STRESS-CORROSION CRACKING AND INTERGRANULAR CORROSION OF AUSTENITIC STAINLESS-STEELS IRRADIATED AT 323-K

被引：15
作者：
KODAMA, M
MORISAWA, J
NISHIMURA, S
ASANO, K
SHIMA, S
NAKATA, K
机构：
[1] TOKYO ELECT POWER CO LTD, CHIYODA KU, TOKYO 100, JAPAN
[2] TOSHIBA CO LTD, DIV NUCL ENERGY, ISOGO KU, YOKOHAMA, KANAGAWA 235, JAPAN
[3] HITACHI LTD, HITACHI RES LAB, HITACHI, IBARAKI 317, JAPAN
来源：
JOURNAL OF NUCLEAR MATERIALS | 1994年 / 212卷 / pt B期
关键词：
D O I：
10.1016/0022-3115(94)91080-4
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
The effect of neutron irradiation on intergranular corrosion (IGC) and stress corrosion cracking (SCC) susceptibility was investigated in several austenitic stainless steels irradiated up to 3.0 X 10(25) n/m(2) (E > 1 MeV) at about 323 K. The IGC of commercial purity (CP) 304 and CP304L.in HNO3/Cr6+ solution was enhanced by neutron irradiation, while HP304 was immune to corrosion. The stainless steels except nuclear grade 316 (316NG) failed intergranularly after neutron irradiation by SSRT. HP304 showed higher IASCC susceptibility than CP304 and CP304L. The occurrence of IASCC in both HP and CP 304 indicated that radiation enrichment of impurities might not be the main contributor to IASCC. 316NG had better SCC resistance than 304 stainless steels under the present irradiation conditions. IASCC susceptibility could be correlated to the austenite phase stability.
引用
收藏
页码：1509 / 1514
页数：6
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