MICROSTRUCTURAL DEVELOPMENT OF AUSTENITIC STAINLESS-STEELS IRRADIATED IN HFIR

被引：37

作者：

TANAKA, MP ^{[1
]}

HAMADA, S ^{[1
]}

HISHINUMA, A ^{[1
]}

MAZIASZ, PJ ^{[1
]}

机构：

[1] OAK RIDGE NATL LAB,DIV MET & CERAM,OAK RIDGE,TN 37831

来源：

JOURNAL OF NUCLEAR MATERIALS | 1988年 / 155卷 / pt B期

关键词：

Metallography--Precipitation - Neutrons - Radiation Effects - Stainless Steel--Microstructure;

D O I：

10.1016/0022-3115(88)90419-9

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

Microstructural developments of neutron irradiated JPCA and USPCA, which are Ti-modified austenitic stainless steels and candidate structural material for fusion reactor first wall, have been examined. The irradiation has been performed in High Flux Isotope Reactor (HFIR) at temperatures ranging between 300 and 600°C to a peak neutron fluence corresponding to approximately 34 dpa and 2500 appm helium. MC precipitation on the radiation-induced dislocation lines is reduced at 500°C and above. This reduces the effective sink strength and increase the number of sites for helium bubble formation, which may lead to a severe reduction in the incubation regime of swelling at these temperatures. The factors controlling the stability of the MC precipitates in PCA's is discussed.

引用

页码：801 / 805

页数：5

共 17 条

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[2]

CHIN BA, 1982, NUCL TECHNOL, V57, P435

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