TENSILE PROPERTIES OF AUSTENITIC STAINLESS-STEELS AND THEIR WELD JOINTS AFTER IRRADIATION BY THE ORR-SPECTRALLY-TAILORING EXPERIMENT

被引：26

作者：

JITSUKAWA, S ^{[1
]}

MAZIASZ, PJ ^{[1
]}

ISHIYAMA, T ^{[1
]}

GIBSON, LT ^{[1
]}

HISHINUMA, A ^{[1
]}

机构：

[1] OAK RIDGE NATL LAB,OAK RIDGE,TN 37831

来源：

JOURNAL OF NUCLEAR MATERIALS | 1992年 / 191卷 / pt B期

关键词：

D O I：

10.1016/0022-3115(92)90576-7

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

Tensile specimens of the Japanese heat of PCA (JPCA) and type 316 stainless steels were irradiated in spectrally tailored capsules in the Oak Ridge Research Reactor (ORR) to a peak dose of 7.4 dpa and a peak helium level of 105 appm in the temperature range between 328 and 673 K. Specimens of type 316 steel with weld joints produced by tungsten inert gas (TIG) and electron beam (EB) welding techniques were also included. Irradiation caused both increases in flow stress and decreases in elongation. Weld joint specimens exhibited both lower strength and elongation after irradiation. The reduction of area (RA) for the TIG weld joint specimens decreased by a factor of 5 compared to unirradiated base metal specimens, however, they still fractured in a ductile mode. The EB weld joints maintained RA levels similar to that of the unirradiated base metal specimens. Post-radiation ductilities of weld joints and base metal specimens of these steels should be adequate for their application to next generation fusion experimental devices, such as the International Tokamak Experimental Reactor (ITER).

引用

页码：771 / 775

页数：5

共 4 条

[1]

GREENWOOD LR, 1989, DOEER03136 OFF FUS E, P23

[2] EMPIRICAL RELATIONS FOR TENSILE PROPERTIES OF AUSTENITIC STAINLESS-STEELS IRRADIATED IN MIXED-SPECTRUM REACTORS [J].