摘要:
核电站反应堆筏板基础为大体积钢筋混凝土,面积大、厚度高、混凝土强度等级高、水泥用量大、施工期间绝热温升高,如何在施工期间采取措施避免裂缝出现、有效进行裂缝控制是反应堆筏板基础施工的重中之重。施工期间混凝土内部应力主要为温度、水化收缩及约束产生的综合应力。温度应力公式显示温度场主要沿着半径方向变化,最大温度应力处总是位于筏板边缘环向,与温度值、半径无关,而试验数据显示收缩应力为中心位置受拉、边缘位置受压,与温度应力相反。在此基础上,提出了"动态养护法"裂缝控制技术,通过不断改变表面覆盖层的保温措施来改变温度分布,进而用温度变形中和抵消收缩变形,再以弹性变形装置监测总变形,依据第三破坏准则来控制裂缝,控制内部总应力在一定范围内。动态养护的裂缝控制方法安全、有效、经济、便捷,目前已在数十个核电基础施工中得到成功应用,大大缩短了基础施工时间。
Abstract:
The mass reinforced concrete in the raft foundation of nuclear power plant reactors has the characteristics of large area, large thickness, high strength, large cement dosage, and increased adiabatic temperature during construction, so the measures to prevent and control cracks are the top priorities. The internal stress is mainly the comprehensive stress caused by temperatures, hydration shrinkage and its constraints during construction. The temperature stress formula shows that the temperature field mainly varies along the radial direction, maximum temperature stress is horizontally hooped at the raft edge, independent of the temperature values and radius. Experimental data showed that the shrinkage stress was tensioned at the center and compressed at the edges, as opposed to the temperature stress. Based on this, the dynamic curing method was proposed, the temperature distribution was changed by continuously changing the insulation measures of the surface covering, and then the temperature deformation was used to neutralize the shrinkage deformation, the total deformation was tested by the elastic deformation device, and the cracks were controlled according to the third failure criterion, thus, and the total internal stress was controlled within a certain range. The crack control method is safe, economical, effective and low investment, and has been successfully applied in dozens of nuclear power foundation construction, which greatly shortens the foundation construction time.