RADIATION DAMAGE IN ANNEALED TYPE 304 STAINLESS STEEL.

被引：12

作者：

Bloom, E.E. ^{[1
]}

Stiegler, J.O. ^{[1
]}

McHargue, C.J. ^{[1
]}

机构：

[1] Metals and Ceramics Division, Oak Ridge National Laboratory, Oak Ridge,TN,37830, United States

来源：

Radiation Effects | 1972年 / 14卷 / 3-4期

关键词：

IRON AND STEEL METALLOGRAPHY - Nuclear reactors - Radiation effects - STAINLESS STEEL - Defects;

D O I：

10.1080/00337577208231205

中图分类号：

学科分类号：

摘要：

The damage appears to be first visible at a threshold fluence that increases with increasing irradiation temperature. At high fluences, void concentrations approach a saturation concentration that decreases with increasing irradiation temperature. The void concentrations and size distributions are not strongly dependent on the fast neutron flux, at least over range encountered in fast reactors. These observations are discussed in terms of proposed mechanisms for void formation.

引用

页码：231 / 243