压力容器环形空腔上部材料屏蔽计算分析  

Calculation Analysis of the Shielded Materials in Circumferential Cavity on Top of the Reactor Pressure Vessel

作　　者：胡建军[1] 傅守信 刘桂莲[1] 

机构地区：[1]中国核动力研究设计院,成都610041

出　　处：《核动力工程》2003年第z1期78-81,共4页Nuclear Power Engineering

摘　　要：用离散纵座标SN法与反照蒙特卡罗AMC法相耦合,对秦山600MW核电厂反应堆压力容器环形空腔上部密封环区、褐铁矿混凝土及电离室入口轻质保护材料的中子和γ射线注量率、剂量率和释热率进行计算分析。计算结果表明,对于停堆后人员可能进入的部位,增加轻质保护材料能有效降低中子辐射;采用SN-AMC计算技术能较好地完成反应堆的大尺寸空腔和复杂孔道屏蔽设计计算。By coupling the discrete ordinates transport calculation method and the albedo Monte Carlo calculation method, this paper analyzes the calculation results of fluence, dose rate and heating release rate of neutron and γ-ray in sealing ring, limonite concrete and the light material of ionization chamber inlet, which lie in the circumferential cavity on top of the reactor pressure vessel for Qinshan Phase II NPP Project. The results of calculation indicate that it can reduce effectively neutron radiation by adding ethereal protective materials in the place of working, and the SN-AMC coupling technology can deal with shielding calculation in large cavity or complex hole.

关 键 词：离散纵座标 反照蒙特卡罗 环形空腔 注量率 剂量率和释热率 

分 类 号：TM623[电气工程—电力系统及自动化] TL352.2[核科学技术—核技术及应用]