辐照监督管中子注量率精细化模型计算方法研究  

Research on Theoretical Calculation Method for Refined Modeling of Fast Neutron Flux in Irradiation Surveillance Capsule

作　　者：邓理邻[1] 吕焕文[1] 谭怡[1] 肖锋[1] 魏述平 

机构地区：[1]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,成都610041

出　　处：《核动力工程》2013年第S1期84-86,共3页Nuclear Power Engineering

摘　　要：针对采用传统简化模型计算反应堆辐照监督管快中子注量率出现的计算结果与实测值误差较大问题,对计算模型进行改进,建立堆芯燃料组件内部结构的精细化计算模型,并将传统简化模型、改进的精细化模型的计算结果与实测值进行比较。结果表明,辐照监督管改进的精细化计算模型的计算结果相对于实测值的误差大幅降低。To deal with the problem of the notable calculation error of Irradiation surveillance capsule fast neutron flux compared with the measured values,the calculation model has been improved and a refined calculation model has been built by detailed inner configuration of assemblies in core.Comparison has been made between conventional compendious model results,refined model results and measured values.It is obviously that the calculation error of the refined model has been greatly reduced.

关 键 词：辐照监督管 快中子注量率 精细化模型 

分 类 号：TL33[核科学技术—核技术及应用]