中子输运计算界面流方法的微扰计算  

Perturbation Calculation of Neutron Transport Equation with Interface Current Method

作　　者：张颖[1] 陈伟[1] 谢仲生[2] 陈立新[1] 

机构地区：[1]西北核技术研究所,西安710024 [2]西安交通大学核热能系,710049

出　　处：《核动力工程》2005年第3期219-223,共5页Nuclear Power Engineering

摘　　要：以六角形几何中子积分输运计算界面流算法及其相对应的数学共扼方程计算为基础,利用微扰原理计算了当反应堆六角形组件中栅元核参数发生微量变化时系统反应性的变化。计算结果表明,本文所开发的基于六角形几何中子积分输运算法的微扰计算方法是正确的。The perturbation calculation for neutron integral transport equation in hexagonal geometry is studied. Based on the calculation for interface current method of neutron integral transport equation in hexagonal geometry and the calculation for corresponding mathematical adjoint equation, the perturbation theory is used to calculate the reactivity variety in reactor hexagonal assembly when the parameters of cell in assembly occurred minimal change. The calculation result is satisfactory. It proves that the perturbation calculation method is correct.

关 键 词：中子输运方程 界面流方法 六角形 微扰理论 数学共扼方程 

分 类 号：TL329.2[核科学技术—核技术及应用]