STRESS-CORROSION CRACKING OF NI-CR-FE ALLOY 600 IN STEAM-GENERATOR ENVIRONMENTS - A REVIEW

被引：0

作者：

SERRA, ET ^{[1
]}

机构：

[1] CTR PESQUISAS ENERGIA ELECTR, DEPT MAT, RIO DE JANERIO, BRAZIL

来源：

TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY | 1981年 / 39卷

关键词：

D O I：

暂无

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

引用

页码：447 / 450

页数：4

共 9 条

[1] CELS JR, 1976, J ELECTROCHEM SOC, V12, P152
[2] COWAN RL, 1973, S HIGH TEMPERATURE H
[3] COWAN RL, 1977, P INT C SCC HYDROGEN
[4] HICKLING H, 1980, CORROS SCI, V20, P269
[5] LEE KH, 1980, FCC7805 EPRI RP11661
[6] MORRIS P, 1979, EPRIRP11701 EL POW R
[7] INFLUENCE OF THERMAL-TREATMENT ON THE SCC BEHAVIOR OF INCONEL ALLOY 600 AT CONTROLLED POTENTIALS IN 10-PERCENT CAUSTIC SODA SOLUTIONS AT 315C
PESSALL, N
AIREY, GP
LINGENFELTER, BP
[J]. CORROSION, 1979, 35 (03) : 100 - 107
[8] THEUS GJ, 1976, NUCL TECHNOL, V28, P388
[9] REVIEW OF STRESS-CORROSION CRACKING OF INCONEL-600
VANROOYEN, D
[J]. CORROSION, 1975, 31 (09) : 327 - 336