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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
Source PublicationMATERIALS AND CORROSION-WERKSTOFFE UND KORROSION
ISSN0947-5117
Volume69Issue:3Pages:328-336
AbstractThe 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.
description.department[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
KeywordHigh-temperature Water Environmentally Assisted Cracking Reactor Primary Water Pwr Primary Water Pressurized-water Dissolved-oxygen Oxidation Behavior Nickel-alloys Growth Metal
Subject AreaMaterials Science, Multidisciplinary ; Metallurgy & Metallurgical Engineering
Funding OrganizationNational Natural Science Foundation of China [51301183]; Key Research Program of Frontier Sciences, CAS [QYZDY-SSW-JSC012]
Indexed BySCI
Language英语
Document Type期刊论文
Identifierhttp://ir.imr.ac.cn/handle/321006/79459
Collection中国科学院金属研究所
Corresponding AuthorWang, JQ (reprint author), Chinese Acad Sci, Inst Met Res, Key Lab Nucl Mat & Safety Assessment, 62 Wencui Rd, Shenyang 110016, Liaoning, Peoples R China.
Recommended Citation
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.
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