聚变驱动次临界堆第一壁材料辐照损伤的初步研究  

Preliminary study on radiation damage on materials of the first wall for the fusion driven sub-critical system

作　　者：邹俊[1] 黄群英[2] 罗乐[1] 许德政[2] 曾勤[2] 陈明亮[2] 吴宜灿[2] 

机构地区：[1]合肥工业大学,安徽合肥230009 [2]中国科学院等离子体物理研究所,安徽合肥230031

出　　处：《核科学与工程》2007年第2期147-151,共5页Nuclear Science and Engineering

摘　　要：介绍了中子对材料的辐照损伤原理及化合物原子平均离位(DPA)截面计算方法;使用辐照损伤计算程序SPECTER计算了聚变驱动次临界堆(FDS-I)第一壁材料CLAM钢的辐照损伤参数,并将CLAM钢的辐照损伤计算结果与相同条件下316SS、SiC等聚变堆结构材料的计算结果进行了比较。The principle theory of neutron radiation damage and the calculation methods on DPA （Displacements Per Atom） cross section of compound materials were introduced briefly. The radiation damage in the CLAM steel of the First Wall in the Fusion-Driven Sub-critical System （FDS- Ⅰ） is calculated by using the code SPECTER. The results are compared with the radiation damage level of other fusion materials, such as 316SS, SiC etc. , under the same irradiation conditions.

关 键 词：辐照损伤 FDS-ⅠDPA 第一壁 

分 类 号：TL34[核科学技术—核技术及应用]