Small break loss of coolant accident (SBLOCA) of a nuclear power plant reactor primary system is simulated at the high pressure integral test facility (HPITF). The break is loca ted at the bottom of the horizontal cold leg and its area is 1% (NSB 7 case).

• 在高压综合实验装置（HPITF）上进行核电厂反应堆一次系统冷管段小破口失水事故（SBLO－CA）模拟实验，破口方向为冷管段底部，破口面积为1%25（NSB－7工况）。