秦山核电二期工程反应堆及反应堆冷却剂系统源项计算分析  

Source Terms Calculation Analysis for the Reactor and Primary Coolant System of Qinshan Phase II NPP Project

作　　者：张传旭[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73-77,共5页Nuclear Power Engineering

摘　　要：介绍了秦山核电二期工程反应堆及反应堆冷却剂系统源项计算方法、程序和计算结果。该辐射源项用于确定核电站厂房、换料设备和设施屏蔽厚度及其辐射剂量场。This paper presents the calculation method and codes of source terms for the reactor and primary coolant system of Qinshan Phase ⅡNPP Project, and presents the source terms results. These source terms are used to determinate the shield thickness and radiation dose field for nuclear power station building, reloading device and facilities.

关 键 词：裂变产物 腐蚀产物 比活度 放射性浓度 γ射线源强 

分 类 号：TL353[核科学技术—核技术及应用]