Frontiers in Energy
>> 2008,
Volume 2,
Issue 2
doi:
10.1007/s11708-008-0024-3
Discrete ordinates method for three-dimensional
neutron transport equation based on unstructured-meshes
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;
Available online: 2008-06-05
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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.
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