首页 | 本学科首页   官方微博 | 高级检索  
     

反应堆压力容器主螺栓水压试验拉伸量调整力学分析评价
引用本文:陈涛,聂照宇,胡大芬,徐晓. 反应堆压力容器主螺栓水压试验拉伸量调整力学分析评价[J]. 装备环境工程, 2019, 16(2): 7-11
作者姓名:陈涛  聂照宇  胡大芬  徐晓
作者单位:核电安全监控技术与装备国家重点实验室,广东 深圳 518172;深圳中广核工程设计有限公司,广东 深圳 518172;深圳中广核工程设计有限公司,广东 深圳,518172
摘    要:目的针对某核电站反应堆压力容器主螺栓残余拉伸量与设计要求(1.63±0.03) mm有出入,个别测试数据不在设计要求范围内的情况,对出厂水压试验工况拉伸量验收值进行调整。方法考虑上述拉伸量偏差对螺栓载荷的影响,从应力、疲劳和密封角度展开系统分析,对螺栓、螺纹、连接法兰及反应堆压力容器密封性能分别进行详细的力学评价。结果根据评价结果,对出厂水压试验工况拉伸量验收值进行两次调整,最终确定为(1.68±0.03) mm。结论该机组反应堆压力容器出厂水压试验各项指标满足要求,针对上述拉伸量调整的力学评价合理性得到有效验证。

关 键 词:力学分析  螺栓  拉伸量  水压试验  核电站
收稿时间:2018-11-23
修稿时间:2019-02-25

Study on the Adjustment of Reactor Pressure Vessel Main Bolt Residual Elongation during Individual Hydraulic Test
CHEN Tao,NIE Zhao-yu,HU Da-fen and XU Xiao. Study on the Adjustment of Reactor Pressure Vessel Main Bolt Residual Elongation during Individual Hydraulic Test[J]. Equipment Environmental Engineering, 2019, 16(2): 7-11
Authors:CHEN Tao  NIE Zhao-yu  HU Da-fen  XU Xiao
Affiliation:1. State Key Laboratory of Nuclear Power Safety Monitoring Technology and Equipment, Shenzhen, 518172 China;2. China Nuclear Power Design Company, Ltd, Shenzhen 518172, China,2. China Nuclear Power Design Company, Ltd, Shenzhen 518172, China,2. China Nuclear Power Design Company, Ltd, Shenzhen 518172, China and 2. China Nuclear Power Design Company, Ltd, Shenzhen 518172, China
Abstract:Objective To adjust the acceptance value of residual elongation in the working condition of hydrostatic test to solve the problem that the values of residual elongation of reactor pressure vessel (RPV) main bolt during calibration experiment for individual hydraulic test condition are not consistent with the design requirement which is 1.63±0.03mm and some values are beyond the requirement range. Methods Considering the influence of the above difference on the bolt load, detailed analyses were carried out for the bolt, the bolt threads and connected flanges in the field of stress, fatigue and sealing of RPV. Results After two times of adjustment, new elongation values of 1.68±0.03mm were determined according to the analysis results. Conclusion Each testing index of the individual hydraulic test for the certain RPV satisfies the demand and the rationality of the numerical assessment is verified.
Keywords:mechanics analysis   bolt   elongation   hydraulic test   nuclear power station
本文献已被 CNKI 万方数据 等数据库收录!
点击此处可从《装备环境工程》浏览原始摘要信息
点击此处可从《装备环境工程》下载免费的PDF全文
设为首页 | 免责声明 | 关于勤云 | 加入收藏

Copyright©北京勤云科技发展有限公司  京ICP备09084417号