核电站反应堆辐射屏蔽程序系统  

The Computer Code System for Reactor Radiation Shielding in Design of Nuclear Power Plant

作　　者：李春槐[1] 傅守信 刘桂莲[1] 赵成昆[1] 张传旭[1] 张立吾[1] 赵增魁 

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》1995年第6期492-497,共6页Nuclear Power Engineering

摘　　要：核电站反应堆辐射屏蔽程序系统包括源项程序、离散座标输运程序、蒙特卡罗和反照蒙特卡罗程序、点核积分程序、最佳化程序、温场程序、大气散射和结构壁屏蔽效应分析程序、数据库以及加工程序和耦合程序.本程序系统程序类型比较齐全,程序和参数配套,在核电站反应堆以及其它类型反应堆和核设施辐射屏蔽设计和安全分析中得到了广泛应用.The computer code system used in reactor radiation shielding design of nuclear power plant includes the source term codes, discrete ordinate transport codes, Monte Carlo and Albedo Monte Carlo codes, kernel integration codes, optimization code, temperature field code, skyshine code, coupling calculation codes and some processing codes for data libraries. This computer code system has more satisfactory variety of codes and complete sets of data library. It is widely used in reactor radiation shielding design and safety analysis of nuclear power plant and other nuclear facilities.

关 键 词：辐射屏蔽 程序系统 安全分析 核电站 

分 类 号：TM623.8[电气工程—电力系统及自动化] TL480.643[核科学技术—核技术及应用]