核电站安全壳人员闸门应力分析--结构改进及其规律

Stress Analysis of Personnel Airlock on Containment Vessel of Nuclear Power Plant——Structure Improvement and its Reasons

安全壳是核电站防止放射性物质外泄的重要屏障,也是最后一道屏障。本文对某在建核电站安全壳重要贯穿件人员闸门进行了在自重、压力载荷下的静态分析、模态分析、地震载荷下的分析和屈曲分析。事故工况下温度载荷对设备的影响采用了简化弹塑性分析的方法。对设备在各使用限制条件下的应力进行了载荷组合与评定,结果显示,设备原设计无法承受核电站严重事故下的压力载荷。为此,作者提出了结构修改方案及其受力规律。经改进的结构的应力分析和评定结果表明,修改设计后的人员闸门满足ASME B&PVC第Ⅲ卷的规范要求。论文也指出了原设计不满足ASME规范的结构方面的原因和历史、法规方面的原因,得到了安全壳贯穿件设备设计需关注的力学问题。

Containment vessel is the important and last barrier of radioactivity leakage in Nuclear Power Plant（NPP）. Static analysis under dead weight and pressure, modal analysis, seismic analysis, and buckling analysis for personnel airlock in an abuilding NPP were performed. The simplified elastic-plastic analysis was used for the thermal expansion loading. The stress combination and evaluation were performed. Some mechanics problems on original design were found and the improvement measures were proposed. The improved equipment meets ASME B＆PVC Ⅲ. Some reasons about structure, history and standard were indicated. The mechanics problems on containment penetrations design needed to be paid attention especially were summarized.