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Mathematical Adjoint Equation of Interface Current Method for Neutron Transport Calculation
Author(s): 
Pages: 97-101
Year: Issue:  2
Journal: NUCLEAR POWER ENGINEERING

Keyword:  中子输运方程界面流方法六角形数学共扼方程;
Abstract: 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.
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