POSTIRRADIATION TENSILE BEHAVIOR OF NICKEL-DOPED FERRITIC STEELS

被引:27
作者
KLUEH, RL
VITEK, JM
机构
[1] Oak Ridge Natl Lab, Oak Ridge, TN,, USA, Oak Ridge Natl Lab, Oak Ridge, TN, USA
关键词
NUCLEAR REACTORS; FUSION - Materials - STEEL HEAT TREATMENT - Tempering - TOKAMAK DEVICES - Materials;
D O I
10.1016/0022-3115(87)90004-3
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Tensile specimens of normalized and tempered 9Cr-1MoVNb, 9Cr-1MoVNb-2Ni, 12Cr-1MoVW, 12Cr-1MoVW-1Ni, and 12Cr-1MoVW-2Ni steels were irradiated in the High-Flux Isotope Reactor (HFIR) at 300, 400, and 500 degree C to displacement damage levels of up to 11 dpa. The nickel was added to the ferritic steels to produce helium by a two-step (n, alpha ) reaction during irradiation. Up to 103 appm He was produced in the steels with 2% Ni. Irradiation at 300 and 400 degree C caused an increase in strength of all steels relative to the strength in both the normalized and tempered condition and after aging the steel for a time period similar to that in the reactor. The strength increases were accompanied by a loss of ductility. At 500 degree C, there was little change in strength properties. The results at 300 and 400 degree C indicate an effect of helium.
引用
收藏
页码:272 / 280
页数:9
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