核电厂主设备在地震加失水事故下的结构反应分析研究

Structural Response Research for Primary Components under Earthquake and LOCA Accidents on NPP

核电厂主设备是核电厂的关键设备。对反应堆堆内构件、控制棒驱动系统、燃料组件和蒸汽发生器传热管等设备进行地震加失水事故联合作用下详细的动力分析与评定,是核电厂设计规范和安全审查的要求。 上海核工程研究设计院在主设备的地震加失水事故下反应分析和试验研究的基础上,将主设备作为一个总体进行分析,从而形成一个完整的分析和评定系统。该研究成果已应用于秦山、PC两座核电厂的设计分析和安全评审中,对我国自主开展百万级先进压水堆核电厂主设备在地震加失水事故下的设计和安全分析具有良好的推广和应用前景。

The primary components are key components of nuclear power plants. The detail dynamic analysis and evaluation for the reactor internals, control rod drive system, fuel assemblies and the steam generator tubes, under combined application of the earthquake and LOCA loads, are the requirements of design codes and safety review. Taking the primary components as integrity carry out research, so as to form a complete analysis and evaluation system, based on response analyses and tests of the primary components under the earthquake and LOCA accidents of Shanghai Nuclear Engineering Rsearch & Design Institute. The research results have applied on the design analysis and safety review for Qinshan and PC NPP, and also having glorious expectation for the design and safety analysis of the primary components under the earthquake and LOCA accidents on the domestic self-developed 1000 MW advanced PWR.