广东台山核电站内安全壳穹顶施工阶段受力性能及稳定性分析  被引量:5

Construction phase mechanical performance and stability analysis of inner containment dome of the Taishan Reactor Building in Guangdong

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作  者:金晓飞[1] 李政 李景芳[1] 

机构地区:[1]中国建筑股份有限公司技术中心,北京101300 [2]中建二局核电建设分公司,广东深圳518034

出  处:《建筑结构学报》2014年第1期63-68,共6页Journal of Building Structures

摘  要:以广东台山核电站工程为研究背景,建立安全壳穹顶的复杂实体有限元分析模型,合理简化边界条件,以整体模型能量误差评估网格精度。该工程穹顶跨度近50 m、内衬6 mm厚的钢板。针对施工时变结构特点,考虑混凝土弹性模量随龄期变化的影响,采用重叠单元和生死单元技术,分析大跨度穹顶在混凝土浇筑成形整个施工过程中的结构变形和应力,并考虑初始几何缺陷和材料弹塑性的影响,分析施工关键阶段结构在新浇筑混凝土自质量及施工活荷载作用下的稳定承载力。结果表明:施工时变全过程分析结果与整体一次成型建模分析的结果差异显著,前者分析的结构最大挠度为3.2 mm,而后者分析的仅为1.2 mm;施工过程中结构稳定安全系数不小于3.4,满足要求。This paper takes the Taishan Nuclear Power Plant Project in Guangdong as the research background. The complicated entity finite element model was built with rational and simplified boundary conditions, and its mesh density was evaluated with the energy error over the model. The dome has a span of nearly 50 m with only 6 mm thick steel liner. The overlap element plus birth and death element technique was used according to the characteristics of time-varying structure in construction, and the effect of time-dependent elastic modulus of concrete was also taken into account ; the structural deformation and stresses of the large-span dome during continuous concreting construction were then analyzed. The structure stability bearing capacities at the critical stages of fresh concrete pouring construction were both analyzed which took into consideration the effect of initial geometrical imperfections and elasto-plastieity. The results show that the difference between the time-varying process analysis and the modeling analysis as a whole is significant, where the former structural deflection is 3.2 mm but the latter is 1.2 mm ; the stability safety factor is not less than 3.4 and meets relevant requirement.

关 键 词:核电站安全壳 时变施工力学 有限元分析 受力性能 稳定性 

分 类 号:TU398.904[建筑科学—结构工程]

 

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