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作 者:齐欢欢[1] 冯志鹏[1] 吴万军[1] 姜乃斌[1] 黄旋[1] Qi Huanhuan Feng Zhipeng Wu Wanjun Jiang Naibin Huang Xuan(Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China)
机构地区:[1]中国核动力研究设计院核反应堆系统设计技术重点实验室,成都610213
出 处:《核动力工程》2017年第5期54-57,共4页Nuclear Power Engineering
基 金:中国核动力院核反应堆系统设计技术重点实验室运行基金(ZDSY-ZSYX-14-12-001)
摘 要:采用Archard磨损公式作为压水堆燃料棒包壳的磨损理论模型,预测燃料棒包壳与格架之间的微振磨损,其中关键的物理量是磨损系数、燃料棒与格架之间的接触力以及滑动距离。磨损系数一般通过试验确定。随着燃耗加深,燃料棒与格架之间的接触力是时变函数,燃料棒夹持力随燃耗的变化曲线可采用试验或经验公式确定。由格架刚凸的刚度、包壳与格架的接触力以及它们之间的摩擦系数确定滑动阈值,将最大湍流激励的振动响应与滑动阈值进行比较,确定燃料棒包壳相对于格架是否存在滑动,计算燃料棒包壳在微小时间间隔内的滑移距离。几个物理量确定后,对磨损公式时间积分得到燃料棒包壳的微振磨损量。根据圆柱和表面的磨损几何关系,理论推导磨损量与磨损深度的关系,确定磨损深度,将磨损深度与相关准则进行比较,评估燃料棒包壳是否满足机械完整性的要求。Archard wear formula was used as the theoretical model for fretting wear of PWR fuel rod cladding, and the fretting wear volume between fuel rod cladding and grid would be predicted through this formula, where the significant physical quantities were wear coefficient, contact force between fuel rod and grid, and sliding distance. Wear coefficient was determined by experiment. Contact force between fuel rod and grid was a function varied with assembly burnup, which was determined by experiment or engineering empirical formula. The maximum vibration displacement for all modes would produce relative sliding if the displacement exceeded the threshold which was defined by grid dimple stiffness, contact force between fuel rod and grid, and friction between them, and the sliding distance could be estimated in an infinitesimal time increment. After the three physical quantities were determined, wear formula integral was implemented to obtain the fretting wear volume. According to the wear geometry of cylinder-plane contact, the relationship between wear volume and depth was derived theoretically, then the wear depth could be obtained from the wear volume. Finally comparing the wear depth to the criterion, it was validated that whether the fuel rod could satisfy the requirement on mechanism integrality.
分 类 号:TL352[核科学技术—核技术及应用]
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