三维离散纵标方法在堆内构件释热率计算中的初步应用  

Preliminary Study on Heating Rate Calculation for PWR Internals by Three-Dimensional S_N Method

作　　者：杨寿海[1] 陈义学[1,2] 王伟金[1] 靳忠敏[1] 陆道纲[1] 

机构地区：[1]华北电力大学核科学与工程学院,北京102206 [2]国家核电软件技术中心,北京100029

出　　处：《核动力工程》2012年第1期25-28,共4页Nuclear Power Engineering

基　　金：国家自然科学基金(10875042);中央高校基本科研业务费专项资金(10ZG08);长江学者和创新团队发展计划(IRT0720)

摘　　要：以美国H.B.Robinson-2#机组反应堆压力容器(RPV)基准实验的参数为输入数据,采用三维离散纵标方法程序(TORT)计算压力辐照监督管处中子能谱及典型核素的活度值。计算得到的辐照监督管处中子能谱与基准实验结果趋势一致、吻合较好;典型核素活度的计算值与测量值之比(C/M)为1.04±0.04。用TORT对福建宁德核电站堆内构件释热率分布进行初步计算,并与蒙特卡罗方法(MCNP)的计算结果相比较,两种方法的结果表现出良好的一致性。最后对TORT程序应用于堆内释热率计算进行讨论。Based on the American H.B.Robinson-2 pressure vessel benchmark,the neutron spectrum in surveillance capsule and reaction rates for some species have been obtain by three-dimensional（3-D） discrete ordinates（SN） method code（TORT）.The results show that,the neutron spectrum in surveillance capsule makes good agreement with the benchmark,and the C/M of reaction rates for some species is 1.04±0.04 by TORT code.Then,the heat release rate distribution over reactor components has been calculated by TORT code and MCNP program for Ningde Nuclear Power Plant in Fujian China,and compared with each other.Finally,the application of TORT code in the calculation of the heating rate for PWR internals is presented and discussed.

关 键 词：三维离散纵标法 H.B.Robinson-2基准 堆内构件 释热率 

分 类 号：TL315.6[核科学技术—核技术及应用]