摘要
为了解决高温气冷堆示范工程(HTR-PM)无测量杆螺柱预紧力的控制问题,保证反应堆一回路压力边界的法兰密封,需要对无测量杆螺柱的预紧力进行标定。以HTR-PM中M56无测量杆螺柱为例,采用液压拉伸机对其进行标定试验,找到螺栓拉伸机拉伸预紧力与螺柱残余预紧力的关系曲线;分析了螺栓拉伸机拉伸前后导致螺柱残余预紧力下降的原因,再通过材料力学本构关系,建立了螺栓拉伸机拉紧力与螺柱回弹后残余预紧力的理论关系式。结果表明,试验获得的螺柱联接体系中的残余预紧力及螺母旋紧前的预紧力关系式都与理论分析比较接近;螺栓拉伸机相同出力下,实际设备管嘴法兰螺柱的残余预紧力会比标定值大,但这更有利于法兰面的密封。
In order to control the final pre-tightening force of the stud without measuring rod in the high temperature gas cooled reactor Pebble Module(HTR-PM)and ensure the sealing of the reactor primary circuit pressure boundary,it is necessary to calibrate the pre-tightening force of the stud.Taking the M56 stud without measuring rod as an example,the calibration test was carried out with a bolt tensioner,and the relation curve between the pre-tightening force and the final pre-tightening force of the stud was found.The final pre-tightening force on the stud was smaller than the pre-tightening force of the bolt tensioner when the nut was tightened.The reason of the force decreasing was analyzed.The relation formula between the pre-tightening force and the final pre-tightening force of the stud was established through the constitutive relation theory of material mechanics.It was shown that the final pre-tightening force and its relation between the pre-tightening force obtained from the test were close to the theoretical analysis results.Under the same output force of the bolt tensioner,the final pre-tightening force of the actual equipment nozzle flange studs will be larger than the calibrated value,but this is good for the sealing.
作者
金东杰
汪垠
金刚
耿宝杰
郭云龙
Jin Dongjie;Wang Yin;Jin Gang;Geng Baoji;Guo Yunlong(Chinergy Co.,Ltd.,Beijing,100193,China;Nuclear and Radiation Safety Center,Ministry of Ecology and Environment,Beijing,102445,China;Huaneng Shandong Shidao Bay Nuclear Power Co.,Ltd.,Shandong,264312,China)
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2020年第6期167-171,共5页
Nuclear Power Engineering
基金
大型先进压水堆及高温气冷堆核电站国家重大专项(2008ZX06905-002)。
关键词
螺栓拉伸机
预紧力
高温气冷堆
回弹量
Bolt tensioner
Pre-tightening force
High temperature gas-cooled reactor
Pre-tightening force reduction
作者简介
金东杰(1981-),男,高级工程师,主要从事核电站非标设备研究,E-mail:jindj1922@163.com;通讯作者:金刚,E-mail:jingang@chinansc.cn。
