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《Engineering Mechanics》 2010-08
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EVALUATION OF THE THERMAL AGING EFFECT ON CHARPY IMPACT PROPERTIES OF THE PRIMARY PIPE MATERIAL IN NUCLEAR POWER STATION

XUE Fei 1 ,SHU Guo-gang 2 , * YU Wei-wei 1 ,WANG Zhao-xi 1,3 ,MENG Xin-ming 1 ,TI Wen-xin 1 (1.Suzhou Nuclear Power Research Institute,Suzhou,Jiangsu 215004,China; 2.China Nuclear Power Engineering Company,Limited,Shenzhen,Guangdong 518124,China; 3.School of Aerospace,Tsinghua University,Beijing 100084,China)  
Instrumented impact test was performed on the Nuclear Power Plant primary pipe material, Z3CN20.09M duplex stainless steel aged at 400oC for up to 3000 hours to characterize the thermal aging embrittlement effect on the Charpy impact properties.The impact test results show that,with the increment of the aging time for more than 100 hours,the ductile displacement decreases while the dynamic yielding load and the unloading slope presenting the crack propagation rate increase.The crack initiation energy,crack propagation energy and the total Charpy impact energy increase slightly then decrease sharply with the increment of the aging time for thermal aging embrittlement effect.The results also indicate that the reduction of the crack propagation energy is the predominant reason of the thermal aging effect on the impact property of Z3CN20.09M steel. Comparing the experimental results with the semi-empirical predictions using the embrittlement kinetics theory,itis found that the predictions agree well with the experimental results.The SEM results show that fracture surface patterns change from ductile fracture with shallow dimples to cleavage brittle fracture with the increment of the aging time.
【Fund】: 973项目(2007BC209802);; 江苏省自然科学基金项目(BK2008177)
【CateGory Index】: TM623;TG142.71
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【Citations】
Chinese Journal Full-text Database 2 Hits
1 LI Shilei,WANG Yanli,CHENG Lu,WANG Xitao,LIN Zhi,CHEN Guoliang State Key Laboratory for Advanced Metals and Materials,University of Science and Technology Beijing,Beijing 100083,China;Thermal aging mechanism of Z3CN20-09M cast austenite stainless steel[J];Journal of University of Science and Technology Beijing;2008-10
2 LIU Peng1,XUE Fei2,DAI Zhong-hua1,CHEN Shi-jun1,ZHU Wen-bin1,WANG Xiao-long2,TI Wen-xin2(1.Daya Bay Nuclear Power Operation and Management Co.Ltd.,Shenzhen,Guangdong,518124,China;2.Suzhou Thermal Research Institute,Suzhou,Jiangsu,215004,China);Thermal Aging and Aging Management of Cast Stainless Steel in LWR Nuclear Power Station[J];Nuclear Power Engineering;2005-S1
【Co-citations】
Chinese Journal Full-text Database 3 Hits
1 LI Shilei,WANG Yanli,CHENG Lu,WANG Xitao,LIN Zhi,CHEN Guoliang State Key Laboratory for Advanced Metals and Materials,University of Science and Technology Beijing,Beijing 100083,China;Thermal aging mechanism of Z3CN20-09M cast austenite stainless steel[J];Journal of University of Science and Technology Beijing;2008-10
2 ZHAO Qiang,WANG Yan-li,CHENG Lu,LIN Zhi,HE Jian-ping,LIN Jun-pin (State Key Laboratory for Advanced Metals and Materials,University of Science & Technology Beijing,Beijing 100083,China);Microcosmic mechanical properties of thermal aged cast austenite stainless steel in primary circuit in nuclear plant[J];Chinese Journal of Nuclear Science and Engineering;2007-03
3 MENG Xin-ming1,GENG Bo1,YU Wei-wei1,XUE Fei1,WANG Zhao-xi1,TI Wen-xin1,SHI Chong-zhe2(1.Suzhou Nuclear Power Research Institute,Suzhou 215004,China;2.School of Meterials and Chemical Engineering,Xi'an Technological University,Xi'an 710032,China);Investigation of the Thermal Aging Effect on the Tensile Property of Primary Pipe Material in Nuclear Power Plant[J];Journal of Xi'an Technological University;2009-04
【Secondary Citations】
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4 SHU Guo-gang LU Nian-wen(Suzhou Nuclear Power Research Institute Co.,Ltd.,Suzhou 215004,China);Aging problems and life evaluation for the key metallic components in PWR nuclear power plant[J];Electric Power;2006-05
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