IMR OpenIR
Life Prediction for Stress Corrosion Behavior of 316L Stainless Steel Elbow of Nuclear Power Plant
Guo Shu; Han En-Hou; Wang Haitao; Zhang Zhiming; Wang Jianqiu
Corresponding AuthorHan En-Hou(ehhan@imr.ac.cn)
2017-04-11
Source PublicationACTA METALLURGICA SINICA
ISSN0412-1961
Volume53Issue:4Pages:455-464
AbstractStress corrosion cracking (SCC) is one of the main ageing mechanism in light water reactor (LWR). 316L austenitic stainless steel was adopted in nuclear industry for its relatively high corrosion resistance. The SCC of austenitic stainless steel may occur as it is subjected to both the tensile stress and the caustic medium, with regard to maintaining the structural integrity of components in nuclear power plant, an accurate prediction and efficient assessment of the component lifetime is significant and necessary. The stress corrosion crack propagation behavior of the 316L stainless steel elbow of nuclear power plant was investigated through a numerical simulation method. Firstly a finite element (FE) model was created for the stainless steel thick-walled elbow (the outer diameter is 355.6 mm, the inner diameter is 275.6 mm), with a semi-elliptical shaped 3D defect introduced at the internal surface of the elbow as the geometry of the crack, which was consistent with a practical crack, the crack opening displacement (delta(i)) was determined by the calculations through the Dugdale model; subsequently, according to the FE calculation results, establish the fitting formula of the stress intensity factor (K) varying with the crack depth (a) and additional stress (P), and the fitting formula of the stress corrosion crack propagation rate (da/dt) for elbows under two types of cold work deformation was deduced through the combination with the experimental data, the crack propagation time was then calculated using a iterative method for cracks which evolved from different initial crack depth values to certain crack depth values. The calculation results provided effective reference criterion for the nuclear power plant safety assesment. This investigation demonstrated that, when the cold deformation extent of the elbow part is relatively small (with the hardness of 230 similar to 245 HV) and it is under the ideal condition (no initial additional stress), it takes around 57 a for the stress corrosion crack to penetrate the elbow, when the initial additional stress was elevated to 200 MPa, the elbow failure time was shrinked to 1/5 (no stress release), 2/7 (half-stress release) and 3/7 (total stress release) of the former; keep the same initial additional stress (200 MPa) and increase the cold work deformation extent (the hardness was increased from 230 similar to 245 HV to 275 similar to 300 HV), the elbow failure time was shortened to 2/5 (no stress release), 3/8 (half-stress release) and 1/3 (total stress release) for the elbow part with higher cold deformation extent compared to the part with lower cold deformation extent, thus it was observed that both the decrease of the extent of stress relaxation and the increase of the extent of cold work deformation contributed to the reduction of the residual life of the nuclear power plant 316L stainless steel elbow.
Keyword316L stainless steel elbow stress corrosion crack propagation crack opening displacement finite element analysis stress relaxation cold work deformation
Funding OrganizationNational Basic Research Program of China
DOI10.11900/0412.1961.2016.00462
Indexed BySCI
Language英语
Funding ProjectNational Basic Research Program of China[2011CB610500]
WOS Research AreaMetallurgy & Metallurgical Engineering
WOS SubjectMetallurgy & Metallurgical Engineering
WOS IDWOS:000399921900009
PublisherSCIENCE PRESS
Citation statistics
Cited Times:4[WOS]   [WOS Record]     [Related Records in WOS]
Document Type期刊论文
Identifierhttp://ir.imr.ac.cn/handle/321006/124580
Collection中国科学院金属研究所
Corresponding AuthorHan En-Hou
AffiliationChinese Acad Sci, Inst Met Res, Key Lab Nucl Mat & Safety Assessment, Shenyang 110016, Peoples R China
Recommended Citation
GB/T 7714
Guo Shu,Han En-Hou,Wang Haitao,et al. Life Prediction for Stress Corrosion Behavior of 316L Stainless Steel Elbow of Nuclear Power Plant[J]. ACTA METALLURGICA SINICA,2017,53(4):455-464.
APA Guo Shu,Han En-Hou,Wang Haitao,Zhang Zhiming,&Wang Jianqiu.(2017).Life Prediction for Stress Corrosion Behavior of 316L Stainless Steel Elbow of Nuclear Power Plant.ACTA METALLURGICA SINICA,53(4),455-464.
MLA Guo Shu,et al."Life Prediction for Stress Corrosion Behavior of 316L Stainless Steel Elbow of Nuclear Power Plant".ACTA METALLURGICA SINICA 53.4(2017):455-464.
Files in This Item:
There are no files associated with this item.
Related Services
Recommend this item
Bookmark
Usage statistics
Export to Endnote
Google Scholar
Similar articles in Google Scholar
[Guo Shu]'s Articles
[Han En-Hou]'s Articles
[Wang Haitao]'s Articles
Baidu academic
Similar articles in Baidu academic
[Guo Shu]'s Articles
[Han En-Hou]'s Articles
[Wang Haitao]'s Articles
Bing Scholar
Similar articles in Bing Scholar
[Guo Shu]'s Articles
[Han En-Hou]'s Articles
[Wang Haitao]'s Articles
Terms of Use
No data!
Social Bookmark/Share
All comments (0)
No comment.
 

Items in the repository are protected by copyright, with all rights reserved, unless otherwise indicated.