Corrosion fatigue behavior of Alloy 690 steam generator tube in borated and lithiated high temperature water

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	Corrosion fatigue behavior of Alloy 690 steam generator tube in borated and lithiated high temperature water
	J. B. Tan; X. Q. Wu; E. H. Han; W. Ke; X. Q. Liu; F. J. Meng; X. L. Xu
	2014
发表期刊	Corrosion Science
ISSN	0010-938X
卷号	89 页码:203-213
摘要	Corrosion fatigue behavior of Alloy 690 tube used for actual steam generator (SG) was investigated in <5 ppb (by weight) dissolved oxygen borated and lithiated high temperature water by low cycle fatigue tests with boat-shaped specimens. It was found that the present tube materials had longer fatigue life than round-bar materials in open literature. The surface cracks were tortuous, typical crack branching and linkage were observed. The fracture surfaces were rough with well-defined fatigue striations. Related mechanisms of fatigue crack initiation and propagation of Alloy 690 SG tube in high temperature water are discussed. (C) 2014 Elsevier Ltd. All rights reserved.
部门归属	[tan, jibo] univ sci & technol china, hefei 230000, peoples r china. [tan, jibo ; wu, xinqiang ; han, en-hou ; ke, wei] chinese acad sci, key lab nucl mat & safety assessment, liaoning key lab safety & assessment tech nucl ma, inst met res, shenyang 110016, peoples r china. [liu, xiaoqiang ; meng, fanjiang ; xu, xuelian] shanghai nucl engn res & design inst, shanghai 200233, peoples r china. ; wu, xq (reprint author), chinese acad sci, key lab nucl mat & safety assessment, liaoning key lab safety & assessment tech nucl ma, inst met res, shenyang 110016, peoples r china. ; xqwu@imr.ac.cn
关键词	Alloy Sem Corrosion Fatigue High Temperature Corrosion Environmentally Assisted Cracking Low-cycle Fatigue Austenitic Stainless-steels Pressure-vessel Steels Reactor Conditions Dissolved-oxygen Growth Behavior Initiation Mechanisms Prediction
URL	查看原文
语种	英语
文献类型	期刊论文
条目标识符	http://ir.imr.ac.cn/handle/321006/73382
专题	中国科学院金属研究所
推荐引用方式 GB/T 7714	J. B. Tan,X. Q. Wu,E. H. Han,et al. Corrosion fatigue behavior of Alloy 690 steam generator tube in borated and lithiated high temperature water[J]. Corrosion Science,2014,89:203-213.
APA	J. B. Tan.,X. Q. Wu.,E. H. Han.,W. Ke.,X. Q. Liu.,...&X. L. Xu.(2014).Corrosion fatigue behavior of Alloy 690 steam generator tube in borated and lithiated high temperature water.Corrosion Science,89,203-213.
MLA	J. B. Tan,et al."Corrosion fatigue behavior of Alloy 690 steam generator tube in borated and lithiated high temperature water".Corrosion Science 89(2014):203-213.