Numerical Calculation Methods for Neutron Transport Equation in Unstructured Fuel Assembly
The spherical harmonics (Pn) finite element method, the Sn finite element method, the triangle transmission probability method and the discrete triangle nodal method were all introduced to solve the neutron transport equation for unstructured fuel assembly respectively. The computing codes of each method were encoded and numerical results were discussed and compared. It was demonstrated that these four methods can solve neutron transport equations with unstructured-meshes very effectively and correctly, they can be used to solve unstructured fuel assembly problem.
Neutron transport Unstructured Fuel assembly Numerical calculation
Wu Hongchun Liu Guoming Lu Haoliang Ju Haitao Cao Liangzhi
School of Nuclear Engineering and Technology, Xian Jiaotong University, Xian, Shaanxi 710049
国际会议
上海
英文
200-208
2007-03-12（万方平台首次上网日期，不代表论文的发表时间）