摘要
讨论了用界面流方法计算二维六角形组件中子通量分布。从积分输运方程出发,导出了一种简便的数学模型,在子区内采用平源通量近似,并假设中子发射和散射为各向同性。在子区表面上,中子通量的空间分布为常数,中子角通量分布通过伴随勒让特多项式展开表示,采用DP_1近似。推导出界面流方程组,给出了泄漏、穿透几率矩阵及其矩阵元素的表达式及计算方法。根据提出的数学模型,编制了TPHEX程序,对二维六角形组件进行了计算,本程序可用于水堆六角形燃料组件计算。
The mathematical model of two-dimensional calculation of neutron flux distribution in the hexagonal fuel assembly by using the interface current method is described in this paper, based on neutron integral transport equation. The fluxes within the meshes and at the mesh interfaces are assumed to be spatially uniform. The source neutron emission and scattering are isotropie, and the angular fluxes at the surfaces are expanded in terms of Legendre polynomials by using double P_1 approximation.The equation of interface current and the formula of matrix element of leakage and transmission probabilities are derived. Based on this mathematical model, a code TPHEX is encoded. It can be used to the calculation of hexagonal fuel assemblies of the light water reactor.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
1991年第4期23-30,共8页
Nuclear Power Engineering
基金
自然科学基金(B187105)
关键词
界面流法
燃烧组件
中子输运方程
Interface current method, Neutron integral transpont equation, Leakage probability, Transmission probability.
