摘要
本文基于球床模块式高温气冷堆核电站(HTR-PM)反应堆设备间γ射线辐射屏蔽设计工程实例,建立了乏燃料中间贮存系统的蒙特卡罗模型,给出了蒙特卡罗方法计算程序MCNP4C和点核积分方法计算程序QAD-CGA的计算剂量值,并通过对二者进行分析和对比,得知点核积分程序QAD-CGA的计算结果较蒙特卡罗程序MCNP4C的计算结果偏大。
This paper provides the results obtained by the Monte Carlo transport method MCNP4C and the Point-Kernel integration method QAD-CGA, which are based on the real example of gamma shield design of High Temperature Gas-Cooled Reactor-Pebble bed Module （HTR-PM） compartments in details, and the results were analyzed and compared. The Monte-Carlo model of the middle stockpile system for the spent fuel was also established and analyzed. The result provide that the calculating obtained by value of the Point-Kernel integration method QAD-CGA is more than that of the Monte Carlo transport method MCNP4C.
出处
《辐射防护》
CAS
CSCD
北大核心
2007年第4期213-218,232,共7页
Radiation Protection
