Evaluation of stress corrosion cracking susceptibility of forged 316 stainless steel in simulated primary water

IMR OpenIR

	Evaluation of stress corrosion cracking susceptibility of forged 316 stainless steel in simulated primary water
	Zhu, RL; Wang, JQ; Ming, HL; Zhang, ZM; Han, EH; Wang, JQ (reprint author), Chinese Acad Sci, Inst Met Res, Key Lab Nucl Mat & Safety Assessment, 62 Wencui Rd, Shenyang 110016, Liaoning, Peoples R China.
	2018-03-01
发表期刊	MATERIALS AND CORROSION-WERKSTOFFE UND KORROSION
ISSN	0947-5117
卷号	69 期号:3 页码:328-336
摘要	The bolts for the reactor coolant pump are planned to be made of the forged 316 stainless steel. Prior to use, the stress corrosion cracking (SCC) resistance of the material requires investigation in simulated primary water at 320 degrees C. The crack growth rates (CGRs) of two duplicate compact tension (CT) specimens are measured using direct current potential drop method. The effects of stress intensity factor (K, changes from 21 to 41MPam), dissolved oxygen (DO, changes from<10 to 2000ppb) and dissolved hydrogen (DH, 2800ppb) on CGRs are comprehensively examined. The results indicate that CGR increases with increasing K. The forged 316 stainless steel is sensitive to SCC in oxygenated water. Changing oxygenated water to hydrogenated water leads to more than one order of magnitude decreases of CGR. The fracture surface, crack path, and the influence of the crack branching on CGR are discussed.; The bolts for the reactor coolant pump are planned to be made of the forged 316 stainless steel. Prior to use, the stress corrosion cracking (SCC) resistance of the material requires investigation in simulated primary water at 320 degrees C. The crack growth rates (CGRs) of two duplicate compact tension (CT) specimens are measured using direct current potential drop method. The effects of stress intensity factor (K, changes from 21 to 41MPam), dissolved oxygen (DO, changes from<10 to 2000ppb) and dissolved hydrogen (DH, 2800ppb) on CGRs are comprehensively examined. The results indicate that CGR increases with increasing K. The forged 316 stainless steel is sensitive to SCC in oxygenated water. Changing oxygenated water to hydrogenated water leads to more than one order of magnitude decreases of CGR. The fracture surface, crack path, and the influence of the crack branching on CGR are discussed.
部门归属	[zhu, ruolin ; wang, jianqiu ; ming, hongliang ; zhang, zhiming ; han, en-hou] chinese acad sci, inst met res, key lab nucl mat & safety assessment, 62 wencui rd, shenyang 110016, liaoning, peoples r china ; [zhu, ruolin] china nucl power operat technol corp ltd, wuhan 430223, hubei, peoples r china
关键词	High-temperature Water Environmentally Assisted Cracking Reactor Primary Water Pwr Primary Water Pressurized-water Dissolved-oxygen Oxidation Behavior Nickel-alloys Growth Metal
学科领域	Materials Science, Multidisciplinary ; Metallurgy & Metallurgical Engineering
资助者	National Natural Science Foundation of China [51301183]; Key Research Program of Frontier Sciences, CAS [QYZDY-SSW-JSC012]
收录类别	SCI
语种	英语
WOS记录号	WOS:000426650400004
引用统计	被引频次：2[WOS] [WOS记录] [WOS相关记录]
文献类型	期刊论文
条目标识符	http://ir.imr.ac.cn/handle/321006/79459
专题	中国科学院金属研究所
通讯作者	Wang, JQ (reprint author), Chinese Acad Sci, Inst Met Res, Key Lab Nucl Mat & Safety Assessment, 62 Wencui Rd, Shenyang 110016, Liaoning, Peoples R China.
推荐引用方式 GB/T 7714	Zhu, RL,Wang, JQ,Ming, HL,et al. Evaluation of stress corrosion cracking susceptibility of forged 316 stainless steel in simulated primary water[J]. MATERIALS AND CORROSION-WERKSTOFFE UND KORROSION,2018,69(3):328-336.
APA	Zhu, RL,Wang, JQ,Ming, HL,Zhang, ZM,Han, EH,&Wang, JQ .(2018).Evaluation of stress corrosion cracking susceptibility of forged 316 stainless steel in simulated primary water.MATERIALS AND CORROSION-WERKSTOFFE UND KORROSION,69(3),328-336.
MLA	Zhu, RL,et al."Evaluation of stress corrosion cracking susceptibility of forged 316 stainless steel in simulated primary water".MATERIALS AND CORROSION-WERKSTOFFE UND KORROSION 69.3(2018):328-336.