非对称预紧载荷下核反应承压容器密封性能分析方法研究

Sealing Behavior Analysis Method of Reactor Pressure Vessel under Asymmetric Preload

针对某核反应承压容器主螺栓孔损伤,分别建立了3螺栓和180°两种三维有限元模型,对非对称预紧载荷下核反应承压容器密封性能分析方法进行了研究,得到了该两种模型下表征密封性的主要指标,包括竖直方向张开位移、水平方向滑动位移、主螺栓受力等。分析结果表明,两种模型均能较为准确地反映该核反应承压容器密封结构的性能,评价了非对称预紧载荷下密封结构的可靠性,为解决主螺栓孔损伤情况下的密封问题提供了计算依据。

For the reactor pressure vessel（RPV） threaded hole damage analysis of sealing performance, a finite element model containing three bolts and surrounding structure was built, compared with which was a 180 degree model. Based on the models, the sealing performance under the asymmetric preload was studied. The key indicators are deduced, include vertical displacement, horizontal displacement, bolt loads, etc. It shows that both models can verify the performance of the seal structure, which used to evalu- ate the reliability of the RPV sealing structure, and is the basis to solve the sealing problem of main bolt damage cases.