中子输运计算界面流方法的数学共扼方程  

Mathematical Adjoint Equation of Interface Current Method for Neutron Transport Calculation

作　　者：张颖[1] 陈伟[1] 陈立新[1] 

机构地区：[1]西北核技术研究所,西安710024

出　　处：《核动力工程》2005年第2期97-101,共5页Nuclear Power Engineering

摘　　要：以子区内中子源为常源近似条件下的中子积分输运方程为前向方程,推导了中子积分输运方程界面流算法在六角形几何情况下的数学共扼方程;介绍了该数学共扼方程求解的内、外迭代策略,并对前向方程计算程序TPHEX进行了改造,得到了常源近似情况下数学共扼方程计算程序TPHEX_J0。通过算例校验表明TPHEX_J0与TPHEX程序所计算的系统本征值符合良好,TPHEX_J0程序的计算结果是可靠的。This paper derives the mathematical adjoint equation of neutron transport equation, which is solved in hexagonal geometry by interface current method in the condition that the neutron source in cell adopts constant assumption. The calculation method of mathematical equation and the progress of inner and outer iteration are introduced. Based on the TPHEX code for forward equation calculation, the TPHEX_J0 code to calculate the mathematical equation is encoded. The calculation checkout proves that the keff of system calculated by TPHEX_J0 and TPHEX code are all in good agreement, and the calculation results of TPHEX_J0 code are reliable.

关 键 词：中子输运方程 界面流方法 六角形 数学共扼方程 

分 类 号：TL329.2[核科学技术—核技术及应用]