核电站安全壳锚具荷载传递性能试验研究

Experimental study on load transfer behaviors of anchorage device of nuclear power station containment vessel

针对核电站安全壳大吨位钢索张拉的结构安全性,用荷载传递性能试验的方法,研究了配置OVM15R-37K核电站安全壳专用锚垫板的预应力混凝土锚固区传力性能,包括极限荷载、应变值和裂缝宽度等,并进行了相关数据分析.试验和分析结果表明,试件的极限荷载均能达到1.2 Fpk;封闭网格钢筋的合理配置可提高试件开裂荷载并有效控制劈裂裂缝宽度;张拉过程中锚具本身的应力低于材料的屈服应力.

Against the safety of the tendon anchorage zones during the tensioning stage,large-tonnage tendon technology was adopted in nuclear power plants containment.With the method of load transfer performance,experimental study on OVM15R-37K-special bearing plate of containment vessel for nuclear power station were tested to investigate the load transfer behaviors of post-tensioned concrete anchorage zones,including ultimate loads,strain,crack width,while some relative parameters were studied.The results of test and analysis show that the ultimate loads of specimens can reach 1.2Fpk;the grid reinforced bar can improve the cracking load and substantially reduce the crack width;the stresses of anchorage devices are far below the yield limit of steel in the tensioning stage.The results of this experiment promote the application of domestic prestressed anchorage in nuclear power station.