Irradiation effect on impact fracture behavior of A508-3 steel in ductile-to-brittle transition range

doi:10.1016/j.engfailanal.2019.01.053

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
发表期刊	ENGINEERING FAILURE ANALYSIS
	2019-03-01
卷号	97 页码:836-843
ISSN	1350-6307
摘要	The 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.
关键词	Reactor pressure vessel Neutron embrittlement Crack propagation Plastic deformation Charpy impact test Scanning electron microscopy
DOI	10.1016/j.engfailanal.2019.01.053
收录类别	SCI ; EI
语种	英语
WOS记录号	WOS:000456719900062
关键词[WOS]	FATIGUE LIFE PREDICTION ; ENERGY ; SIZE ; CONSTRAINT ; MODE
WOS研究方向	Engineering, Mechanical ; Materials Science, Characterization & Testing
WOS类目	Engineering ; Materials Science
项目资助者	Large-scale Advanced PWR Nuclear Power Plant Major Projects [2018ZX06002008] ; National Natural Science Foundation of China [11872364]
论文分区	二类
力学所作者排名	1
RpAuthor	Tong, ZF ; Qian, GA
引用统计	被引频次：16[WOS] [WOS记录] [WOS相关记录]
文献类型	期刊论文
条目标识符	http://dspace.imech.ac.cn/handle/311007/78439
专题	非线性力学国家重点实验室
作者单位	1.{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
推荐引用方式 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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