RAFM钢中氚氦行为的研究进展  

Exploring of Tritium and Helium Behaviors in RAFM Steels

作　　者：何伟波[1] 陈长安[2] 王佳佳[2] 向鑫[1] 帅茂兵[2] 

机构地区：[1]中国工程物理研究院,绵阳621900 [2]表面物理与化学重点实验室,绵阳621907

出　　处：《材料导报》2015年第17期101-105,共5页Materials Reports

基　　金：国家自然科学基金面上项目(51471154)

摘　　要：低活化铁素体/马氏体(RAFM)钢是未来磁约束核聚变堆产氚包层推荐的主体结构材料,将在ITER实验包层模块中进行考核。氚及氚衰变氦-3在RAFM钢中的驻留行为将影响所产生氚的有效利用并导致材料的结构损伤,因此RAFM钢的涉氚相容性是其最终应用于聚变堆结构材料之前必须考核的问题之一。总结了国内外对RAFM钢的氚氦相容性研究进展情况,提出了一些要解决的关键问题和将来的研究方向。As a highly recommended main structure material for the tritium breeding blanket in a future mag- netically controlled fusion reactor, reduce activation ferritic/martensitic （RAFM） steels will be tested with the test blanket modules in ITER machine. The entry subsequently retaining of tritium and helium-3 from tritium decay in the material can lead to a significant loss of tritium as fuel produced in the breeders and cause damages to the performance. So the tritium confinement capacities of RAFM steels is one of the most important questions should be tested before it is applied to the structure material for the fusion reactor finally. The research progress of RAFM steels on tritium and helium confinement capacities around the world are summarized, some crucial problems to be resolved and prospective study direction are put foward.

关 键 词：低活化铁素体/马氏体钢 氚氦损伤 微结构演化 

分 类 号：TL627[核科学技术—核技术及应用]