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) | |
刊名 | JOURNAL OF NUCLEAR MATERIALS |
2015 | |
卷号 | 457页码:130-134 |
英文摘要 | 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. |
学科主题 | Materials Science; Nuclear Science & Technology; Mining & Mineral Processing |
类目[WOS] | Materials Science, Multidisciplinary ; Nuclear Science & Technology ; Mining & Mineral Processing |
收录类别 | SCI ; EI |
WOS记录号 | WOS:000349169100017 |
公开日期 | 2016-05-03 |
内容类型 | 期刊论文 |
源URL | [http://ir.ihep.ac.cn/handle/311005/228124] |
专题 | 高能物理研究所_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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