The high-temperature gas-cooled reactor pebble-bed module project is the first commercial Generation-IV NPP(Nuclear Power Plant) in China. A new joint is used for the vertical support of RPV(Reactor Pressure Vessel). The steel corbel is integrally embedded into the reactor-cabin wall through eight asymmetrically arranged pre-stressed high-strength bolts, achieving the different path transmission of shear force and moment. The vertical monotonic loading test of two specimens is conducted. The results show that the failure mode of the joint is bolt fracture. There is no prominent yield stage in the whole loading process. The stress of bolts is linearly distributed along the height of corbel at initial loading. As the load increases, the height of neutral axis of bolts gradually decreases. The upper and lower edges of the wall opening contact the corbel plate to restrict the rotation of the corbel. During the loading, the pre-stress of some bolts decreases. The increase of the pre-stress strength ratio of bolts has no noticeable effect on the structure stiffness, but it reduces the ultimate bearing capacity of the joint. A simplified calculation model for the elastic stage of the joint is established, and the estimation results are in good agreement with the experimental results.

高温气冷堆球床模块项目是我国第一座商用第四代核电站。RPV（反应堆压力容器）的垂直支撑使用了一种新的接头。钢梁通过8个非对称布置的预应力高强度螺栓整体嵌入反应堆舱壁，实现剪力和力矩的不同路径传递。对两个试件进行垂直单调加载试验。结果表明，接头的失效模式为螺栓断裂。整个加载过程中没有突出的屈服阶段。在初始加载时，螺栓的应力沿牛腿高度呈线性分布。随着载荷的增加，螺栓中性轴的高度逐渐减小。墙壁开口的上下边缘与牛腿板接触，以限制牛腿的转动。在加载过程中，一些螺栓的预应力减小。螺栓预应力强度比的增加对结构刚度没有明显影响，但会降低节点的极限承载力。建立了节点弹性阶段的简化计算模型，估计结果与试验结果吻合较好。