Microstructural evolution in annealed austenitic steels during neutron irradiation
Microstructural evolution in annealed austenitic steels during neutron irradiation
复制标题
中子辐照期间退火奥氏体钢的微观结构演变
DOI：
10.1179/095066087790150331
复制
发表时间：
1987
影响因子：
16.1
通讯作者：
C. McHargue
中科院分区：
文献类型：
--
作者：
P. Maziasz;C. McHargue
本文综述了奥氏体不锈钢在中子辐照过程中组织演变的文献，重点介绍了AISI316不锈钢的固溶处理。裂变中子辐射和聚变中子辐射造成的初级损害的主要区别是聚变中子产生的变形气体(氢和氦)的量要大得多。二次损伤由位错环、空洞和受辐射影响的相组成。二次损伤引起的微观结构变化主要由杂质原子/点缺陷复合体的耦合迁移引起的辐照偏析和形变产生的氦的量决定。
AbstractThe literature which describes the microstructural development during neutron irradiation of austenitic stainless steels is reviewed, with emphasis on solution annealed AISI 316 stainless steel. The main difference in primary damage caused by fission and fusion neutron irradiation is the considerably larger amounts of transmutation gases (hydrogen and helium) produced by fusion neutrons. The secondary damage consists of dislocation loops, cavities, and radiation-affected phases. The microstructural changes produced by secondary damage is largely determined by radiation-induced segregation due to coupled migration of impurity atom/point defect complexes, and by the amount of helium produced by transmutation.