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作 者:杨思远 袁波 文青龙[1,2,3] 文爽 张瑞谦 杨红艳[4] Yang Siyuan;Yuan Bo;Wen Qinglong;Wen Shuang;Zhang Ruiqian;Yang Hongyan(School of Energy and Power Engineering,Chongqing University,Chongqing,400044,China;Key Laboratory of Low-grade Energy Utilization Technologies and Systems,Ministry of Education,Chongqing University,Chongqing,400044,China;Liangjiang Laboratory for New Energy(Nuclear Energy and Power),Chongqing,400044,China;Nuclear Power Institute of China,Chengdu,610213,China)
机构地区:[1]重庆大学能源与动力工程学院,重庆400044 [2]重庆大学低品位能源利用技术及系统教育部重点实验室,重庆400044 [3]两江新能源(核能与动力)实验室,重庆400044 [4]中国核动力研究设计院,成都610213
出 处:《核动力工程》2024年第S01期103-109,共7页Nuclear Power Engineering
基 金:国家自然科学基金(52201091)。
摘 要:为研究压水堆湍流激振条件下Cr涂层锆包壳微动磨损的机理和微观作用机制,本文主要以Cr涂层锆包壳为研究对象,开展了多参数耦合下的微动磨损实验研究,阐明了频率、载荷、位移以及循环次数等参数对微动磨损的影响规律。研究获得了19组微动磨损实验后的最大磨损深度与磨损体积,其中最大磨损深度为12.052μm,最大磨损体积为3.301×10^(-3) mm^(3)。研究结果表明,微动磨损的主要影响参数包括微动幅度、法向载荷、循环次数和材料硬度,而微动频率对磨损体积和最大磨损深度影响较小。通过最小二乘法拟合实验数据得到了磨损体积计算关系式,其中有68%的实验值和关系式计算值的偏差在±50%以内。本研究对Cr涂层锆包壳耐磨性能评价提供了数据支撑。To study the mechanism and microscopic mechanism of fretting wear of Cr-coated zircaloy cladding under the condition of turbulent excitation of PWR,this paper mainly takes Cr-coated zircaloy cladding as the research object,carries out experimental research on fretting wear under multi-parameter coupling,and expounds the influence laws of parameters such as frequency,load,displacement and cycle times on fretting wear.The maximum wear depth and wear volume of 19 sets of fretting wear experiments were obtained,of which the maximum wear depth was 12.052μm and the maximum wear volume was 3.301×10^(−3) mm^(3).The results show that the main influencing parameters of fretting wear include fretting amplitude,normal load,cycle times and material hardness,while fretting frequency has little influence on wear volume and maximum wear depth.The least square method is used to fit the experimental results to obtain the wear volume calculation formula,and the deviation between the experimental value and the calculated value of the formula is within±50%.This study provides data support for the evaluation of wear resistance of Cr-coated zircaloy cladding.
分 类 号:TL341[核科学技术—核技术及应用]
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