原子能科学技术Issue(10)：1707-1712,6.DOI:10.7538/yzk.2013.47.10.1707
三维多群六角形几何中子扩散程序开发
Development of 3D Multi-group Neutron Diffusion Code for Hexagonal Geometry
孙伟 1倪东洋 2李庆 3王侃3
作者信息
- 1. 清华大学 工程物理系，北京 100084
- 2. 中国核动力研究设计院 核反应堆系统设计技术重点实验室，四川 成都 610041
- 3. 中国核动力研究设计院 核反应堆系统设计技术重点实验室,四川 成都,610041
- 折叠
摘要
Abstract
Based on the theory of new flux expansion nodal method to solve the neutron diffusion equations ,the intra-nodal fluence rate distribution was expanded in a series of analytic basic functions for each group .In order to improve the accuracy of calculation result ,continuities of neutron fluence rate and current were utilized across the nodal surfaces .According to the boundary conditions ,the iteration method was adopted to solve the diffusion equation , where inner iteration speedup method is Gauss-Seidel method and outer is Lyusternik-Wagner .A new speedup method (one-outer-iteration and multi-inner-iteration method) was proposed according to the characteristic that the convergence speed of multiplication factor is faster than that of neutron fluence rate and the update of inner iteration matrix is slow .Based on the proposed model ,the code HANDF-D was developed and tested by 3D two-group vver440 benchmark ,experiment-2 of HFETR ,3D four-group thermal reactor benchmark ,and 3D seven-group fast reac-tor benchmark .The numerical results show that HANDF-D can predict accurately the multiplication factor and nodal powers .关键词
解析基函数/中子扩散方程/高斯-塞德尔方法/加速收敛方法Key words
analytic basis function/neutron diffusion equation/Gauss-Seidel method/speedup method分类
能源科技引用本文复制引用
孙伟,倪东洋,李庆,王侃..三维多群六角形几何中子扩散程序开发[J].原子能科学技术,2013,(10):1707-1712,6.
