反应堆压力容器承重支撑部位墙体受力分析及设计优化  

STRESS ANALYSIS AND DESIGN OPTIMIZATION OF THE WALL AT SUPPORT POSITION OF REACTOR PRESSURE VESSEL

作　　者：何志坚 陈岩 庄艺斌 张君鸿 李潇南 涂健 HE Zhijian;CHEN Yan;ZHUANG Yibin;ZHANG Junhong;LI Xiaonan;TU Jian(Chinergy Co.,Ltd.,Beijing 100193,China)

机构地区：[1]中核能源科技有限公司,北京100193

出　　处：《工业建筑》2021年第12期49-55,共7页Industrial Construction

基　　金：国家科技重大专项项目(2018ZX06902016)。

摘　　要：反应堆压力容器承重支撑是核电厂结构设计的关键部位,以华能山东石岛湾高温堆示范工程反应堆压力容器承重支撑附近墙体为研究对象,根据局部承压理论机理,结合压力容器承重支撑区域墙体混凝土受力特点,采用混凝土多轴强度准则,对承重支撑的侧框架、下框架以及螺栓群作用区在复合应力状态下的局部混凝土进行受力分析。根据有限元弹性和弹塑性计算结果及构造分析,发现原设计方案存在的不足并提出优化建议。按优化后的设计方案对该处墙体的承载力以及施工可行性进行了重新分析论证,方案优化后的计算结果与试验结果符合较好。该区域墙体分析结果能满足现行国家规范标准的要求,其中大部分研究成果被示范工程所采纳。The support of reactor pressure vessel is the key part in the structural design of nuclear power plant. The wall at support position of reactor pressure vessel of Huaneng Shandong Shidaowan high temperature reactor demonstration project was taken as the research object. According to the theory of local pressure, combined with the concrete stress characteristics of the wall at support position of reactor pressure vessel, the multiaxial strength criterion of concrete was used to analyze the local concrete stress of the side frame, the lower frame and the bolt group in the composite stress state. According to the finite element elastic and elastic-plastic calculation results and the structural analysis, the shortcomings of the original design scheme were found and the optimization suggestions were put forward. According to the optimized design scheme, the bearing capacity and construction feasibility of the wall were analyzed and demonstrated again to ensure that the area met the requirements of the current national standards. Most of the research results in the paper were adopted by the demonstration project.

关 键 词：局部承压 多轴强度 第三主应力 

分 类 号：TM623[电气工程—电力系统及自动化]