Effect of dissolved oxygen content on stress corrosion cracking of a cold worked 316L stainless steel in simulated pressurized water reactor primary water environment

被引：57
作者：
Zhang, Litao [1 ]
Wang, Jianqiu [1 ]
机构：
[1] Chinese Acad Sci, Inst Met Res, State Key Lab Corros & Protect, Shenyang 110016, Peoples R China
来源：
JOURNAL OF NUCLEAR MATERIALS | 2014年 / 446卷 / 1-3期
关键词：
HIGH-TEMPERATURE WATER; ASSISTED CRACKING; ALLOY; 690TT; PURE WATER; GROWTH; BEHAVIOR; DEPENDENCE; CHEMISTRY; COOLANT; MODEL;
D O I：
10.1016/j.jnucmat.2013.11.027
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
Stress corrosion crack growth tests of a cold worked nuclear grade 316L stainless steel were conducted in simulated pressurized water reactor (PWR) primary water environment containing various dissolved oxygen (DO) contents but no dissolved hydrogen. The crack growth rate (CGR) increased with increasing DO content in the simulated PWR primary water. The fracture surface exhibited typical intergranular stress corrosion cracking (IGSCC) characteristics. (C) 2013 Elsevier B.V. All rights reserved.
引用
收藏
页码：15 / 26
页数：12
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