“华龙一号”核电安全壳结构整体性试验变位测试分析

DISPLACEMENT ANALYSIS FOR STRUCTURAL INTEGRITY TEST OF CONTAINMENT OF HPR1000 NUCLEAR POWER PLANT

以全球首堆福建福清核电站5号机组和海外首推巴基斯坦卡拉奇核电K2机组“华龙一号”核电为研究对象,首先基于ABAQUS有限元模型对“华龙一号”堆型核电安全壳结构进行了整体性试验及理论分析,研究了安全壳结构在LOCA事故下的破坏过程,明确了安全壳的薄弱环节;参照NB/T 20017—2010《压水堆核电厂安全壳结构整体性试验》对SIT试验变位测试数据进行分析,并依据试验过程及结果对上述标准提出合理化建议。结果表明,福建福清核电站5号机组和巴基斯坦卡拉奇核电K2机组的试验参数随试验压力变化趋势一致;试验结果与理论分析吻合,两台机组变位测试结果均满足NB/T 20017—2010标准设计要求。建议在NB/T 20017—2010中补充径向变形测量中增加筒体在预计最大水平直径变形处和竖向变形处的测点布置数量,增加设备闸门口附近测点和数据采集频次。

This paper took the world’s first HPR1000 nuclear power plant(NPP) of Fuqing 5 unit and Pakistan K2 unit in Karachi as the research object. Firstly, based on the ABAQUS finite element model, the overall test and theoretical analysis of containment structure of the HPR1000 NPP were carried out, the damage process of the containment structure under the LOCA accident was studied, and the weak links of the containment were clarified. According to NB/T 20017—2010 “Structural Integrity Test of Containments of Pressurized Water Reactor Nuclear Power Plants”, the displacement test data of SIT test was analyzed, and the rationalization suggestions for the above standards were proposed according to the test process and results. The results showed that the test parameters of Fuqing 5 unit and Karachi K2 unit of NPP had the same trend with the test pressure;the test results were consistent with the theoretical analysis, and the displacement test results of the two units both met the standard design requirements of NB/T 20017—2010. It was suggested to increase the number of measuring points at the expected maximum horizontal diameter deformation and vertical deformation of the cylinder in the supplementary radial deformation measurement in NB/T 20017—2010, and increase the frequency of measuring points and data collection near the gate of the equipment.