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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
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.
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页码：966 / 972
页数：7
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