering, Xi'an Jiaotong University; 2.National Key Laboratory of Reactor System Design Technology, Nuclear Power Institute of China;

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Abstract A discrete ordinates method for a three-dimensional first-order neutron transport equation based on unstructured-meshes that avoids the singularity of the second-order neutron transport equation in void regions was derived. The finite element variation equation was obtained using the least-squares method. A three-dimensional transport calculation code was developed. Both the triangular-z and the tetrahedron elements were included. The numerical results of some benchmark problems demonstrated that this method can solve neutron transport problems in unstructured-meshes very well. For most problems, the error of the eigenvalue and the angular flux is less than 0.3% and 3.0% respectively.

Issue Date: 05 June 2008

Cite this article:

JU Haitao,WU Hongchun,YAO Dong, et al. Discrete ordinates method for three-dimensional neutron transport equation based on unstructured-meshes[J]. Front. Energy, 2008, 2(2): 179-182.

URL:

https://academic.hep.com.cn/fie/EN/10.1007/s11708-008-0024-3
https://academic.hep.com.cn/fie/EN/Y2008/V2/I2/179

1	Xie Zhongsheng Dorning J J A discrete nodal method forthree-dimensional neutron transport numerical calculationsChinese Journal of Nuclear Science and Engineering 1986 6(4)311322 (in Chinese)
2	Wu Hongchun Xie Zhongsheng Zhu Xuehua The nodal discrete-ordinate transport calculation of anisotropyscattering problem in three-dimensional cartesian geometryNuclear Power Engineering 1994 15(2)138141 (in Chinese)
3	Varin E Samba G Spherical harmonics finiteelement transport equation solution using a least-squares approachNucl Sci Eng 2005 151(2)167183
4	Wareing T A McGhee J M Morel J E et al.Discontinuous finite element Sn methods on three-dimensionalunstructured gridsNucl Sci Eng 2001 138(3)256268
5	Warsa J S Wareing T A Morel J E Fully consistent diffusion synthetic acceleration of lineardiscontinuous Sn transport discretizations on unstructured tetrahedralmeshesNucl Sci Eng 2002 141(3)236251
6	Ying Genjun 3D numerical simulation with least-squares finite element methodfor neutron transport equation in diffusive regimesXi'anXi'an Jiaotong University 2003 (in Chinese)
7	Manteuffel T A Ressel K J Starke G Least-Squares finite-element solution of the neutron transportequation in diffusive regimesSiam J NumerAnal 1998 35(2)806835. doi:10.1137/S0036142996299708
8	Manteuffel T A Ressel K J A boundary functional for theleast-squares finite-element solution of neutron transport problemsSiam J Numer Anal 2000 37(2)556586. doi:10.1137/S0036142998344706
9	Takeda T Ikeda H 3-D neutron transport benchmarksTechnical Report OECD/NEA Committee on Reactor Physics (NEACRP-L-330)JapanOSAKAUniversity 1991
10	Issa J G Riyait N S Goddard A J H et al.Multigroup application of the anisotropic FEM codeFELTRAN to one, two, three-dimensional and R-Z problemsProg Nucl Eng 1986 18(1)251264. doi:10.1016/0149‐1970(86)90031‐4

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