FATIGUE BEHAVIOR OF IRRADIATED HELIUM-CONTAINING FERRITIC STEELS FOR FUSION-REACTOR APPLICATIONS

被引：21

作者：

GROSSBECK, ML

VITEK, JM

LIU, KC

机构：

[1] Oak Ridge Natl Lab, Oak Ridge, TN,, USA, Oak Ridge Natl Lab, Oak Ridge, TN, USA

来源：

JOURNAL OF NUCLEAR MATERIALS | 1986年 / 141卷 / pt B期

关键词：

HELIUM - STAINLESS STEEL - Radiation Effects;

D O I：

10.1016/0022-3115(86)90126-1

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

The martensitic alloys 1Cr-1MoVW and 9Cr-1MoVNb have been irradiated and tested in fatigue. In order to achieve helium levels characteristic of fusion reactors, the 12Cr-1MoVW was doped with 1 and 2% Ni, resulting in helium levels of 210 and 410 appm at damage levels of 25 dpa. The 9Cr-1MoVNb was irradiated to a damage level of 3 dpa and contained less than 5 appm He. Effects that could be attributed to helium were found in 12Cr-1MoVW. Levels of 210 and 410 appm He produced cyclic strengthening of 29 and 34% over unirradiated nickel-doped materials, respectively. Cyclic hardening, attributable largely to helium, resulted in degradation of the cyclic life.

引用

页码：966 / 972

页数：7