IRRADIATION ASSISTED STRESS-CORROSION CRACKING OF CONTROLLED PURITY 304L STAINLESS-STEELS

被引：27

作者：

COOKSON, JM ^{[1
]}

CARTER, RD ^{[1
]}

DAMCOTT, DL ^{[1
]}

ATZMON, M ^{[1
]}

WAS, GS ^{[1
]}

机构：

[1] UNIV MICHIGAN,DEPT MAT SCI & ENGN,ANN ARBOR,MI 48109

来源：

JOURNAL OF NUCLEAR MATERIALS | 1993年 / 202卷 / 1-2期

关键词：

D O I：

10.1016/0022-3115(93)90034-V

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

The effect of chromium, phosphorus, silicon and sulfur on the stress corrosion cracking of 304L stainless steel in CERT tests in high purity water or argon at 288-degrees-C following irradiation with 3.4 MeV protons at 400-degrees-C to 1 dpa, has been investigated using ultrahigh purity alloys (UHP) with controlled impurity additions. Grain boundary segregation of phosphorus or silicon due to proton irradiation was quantified using both Auger electron spectroscopy and scanning transmission electron microscopy, and the alloys with impurity element additions were observed to have greater grain boundary chromium depletion and nickel enrichment than the UHP alloy. The UHP alloy suffered severe cracking in CERT tests in water. Less cracking was found after CERT tests of irradiated UHP+P or UHP+Si alloys, despite greater chromium depletion. This suggests a mitigating effect of phosphorus and silicon at grain boundaries. No cracking was found in argon tests, eliminating a purely mechanical embrittlement mechanism, but not eliminating a contribution from radiation hardening. Implanted hydrogen was not a factor in the intergranular cracking found.

引用

页码：104 / 121

页数：18

共 30 条

[1]

Andresen P. L., 1992, 5 INT S ENV DEGR MAT, P209

[2] ENVIRONMENTALLY ASSISTED CRACKING OF TYPES 304L 316L 316NG STAINLESS-STEEL IN 288-DEGREES-C WATER [J].