Research Progress on Breakaway Oxidation of Zircaloy Cladding under LOCA Conditions
摘 要
失稳氧化是导致锆合金包壳脆化的原因之一。介绍了与锆合金失稳氧化有关的氧化膜特征、机理、影响因素,以及目前仍然存在的问题,旨在为失稳氧化的研究提供参考。
Abstract
Breakaway oxidation is one of the causes for the embrittlement of zircaloy cladding. The oxide film characteristics, mechanism, influencing factors and current existing issues for breakaway oxidation of zircaloys are introduced in order to provide references for the study of breakaway oxidation.
中图分类号 TG172 DOI 10.11973/fsyfh-202012006
所属栏目 专论
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收稿日期 2018/9/10
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引用该论文: XU Qian,DIAO Junhui,JI Songtao. Research Progress on Breakaway Oxidation of Zircaloy Cladding under LOCA Conditions[J]. Corrosion & Protection, 2020, 41(12): 31
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参考文献
【1】LEISTIKOW S,SCHANZ G. Comprehensive presentation of extended zircaloy-4 steam oxidation results (600-1600℃)[R]//OECD-NEA-CSNI/IAEA Specialists Meeting on Water Reactor Fuel Safety and Fission Product Release in Off-Normal and Accident Conditions. Springfield:Nuclear Energy Agency,1983.
【2】YAN Y,BURTSEVA T A,BILLONE M C. High-temperature steam-oxidation behavior of Zr-1Nb cladding alloy E110[J]. Journal of Nuclear Materials,2009,393(3):433-448.
【3】KIM H G,KIM I H,CHOI B K,et al. A study of the breakaway oxidation behavior of zirconium cladding materials[J]. Journal of Nuclear Materials,2011,418(1/2/3):186-197.
【4】PARK D J,PARK J Y,JEONG Y H,et al. Microstructural characterization of ZrO2 layers formed during the transition to breakaway oxidation[J]. Journal of Nuclear Materials,2010,399(2/3):208-211.
【5】BARBERIS P. Zirconia powders and Zircaloy oxide films:tetragonal phase evolution during 400℃ autoclave tests[J]. Journal of Nuclear Materials,1995,226(1/2):34-43.
【6】BAEK J H,JEONG Y H. Breakaway phenomenon of Zr-based alloys during a high-temperature oxidation[J]. Journal of Nuclear Materials,2008,372(2/3):152-159.
【7】YILMAZBAYHAN A,BREVAL E,MOTTA A T,et al. Transmission electron microscopy examination of oxide layers formed on Zr alloys[J]. Journal of Nuclear Materials,2006,349(3):265-281.
【8】KIM H G,PARK J Y,CHOI B K,et al. Evaluation of pre-transition oxide on Zr-0.4 Nb alloy by using the HVEM[J]. Journal of Nuclear Materials,2008,374(1/2):204-210.
【9】WADMAN B,LAI Z,ANDRÉN H O,et al. Microstructure of oxide layers formed during autoclave testing of zirconium alloys[C]//Zirconium in the Nuclear Industry:Tenth International Symposium. West Conshohocken,PA:ASTM International,1994:579-598.
【2】YAN Y,BURTSEVA T A,BILLONE M C. High-temperature steam-oxidation behavior of Zr-1Nb cladding alloy E110[J]. Journal of Nuclear Materials,2009,393(3):433-448.
【3】KIM H G,KIM I H,CHOI B K,et al. A study of the breakaway oxidation behavior of zirconium cladding materials[J]. Journal of Nuclear Materials,2011,418(1/2/3):186-197.
【4】PARK D J,PARK J Y,JEONG Y H,et al. Microstructural characterization of ZrO2 layers formed during the transition to breakaway oxidation[J]. Journal of Nuclear Materials,2010,399(2/3):208-211.
【5】BARBERIS P. Zirconia powders and Zircaloy oxide films:tetragonal phase evolution during 400℃ autoclave tests[J]. Journal of Nuclear Materials,1995,226(1/2):34-43.
【6】BAEK J H,JEONG Y H. Breakaway phenomenon of Zr-based alloys during a high-temperature oxidation[J]. Journal of Nuclear Materials,2008,372(2/3):152-159.
【7】YILMAZBAYHAN A,BREVAL E,MOTTA A T,et al. Transmission electron microscopy examination of oxide layers formed on Zr alloys[J]. Journal of Nuclear Materials,2006,349(3):265-281.
【8】KIM H G,PARK J Y,CHOI B K,et al. Evaluation of pre-transition oxide on Zr-0.4 Nb alloy by using the HVEM[J]. Journal of Nuclear Materials,2008,374(1/2):204-210.
【9】WADMAN B,LAI Z,ANDRÉN H O,et al. Microstructure of oxide layers formed during autoclave testing of zirconium alloys[C]//Zirconium in the Nuclear Industry:Tenth International Symposium. West Conshohocken,PA:ASTM International,1994:579-598.
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