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作 者:Yusheng Zhang Jiang Lai Hongliang Ming Lixia Gao Jianqiu Wang En-Hou Han
机构地区:[1]School of Materials Science and Engineering,University of Science and Technology of China,Shenyang,110016,China [2]CAS Key Laboratory of Nuclear Materials and Safety Assessment,Institute of Metal Research,Chinese Academy of Sciences,Shenyang,110016,China [3]Nuclear Power Institute of China,Chengdu,610213,China
出 处:《Acta Metallurgica Sinica(English Letters)》2023年第5期865-880,共16页金属学报(英文版)
基 金:supported by the CNNC Science Fund for Talented Young Scholars,Youth Innovation Promotion Assessment CAS(2022187);the IMR Innovation Fund(No.2021-PY10);the open-ended fund of the CAS Key laboratory of Nuclear Materials and Safety Assessment(Institute of Metal Research,Chinese Academy of Sciences,China)(No.2020NMSAKF01).
摘 要:The effect of normal force on fretting wear behavior of zirconium alloy tube mated with grid dimple in simulated primary water of pressurized water reactor nuclear power plant was investigated.Results showed that the maximum wear depth,wear volume and wear coefficient of Zr alloy tube in simulated primary water at 315℃ gradually increased with increasing normal force,while the friction coefficient gradually decreased.Fretting process could be divided into four stages according to the variation of friction coefficient during test.When normal force exceeds 30 N,the fretting regime would transition from gross slip regime to partial slip regime after 3×10^(7 )cycles.Delamination was aggravated with increasing normal force,while abrasive wear became slighter.A thicker third-body layer with monoclinic ZrO_(2) was formed by the tribo-sintering mechanism under higher normal force.In addition,the schematic evolution processes of delamination and third-body layer formation were displayed according to morphology observation.
关 键 词:Zirconium alloy tube Fretting wear Grid-to-rod High-temperature pressurized water Normal force
分 类 号:TM623[电气工程—电力系统及自动化]
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