IMECH-IR  > 非线性力学国家重点实验室
Irradiation effect on impact fracture behavior of A508-3 steel in ductile-to-brittle transition range
Zhou ZY; Tong ZF; Qian GA(钱桂安); Zhong WH; Wang CL; Yang W; Berto F
Source PublicationENGINEERING FAILURE ANALYSIS
2019-03-01
Volume97Pages:836-843
ISSN1350-6307
AbstractThe mechanical performance of reactor pressure vessel (RPV) materials is an important factor in determining the safety and economics of the operation of a nuclear power plant. The ductile-to-brittle transition temperature (DBTT) tested by Charpy impact test is an important parameter for evaluating the RPV embrittlement. In this paper, the Charpy impact test of RPV steel prior and after irradiation was carried out at different temperatures. The fracture morphology was observed by scanning electron microscopy. The irradiation effect on the impact fracture behavior was analyzed in the DBTT temperature zone. Results show that in the DBTT range, the crack initiation and propagation energy are obviously reduced for the irradiated material. After irradiation, the dimple area on the fracture surface is significantly reduced, and the distance from the crack initiation source to the gap is decreased. For the RPV steel with low Cu steel content, matrix damage becomes the main factor on material irradiation embrittlement.
KeywordReactor pressure vessel Neutron embrittlement Crack propagation Plastic deformation Charpy impact test Scanning electron microscopy
DOI10.1016/j.engfailanal.2019.01.053
Indexed BySCI ; EI
Language英语
WOS IDWOS:000456719900062
WOS KeywordFATIGUE LIFE PREDICTION ; ENERGY ; SIZE ; CONSTRAINT ; MODE
WOS Research AreaEngineering, Mechanical ; Materials Science, Characterization & Testing
WOS SubjectEngineering ; Materials Science
Funding OrganizationLarge-scale Advanced PWR Nuclear Power Plant Major Projects [2018ZX06002008] ; National Natural Science Foundation of China [11872364]
Classification二类
Ranking1
Citation statistics
Document Type期刊论文
Identifierhttp://dspace.imech.ac.cn/handle/311007/78439
Collection非线性力学国家重点实验室
Affiliation1.{Zhou, Ziyang、Tong, Zhenfeng、Zhong, Weihua、Wang, Chenglong、Yang, Wen} China Inst Atom Energy, Beijing, Peoples R China
2.{Qian, Guian} Chinese Acad Sci, Inst Mech, State Key Lab Nonlinear Mech LNM, Beijing, Peoples R China
3.{Berto, Filippo} Norwegian Univ Sci & Technol NTNU, Dept Mech & Ind Engn, Richard Birkelands Vei 2b, N-7491 Trondheim, Norway
Recommended Citation
GB/T 7714
Zhou ZY,Tong ZF,Qian GA,et al. Irradiation effect on impact fracture behavior of A508-3 steel in ductile-to-brittle transition range[J]. ENGINEERING FAILURE ANALYSIS,2019,97:836-843.
APA Zhou ZY.,Tong ZF.,钱桂安.,Zhong WH.,Wang CL.,...&Berto F.(2019).Irradiation effect on impact fracture behavior of A508-3 steel in ductile-to-brittle transition range.ENGINEERING FAILURE ANALYSIS,97,836-843.
MLA Zhou ZY,et al."Irradiation effect on impact fracture behavior of A508-3 steel in ductile-to-brittle transition range".ENGINEERING FAILURE ANALYSIS 97(2019):836-843.
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