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Proactive Management of Materials Degradation Research in China

Engagement Workshop International Forum on LWR Aging Management Seoul National University, Oct. 12-13, 2009. Proactive Management of Materials Degradation Research in China. En-Hou Han Institute of Metal Research (IMR) Chinese Academy of Sciences ehhan@imr.ac.cn.

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Proactive Management of Materials Degradation Research in China

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  1. Engagement Workshop International Forum on LWR Aging Management Seoul National University, Oct. 12-13, 2009 Proactive Management of Materials Degradation Research in China En-Hou Han Institute of Metal Research (IMR) Chinese Academy of Sciences ehhan@imr.ac.cn

  2. Nuclear Power Plants in Mainland of China • Operation: 11 Reactors • 9 PWR (3 China made; 4 from France; 2 from Russia ) • 2 HWR (from Canada) • Under construction & Planning: 4 reactors/year

  3. R&D Institutions Pertaining to Nuclear Power in China C A,F,H, I, K D B,G, J E Research A. China Institute of Atomic Energy (CIAE), Beijing --CNNC B. Shanghai Research Institute of Materials (SRIM), --Independent C. Institute of Metal Research (IMR), Chinese Academy of Science (CAS), Shenyang –Government Supported D. Suzhou Nuclear Power Research Institute Co.Ltd (SNPRI), --CGNPC Design E. Nuclear Power Institute of China (NPIC), Chengdu --CNNC F. Beijing Institute of Nuclear Engineering (BINE), Beijing --CNNC G.The Shanghai Nuclear Engineering Research & Design Institute (SNERDI) --CNNC H.Institute of Nuclear and New Energy Technology (INET), University I. Tsinghua University(TU), --Independent J. Shanghai Jiaotong Uni.(SJTU)–Independent K. Uni. Sci. Tech. Beijing (USTB), –Independent

  4. Current laboratory test loops in China • IMR: 4 • NPIC: 3 • CIAE: 2 • SRIM: 1 • SNPRI: 1

  5. Laboratory test loops are under construction in China • IMR: 5 • SJTU: 2 • USTB: 1 • SNPRI: 1

  6. The largest research program in ChinaEnvironmental behavior of materials in nuclear power plant and its failurePI: En-Hou Han 2006-2011 • Corrosion mechanisms and electrochemistry in high temperature pressurized water • Stress corrosion cracking (SCC) for SG materials • Irradiation damage mechanisms and evaluation • Nondestructive methodologies • Lifetime prediction • Data base and its utilization En-Hou Han Jianqiu Wang Wen Yang Shizhe Song Guangfu Li Xiaoyan Tong

  7. 1. Corrosion mechanisms and electrochemistry in high temperature pressurized water • E-pH diagram in high temperature pressurized water especially when Pb, S etc. present • Electrochemical dynamics in high temperature pressurized water • Pb precipitation dynamics and its roles on corrosion • Synergistic effects of Cl-、SO42- • Film Characterization • Grain boundary effects on corrosion IMR Shanghai University

  8. 2. Stress corrosion cracking (SCC) for SG materials For 690 • Pb SCC • Cold work effect on SCC • Cl- , SO42- effects on SCC • Surface film properties and its influence on crack initiation IMR

  9. 3. Irradiation damage mechanisms and evaluation For RPV steels • Neutron irradiation • Proton irradiation • Cu cluster formation mechanisms • Small specimen test technique, size effect on J, DBTT • Molecular dynamic simulation NPIC CIAE Shanghai Univ. Tsinghua Univ. Univ. Sci. Tech. Beijing

  10. 4. Nondestructive methodologies • Electrochemistry based for films’ properties change • Electrochemical noise • Electrochemical Impedance Spectrum • Electrochemical pulse • Reluctivity probe • Digital laser holography • Computer simulation on flow-assisted corrosion Tianjing Univ. Shandong Univ. IMR

  11. 5. Lifetime prediction For RPV steel and SS • Damage modeling for SCC • Environmental effects on CF • Multi-defects probability damage analysis methodology • Environmental effect on fracture toughness • Aging probability analysis (APSA) SRIM IMR Northeastern Univ. Univ. Sci. Tech. Beijing

  12. 6. Data base and its utilization • Data structure • Basic materials’s properties • Experimental data • Experience data in power plant • Failure analysis data • Data mining Northwestern Poly. Univ. IMR SNPRI Beihang Univ.

  13. Planning future research programs 2010-2014 • Materials degradation • Water chemistry • Aging evaluation

  14. Contact person • IMR: En-Hou Han • NPIC: Qian Peng • CIAE: Wen Yang • SRIM: Guangfu Li • SNPRI: Ai Ren • SJTU: Lefu Zhang • USTB: Dongbei Sun

  15. Main focus in the institutions • IMR: En-Hou Han • High temperature electrochemistry • Surface effect and Film characterization • Cold work effect • Dissimilar weld effect • Stress corrosion cracking of Ni-based alloy • Corrosion fatigue of LAS • Corrosion of SS • FAC of CS • Water chemistry effect • Sensors • Lifetime evaluation and modeling • Data base

  16. Main focus in the institutions(Cont.) • NPIC: Qian Peng • Irradiation effects • Corrosion and cracking of Zr alloys • Corrosion fatigue • CIAE: Wen Yang • Irradiation effects • Corrosion and cracking of Zr alloys • SCC • Water chemistry effect • SRIM: Guangfu Li • SCC • Lifetime evaluation

  17. Main focus in the institutions (Cont.) • SNPRI: Ai Ren • CF of LAS • SCC • Dissimilar weld effect • Temperature aging effect • SJTU: Lefu Zhang • Corrosion products release • Dissimilar weld effect • USTB: Dongbei Sun • Lifetime evaluation

  18. Institute of Metal Research (IMR) IMR, CAS is the top institution on materials in China. It has been long-term engaged in the studies on mechanics / chemistry interaction and EAC issues.  1980th, a cooperative project with University of Newcastle upon Tyne in U.K. on SCC behavior of components’ materials in NPPs.  1990th, a cooperative research with National Research Institute of Metal (NRIM) in Japan on crevice corrosion of low-alloy steels in high temperature pressurized water and its effects on low cycle fatigue properties,.  IMR also finished several projects on environmental damage behavior of materials in supercritical water.

  19. Research Work in IMR Research Group The research group of high temperature pressurized water in IMR, consists of full-time staffs and graduates, including 7 professors, 2 associate professors, 1 senior engineer, 2 assistant professors, 2 technicians, 16 graduates. Total 30 persons.

  20. Seminar on Materials Problems in Light Water Nuclear Power Plant--Status, Mitigation, Future Problems Feb. 20-23, 2005 Chairmen: En-Hou Han Roger Staehle

  21. Seminar on Materials Problems in Light Water Nuclear Power Plant--Status, Mitigation, Future Problems

  22. 5th IMR Symposium on Materials Sciences and Engineering  --Materials and Reliability in Nuclear Power Plants July 22-24, 2009 Chairmen: En-Hou Han Lijian Rong

  23. Research Projects Involved in IMR (1) “Environmental sensitive cracking in energy source industry”, jointly supported by the CAS, China and Britain Cultural Association, U.K. (2) “Corrosion behavior of alloys in high temperature alkaline solutions”, supported by the Amoco Corporation, USA. (3) “Crevice corrosion and its effects on low cycle fatigue of low alloy steels in high temperature pressurized water”, jointly supported by the NRIM, Japan and CAS, China. (4) “Corrosion behavior of materials used for nuclear waste container”, supported by the Nevada State Government, USA. (5) “Environmental assisted cracking behavior of LWR structural materials”, supported by the Innovation Fund, IMR, CAS, China. (6) “Environmental behavior and failure mechanisms of materials”, supported by the Special Funds for the Major State Basic Research Projects, Ministry of Science and Technology (MOST), China. (7) “Study on corrosion Behavior of materials in supercritical water environments”, supported by the National Science Foundation of China. (8) “Corrosion testing systems of materials in supercritical water environments”, supported by the CAS, China. (9) “Corrosion and stress corrosion cracking in HTHP water”, supported by National Science Foundation of China (NSF-C) (10) MOST national 973 project, as above

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