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The studies of irradiation assisted stress corrosion cracking on reactor internals stainless steel under Xe irradiation
Wang, RS; Xu, CL; Liu, XB; Huang, P; Chen, Y; Chen Y(陈雨)
2015
发表期刊JOURNAL OF NUCLEAR MATERIALS
卷号457页码:130-134
文章类型Article
摘要Specimens of Chinese domestic reactor internals stainless steel were irradiated with 6 MeV Xe ions for three peak displacement damage of 2, 7 and 15 dpa at room temperature. The slow strain rate tests (SSRT), grazing incidence X-ray diffraction (GIXRD) and nano-indentation tests were carried out to study the IASCC properties, phase transition and nano-hardness variations. The SSRT results indicate that the IASCC susceptibility increases with irradiation damage. Ion irradiation accelerates the stress corrosion cracking (SCC). A new ferrite phase diffraction peak of a(110) after irradiated to 7 dpa and another two a phase of alpha(200) and alpha(211) after irradiated to 15 dpa were observed by GIXRD, which may be due to localized deformation. A similar trend of irradiation hardening and IASCC susceptibility was observed, which suggests an essential connection between them. (C) 2014 Elsevier B.V. All rights reserved.
学科领域Materials Science; Nuclear Science & Technology; Mining & Mineral Processing
DOI10.1016/j.jnucmat.2014.11.019
收录类别SCI ; EI
WOS类目Materials Science, Multidisciplinary ; Nuclear Science & Technology ; Mining & Mineral Processing
WOS记录号WOS:000349169100017
引用统计
被引频次:4[WOS]   [WOS记录]     [WOS相关记录]
文献类型期刊论文
条目标识符http://ir.ihep.ac.cn/handle/311005/228124
专题多学科研究中心
推荐引用方式
GB/T 7714
Wang, RS,Xu, CL,Liu, XB,et al. The studies of irradiation assisted stress corrosion cracking on reactor internals stainless steel under Xe irradiation[J]. JOURNAL OF NUCLEAR MATERIALS,2015,457:130-134.
APA Wang, RS,Xu, CL,Liu, XB,Huang, P,Chen, Y,&陈雨.(2015).The studies of irradiation assisted stress corrosion cracking on reactor internals stainless steel under Xe irradiation.JOURNAL OF NUCLEAR MATERIALS,457,130-134.
MLA Wang, RS,et al."The studies of irradiation assisted stress corrosion cracking on reactor internals stainless steel under Xe irradiation".JOURNAL OF NUCLEAR MATERIALS 457(2015):130-134.
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