200MW低温供热堆组件群参数计算方法的比较  

THE CALCULATION METHODS OF ASSEMBLY GROUP CROSS - SECTIONS FOR THE 200 MW LOW TEMPERATURE HEATING REACTOR

作　　者：单文志[1] 胡永明[1] 杨洁[1] 罗经宇[1] 

机构地区：[1]清华大学

出　　处：《核科学与工程》1994年第1期11-20,共10页Nuclear Science and Engineering

摘　　要：介绍了200MW低温供热堆组件中子学计算中使用的两种程序方法:1)输运理论SN方法;2)穿透几率方法.做了两种方法特点的分析比较,并做了例题的校算.通过对理论模型和处理方法的分析,以及实例结果的比较,两种方法各有特点,都适于低温供热堆组件中子学计算,提供较好的群常数和组件内功率分布.This paper discribes two methods for the assembly neutron cross - sections calculation for the 200 MW low temperature heating reactor: 1) Discrete - Ordinate SN method ; 2) Transmission probability method. From the theoretical point of view and considering different kinds of treatment, the two mehods have their own features and both of them can be used to generate group cross- sections and assembly power distributions for the low temperature heating reactor. Results of calculation for samples are compared.

关 键 词：低温低热堆 组件 群常数 供热堆 

分 类 号：TL413.2[核科学技术—核技术及应用]