Full-Text Search:
Home|Journal Papers|About CNKI|User Service|FAQ|Contact Us|中文
《Journal of University of Science and Technology Beijing》 2013-05
Add to Favorite Get Latest Update

Thermal aging embrittlement of cast stainless steel for nuclear primary pipes

LI Shu-xiao~(1)),LI Shi-lei~(1)),L Xu-ming~(1)),WANG Yan-li~(1)),XUE Fei~(2)),WANG Xi-tao~(1)) 1) State Key Laboratory for Advanced Metals and Materials,University of Science and Technology Beijing,Beijing 100083,China 2) Suzhou Nuclear Power Research Institute,Suzhou 215004,China  
To study the thermal aging of the nuclear primary pipe material Z3CN20-09M,accelerated thermal aging experiments were performed at 300,350 and 400℃for 30000 h.Charpy impact energy and nanohardness of ferrite phase were tested for samples with different thermally aged time.Taking Charpy impact energy as the standard of thermal aging embrittlement,the thermal aging activation energy of the material was obtained to be 51.962 kJ·mol~(-1) by the fitting method.Meanwhile,the thermal aging parameter P was used to describe the kinetics of thermal aging embrittlement with Charpy impact energy.Finally,the Charpy impact energy and nanohardness of the material during 40 operation years at the actual operation temperature were estimated by the thermal aging activation energy and the thermal aging kinetics.The predicted results show that the toughness of the material decreases fast in the early 5 years, and then undergoes a slowly-decreased operation process.
【Fund】: 国家高技术研究发展计划资助项目(2012AA03A507 2012AA050901);; 国家重大科技专项资助项目(2011ZX06004)
【CateGory Index】: TL353.11
Download(CAJ format) Download(PDF format)
CAJViewer7.0 supports all the CNKI file formats; AdobeReader only supports the PDF format.
【Citations】
Chinese Journal Full-text Database 6 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 WANG Yongqiang,LI Shilei,YANG Bin,WANG Yanli,WANG Xitao(State Key Laboratory for Advanced Metals and Materials,University of Science and Technology Beijing,Beijing 100083);Research Status and Outlook on Thermal Aging of Cast Austenitic Stainless Steels Used in Primary Coolant Pipes of Nuclear Power Plant[J];Materials Review;2012-03
3 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
4 LI Shilei,WANG Yanli,LI Shuxiao,WANG Xitao State Key Laboratory for Advanced Metals and Materials,University of Science and Technology Beijing,Beijing 100083;EFFECT OF LONG TERM AGING ON THE MICROSTRUCTURE AND MECHANICAL PROPERTIES OF CAST AUSTENITIC STAINLESS STEELS[J];Acta Metallurgica Sinica;2010-10
5 XUE Fei 1,2,YU Wei-wei 2,,WANG Zhao-xi 2,MA Qin-zheng 2,LIU Wei 1 (1.Department of Materials Science and Engineering,Tsinghua University,Beijing 100084,China; 2.Suzhou Nuclear Power Research Institute,Suzhou 215004,China);Evaluation of Thermal Aging Effect on Primary Pipe Material in Nuclear Power Plant by Micro Hardness Test Method[J];Atomic Energy Science and Technology;2012-07
6 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
【Co-citations】
Chinese Journal Full-text Database 10 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 WANG Yongqiang,LI Shilei,YANG Bin,WANG Yanli,WANG Xitao(State Key Laboratory for Advanced Metals and Materials,University of Science and Technology Beijing,Beijing 100083);Research Status and Outlook on Thermal Aging of Cast Austenitic Stainless Steels Used in Primary Coolant Pipes of Nuclear Power Plant[J];Materials Review;2012-03
3 SHI Yao-xin,TIAN Hong-zhi State Nuclear Power Engineering Company,Shanghai 200233,China;Property Requirements and Technological Measures of a Based Metal for Reactor Pressure Vessels with an Expected 60-year Life[J];Power Equipment;2012-02
4 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);EVALUATION OF THE THERMAL AGING EFFECT ON CHARPY IMPACT PROPERTIES OF THE PRIMARY PIPE MATERIAL IN NUCLEAR POWER STATION[J];Engineering Mechanics;2010-08
5 LI Shu-xiao1,LV Xu-ming1,ZHANG Hai-long1,WANG Yan-li1,XUE Fei2,WANG Xi-tao1 (1.State Key Laboratory for Advanced Metals and Materials,University of Science and Technology Beijing,Beijng 100083,China;2.Suzhou Nuclear Power Research Institute,Suzhou 215004,China);Research on Failure Assessment Curves of Thermally Aged Nuclear Primary Pipe[J];Bulletin of the Chinese Ceramic Society;2013-05
6 LI Qiang,CEN Peng,ZHEN Hong-dong (China Nuclear Power Design Company,Ltd,Shenzhen,Guangdong,518057,China);Overview of LBB Analysis Technologies for High Power Lines in Nuclear Power Plants[J];Nuclear Power Engineering;2011-S1
7 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
8 LI Shilei,WANG Xitao,WANG Yanli,LI Shuxiao State Key Laboratory for Advanced Metals and Materials,University of Science and Technology Beijing,Beijing 100083;EFFECTS OF THERMAL AGING ON MICRO-MECHANICAL PROPERTIES AND IMPACT FRACTURE BEHAVIOR OF Z3CN20-09M STAINLESS STEELS[J];Acta Metallurgica Sinica;2011-06
9 XUE Fei1 YU WeiWei1 TI WenXin1 WANG ZhaoXi1,2 ZHANG Lu1 LIN Lei1 SHI ChongZhe3 (1.Suzhou Nuclear Power Research Institute,Suzhou 215004,China)(2.Department of Materials Science and Engineering,Tsinghua University,Beijing 100084,China)(3.School of Materials Science and Chemical Engineering,Xi′an Technological University,Xi′an 710032,China);LOW CYCLE FATIGUE BEHAVIOR OF PWR PRIMARY PIPE MATERIAL FOR NUCLEAR POWER PLANT[J];Journal of Mechanical Strength;2011-06
10 LIU Zhenting1,2,LIU Jiangnan2,GAO Wei2,SHI Chongzhe2(1.School of Materials Science and Engineering,Northwestern Polytechnical University,Xi'an 710072,China;2.School of Materials and Chemical Engineering,Xi'an Technology University,Xi'an 710032,China);Effect of Thermal Aging on Substructures of Cast Duplex Stainless Steel[J];Hot Working Technology;2010-18
China Proceedings of conference Full-text Database 1 Hits
1 XUE Fei~1,WANG Zhao-xi~(1,2),SHU Guo-gang~1,TI Wen-xin~1,YU Wei-wei~1,MENG Xin-ming~1 (1.Suzhou Nuclear Power Research Institute,Suzhou of Jiangsu Prov.215004,China; 2.School of Aero Space,Tsinghua University,Beijing 1000084,China);Thermal aging mechanism of the primary pipe CDSS[A];[C];2009
【Secondary Citations】
Chinese Journal Full-text Database 10 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 Yanfen,Ti Wenxin,Wang Xiaolong,Xue Fei ( Suzhou Thermal Tool Research Institute,Suzhou 215004,China);Steel Tubular Materials for Nuclear Power Plant Service and Production Localization[J];Steel Pipe;2007-02
3 Cheng Haitao,Guo Yuanrong(Pangang Group Chengdu Iron & Steel Co.,Ltd.,Chengdu 610303,China);Current Situation and Localization Progress of Pipes for Nuclear Power Generation Service[J];Steel Pipe;2008-04
4 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);EVALUATION OF THE THERMAL AGING EFFECT ON CHARPY IMPACT PROPERTIES OF THE PRIMARY PIPE MATERIAL IN NUCLEAR POWER STATION[J];Engineering Mechanics;2010-08
5 Xia Shenglan;Gu Shixiong;The Corrosion Basis of Primary Circuit Water Quality Specification of PWR[J];Nuclear Power Engineering;1988-02
6 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
7 WANG Qin-hu,LI She-kun,LU Wen-yue,YU Hai-feng,CAO Zhi-peng(Daya Bay Nuclear Power Operation and Management Co.Ltd,Shenzhen,Guangdong,518124,China);Effect of Operation Conditions of Primary Coolant System of PWR NPP on Mechanic Performance of Primary Coolant Pump[J];Nuclear Power Engineering;2005-S1
8 LI Yuan-tai, ZHANG Chun-lai, LEI Zhong-li (China Nuclear Power Engineering Co. Ltd., Shenzhen, Guangdong, 518124, China);Casting Technique for Primary Coolant Piping for Pressurized Water Reactor Power Plant and Its Localization[J];Nuclear Power Engineering;2009-S2
9 XUE Fei1,SHU Guo-gang1,TI Wen-xin1,YU Wei-wei1,MENG Xin-ming1 LIU Jing-nan2,SHI Chong-zhe2,manufactured by France was studied with Charpy impact test,which is used as the primary loop pipe in PWR nuclear power plant.Statistical analysis of the instrumental impact test data indicates that thermal ageing has 2.Xi’an Technological University,Xi’an,710032,China);Experimental Study on Thermal Aging Impact Properties of Austenitic Stainless Steel Z3CN20.09M[J];Nuclear Power Engineering;2010-01
10 LI Qi-zhi~1,LI Hui-zhong~2 (1.Changsha Dizhi Science and Technology Co.Ltd,Changsha 410087,China;2.Central South University,Changsha 410083,China);Effect of Microstructure and Mechanical Property of Duplex Stainless Steel under Different Heat-treatment[J];Hunan Nonferrous Metals;2006-01
©2006 Tsinghua Tongfang Knowledge Network Technology Co., Ltd.(Beijing)(TTKN) All rights reserved