某EPR核电站安全壳预应力摩擦损失的试验研究

Experimental Studies on Friction Loss of Prestress of Containment Vessel in an EPR Nuclear Power Plant

本文以欧洲提出的第三代原子能反应堆(Evolutionary power reactors,简称EPR)核电站安全壳为工程背景,对预应力筋系统中水平预应力筋、竖向预应力筋和穿过穹顶的预应力筋的预应力摩擦损失进行一系列的现场试验研究。研究结果表明,水平预应力筋、竖向预应力筋和穿过穹顶的预应力筋的平均摩擦系数分别为0.1016、0.0614和0.0744,而其设计值分别为0.1000、0.0600和0.0750,其偏差分别为+2%、+2%和-1%。经摩擦系数调整后,预应力筋伸长量偏差均符合要求,为核电站安全壳的结构设计与工程应用提供了理论依据。

In this study,a containment vessel of the nuclear power plant with the evolutionary power reactors(EPR) was taken as the engineering background.A series of field tests were conducted to study the friction loss of the horizontal prestressed tendons,vertical prestressed tendons,and prestressed tendons passing through the dome in the prestressed tendon system.The results showed that the average friction coefficients of horizontal prestressed tendons,vertical prestressed tendons,and prestressed tendons passing through the dome were 0.1016,0.0614and 0.0744 respectively;and their design values were 0.1000,0.0600 and 0.0750 respectively.Consequently,their deviations were+2%,+2%,and-1%,respectively.After the adjustment of the friction coefficient,the elongation deviations of the prestressed tendons meeted the requirements.Thus,it could provide the theoretical basis for the structural design and engineering application of the nuclear power plant containment vessel.