Stress corrosion cracking susceptibility of steam generator tube materials in AVT (all volatile treatment) chemistry contaminated with lead

被引:16
作者
Briceno, DG
Castano, ML
Garcia, MS
机构
[1] CIEMAT, E-28040 Madrid
关键词
Contamination - Corrosion resistance - Cracks - Fabrication - Lead - Steam generators - Stress corrosion cracking - Tubes (components);
D O I
10.1016/0029-5493(96)01195-8
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
Alloy 600 steam generator tubing has shown a high susceptibility to stress corrosion degradation at the operation conditions of pressurized water reactors. Several contaminants, such as lead, have been postulated as being responsible for producing the secondary side stress corrosion cracking that has occurred mainly at the location where these contaminants can concentrate. An extensive experimental work has been carried out in order to better understand the effects of lead on the stress corrosion cracking susceptibility of steam generator tube materials, namely Alloys 600, 690 and 800. This paper presents the experimental work conducted with a view to determining the influence of lead oxide concentration in AVT (all volatile treatment) conditions on the stress corrosion resistance of nickel alloys used in the fabrication of steam generator tubing.
引用
收藏
页码:161 / 169
页数:9
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