反应堆顶盖跌落核岛厂房结构完整性分析

Integrity Analysis of Reactor Pit and Containment under Steam Explosion

压力容器顶盖跌落为核电厂灾害防护设计中重点关注部分,本文旨在分析此跌落对核岛厂房混凝土构件的影响。首先针对某三代核电厂反应堆厂房建立有限元模型,以重物跌落试验分析方法为基础,采用数值仿真方法分析压力容器顶盖跌落对反应堆水池混凝土构件与顶盖存放间楼板的动力响应以及破坏形态。根据研究结果,反应堆水池底板具备承受顶盖跌落撞击的能力,底板严重破坏,但底下的堆坑混凝土结构完好;而顶盖存放间底板在跌落作用下破坏不明显,可确保下方设备完好,结果表示吊运路径安全可靠,满足灾害防护要求。

Reactor Pressure Vessel Head(RPVH) Drop is required to evaluate in nuclear power plant as a part of internal hazard protection design.This paper aims to numerically analyze the RPVH drop impact on steel concrete in Reactor Building.The finite element model of a thirdgeneration nuclear power plant if firstly established.Based on the previous conducted 1/3 scaled free drop test of spent fuel cask,the adopted numerical algorithms,constitutive models and parameters are verified and further applied to the refined numerical simulations of Reactor Building,including the RPVH drop onto the bottom slab of Reactor Cavity Pool and bottom slab of RPVH storage compartment.According to the research results,RPVH drop induces extensive damage of Reactor Cavity Pool,but the steel bars can still keep a certain load-carrying capacity,and the overall civil structure can be still maintained.The bottom slab of RPVH storage compartment is not significantly damaged,indicating that the equipment below is effectively protected.The numerical result indicates the reliability of lifting path and meets the design requirements.