Primary water stress corrosion cracking behaviors in the shot-peened Alloy 600 TT steam generator tubings

被引：13
|
作者：
Park, IG [1 ]
机构：
[1] Sun Moon Univ, Dept Mat & Chem Engn, ChungNam 336840, South Korea
来源：
NUCLEAR ENGINEERING AND DESIGN | 2002年 / 212卷 / 1-3期
关键词：
Alloys - Compressive stress - Crack propagation - Nuclear power plants - Pressure tube reactors - Residual stresses - Shot peening - Stress corrosion cracking - Tubing;
D O I：
10.1016/S0029-5493(01)00500-3
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：
The effect of compressive residual stress on the primary water stress corrosion cracking behavior was investigated, based on the J-1 and J-2 nuclear power plant data. The following analyses were performed such as: (i) Weibull slope; (ii) crack growth rate; (iii) average crack length; (iv) crack length distribution. Alloy 600 TT exhibits strong heat to heat variations in its sensitivity to PWSCC. Crack growth rate was retarded after shot-peening. The compressive residual stress induced by shot-peening was more effective on new, short cracks, than on existing, long cracks. However, whether the 'new' cracks were initiated after peening is an unresolved issue, due to the present ECT sensitivity limit. (C) 2002 Elsevier Science B.V. All rights reserved.
引用
收藏
页码：395 / 399
页数：5
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