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.
部门归属
[zhang, litao
; wang, jianqiu] chinese acad sci, inst met res, state key lab corros & protect, shenyang 110016, peoples r china.
; wang, jq (reprint author), chinese acad sci, inst met res, state key lab corros & protect, shenyang 110016, peoples r china.
; wangjianqiu@imr.ac.cn
L. T. Zhang,J. Q. Wang. Effect of dissolved oxygen content on stress corrosion cracking of a cold worked 316L stainless steel in simulated pressurized water reactor primary water environment[J]. Journal of Nuclear Materials,2014,446(1-3):15-26.
APA
L. T. Zhang,&J. Q. Wang.(2014).Effect of dissolved oxygen content on stress corrosion cracking of a cold worked 316L stainless steel in simulated pressurized water reactor primary water environment.Journal of Nuclear Materials,446(1-3),15-26.
MLA
L. T. Zhang,et al."Effect of dissolved oxygen content on stress corrosion cracking of a cold worked 316L stainless steel in simulated pressurized water reactor primary water environment".Journal of Nuclear Materials 446.1-3(2014):15-26.
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