预形变及模拟压水堆一回路水中预浸泡对690合金拉伸性能的影响
Effects of Prior Deformation and Prior Immersion in Simulated Pressurized Water Reactor Primary Water on Tensile Properties of Alloy 690
摘 要
研究了预充氢和模拟压水堆核电站一回路水中预浸泡对有、无经过20%轧制冷加工690合金拉伸性能的影响.室温下空气中拉伸试验结果表明,冷加工显著提升690合金的抗拉强度并降低延伸率和断面收缩率;预充氢显著降低有、无冷加工690合金的延伸率和断面收缩率,并且降低冷加工690合金的抗拉强度;高温水中预浸泡对未冷加工690合金的拉伸性能有一定影响.320 ℃高温水中测得的抗拉强度、延伸率和断面收缩率均低于室温时的值;高温水中预浸泡对抗拉强度和延伸率的影响不大,使断面收缩率略有增大.
压水堆核电站
冷加工
拉伸试验
氢
nickel-based alloy 690
pressurized water reactor
cold work
tensile test
hydrogen
Abstract
The effects of prior hydrogen-charge and prior immersion in a simulated pressurized water reactor primary water on tensile properties of alloy 690 and 20% cold worked alloy 690 were investigated.Results of tensile tests in air at RT showed that cold work significantly increased the ultimate tensile strength,decreased the elongation ratio and reduction in area.Prior hydrogen-charge significantly decreased the elongation ratio and reduction in area,and decreased the tensile strength of cold worked alloy 690.Prior-immersion in high temperature water affected the tensile test behavior at RT.The values of tensile strength,elongation ratio and reduction in area in the simulated PWR primary water at 320 ℃ were significantly lower than those in air at RT.Prior-immersion did not show any significant effect on tensile strength and elongation ratio at 320 ℃,which increased the reduction in area.
中图分类号 TG172
所属栏目 试验研究
基金项目 核燃料与材料重点实验室基金项目;上海市浦江人才计划(12PJ1403600);教育部博士点基金博导类项目(20123108110021)
收稿日期 2014/3/30
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联系人作者吕战鹏(zplu@shu.edu.cn)
备注吕战鹏(1967-),研究员,博士,从事核电材料腐蚀与防护研究.
引用该论文: XIA Xiao-feng,Lv Zhan-peng,CHEN Jun-jie,XIAO Qian,RU Xiang-kun,ZHOU Bang-xin,XIONG Ru. Effects of Prior Deformation and Prior Immersion in Simulated Pressurized Water Reactor Primary Water on Tensile Properties of Alloy 690[J]. Corrosion & Protection, 2015, 36(2): 170
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参考文献
【1】FORD F P,GORDON B M,HORN R M.Intergranular stress corrosion cracking (IGSCC) in boiling water reactors (BWRs)[J].Nuclear Corrosion Science and Engineering,2012,286:548-580.
【2】JEONG H S,JIN K S,SUK J L K,et al.Investigation of IGSCC behavior of sensitized and laser-surface-melted alloy 600[J].Materials Science and Engineering,1998,254:67-75.
【3】YANG W,LU Z P,HUANG D L.Caustic stress corrosion cracking of nickel-rich,chromium-bearing alloys[J].Corros Sci.,2001,43(5):963-977.
【4】PENG Q J,YONEZAWAT,SHOJI T,et al.Environ-mentally assisted crack growth in one-dimensionally cold worked alloy 690TT in primary water[J].Corrosion Science,2012,57:81-88.
【5】HOU J,SHOJI T,LU Z P,et al.Residual strain measurement and grain boundary characterization in the hear-affected zone of a weld joint between alloy 690TT and alloy 52[J].Journal of Nuclear Materials,2010,397:109-115.
【6】SYMONS D M.Hydrogen embrittlement of Ni-Cr-Fe alloys[J].Metall Mater Trans A,1997,28(3):655-663.
【7】SYMONS D M.The effect of carbide precipitation on the hydrogen-enhanced fracture behavior of alloy 690[J].Metall Mater Trans A,1998,29(4):1265-1277.
【8】褚武扬,乔利杰,陈奇志,等.断裂与环境断裂[M].北京:科学出版社,2000:82-152.
【9】GERBERICH W W,STAUFFER D D.A coexistent view of hydrogen effects on mechanical behavior of crystals:HELP and HEDE[C]//Effects of Hydrogen on Materials Proc 2008 International Hydrogen Conference,[S.l]:[s.n],2009:38-45.
【10】QIAO L,MAO X.Thermodynamic analysis on the role of hydrogen in anodic stress corrosion cracking[J].Acta Metall Mater,1995,43(1):4001-4006.
【11】DAN T C,LU Z P,SHOJI T,et al.Effects of hydrogen on the anodic behavior of alloy 690 at 60 ℃[J].Corros Sci,2010,52(4):228-1236.
【12】SHOJI T,LU Z P,MURAKAMI H.Formulating stress corrosion cracking growth rates by combination of crack tip mechanics and crack tip oxidation kinetics[J].Corros Sci,2010,52(3):769-779.
【2】JEONG H S,JIN K S,SUK J L K,et al.Investigation of IGSCC behavior of sensitized and laser-surface-melted alloy 600[J].Materials Science and Engineering,1998,254:67-75.
【3】YANG W,LU Z P,HUANG D L.Caustic stress corrosion cracking of nickel-rich,chromium-bearing alloys[J].Corros Sci.,2001,43(5):963-977.
【4】PENG Q J,YONEZAWAT,SHOJI T,et al.Environ-mentally assisted crack growth in one-dimensionally cold worked alloy 690TT in primary water[J].Corrosion Science,2012,57:81-88.
【5】HOU J,SHOJI T,LU Z P,et al.Residual strain measurement and grain boundary characterization in the hear-affected zone of a weld joint between alloy 690TT and alloy 52[J].Journal of Nuclear Materials,2010,397:109-115.
【6】SYMONS D M.Hydrogen embrittlement of Ni-Cr-Fe alloys[J].Metall Mater Trans A,1997,28(3):655-663.
【7】SYMONS D M.The effect of carbide precipitation on the hydrogen-enhanced fracture behavior of alloy 690[J].Metall Mater Trans A,1998,29(4):1265-1277.
【8】褚武扬,乔利杰,陈奇志,等.断裂与环境断裂[M].北京:科学出版社,2000:82-152.
【9】GERBERICH W W,STAUFFER D D.A coexistent view of hydrogen effects on mechanical behavior of crystals:HELP and HEDE[C]//Effects of Hydrogen on Materials Proc 2008 International Hydrogen Conference,[S.l]:[s.n],2009:38-45.
【10】QIAO L,MAO X.Thermodynamic analysis on the role of hydrogen in anodic stress corrosion cracking[J].Acta Metall Mater,1995,43(1):4001-4006.
【11】DAN T C,LU Z P,SHOJI T,et al.Effects of hydrogen on the anodic behavior of alloy 690 at 60 ℃[J].Corros Sci,2010,52(4):228-1236.
【12】SHOJI T,LU Z P,MURAKAMI H.Formulating stress corrosion cracking growth rates by combination of crack tip mechanics and crack tip oxidation kinetics[J].Corros Sci,2010,52(3):769-779.
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