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总结了用1:1钢质人孔模型容器对国产不锈钢膨胀石墨缠绕密封垫,在冷态力学性能试验的基础上置于大型热态试验台架回路中、以核岛主设备的实际运行工况和稍苛刻的参数,进行热态循环试验研究的结果。研究了其相当于启堆升温升压、正常运行和停堆降温全过程中螺栓力、人孔盖和人孔座法兰的转角、分离量的变化及其密封性。并模拟了其中一根螺栓断掉后对周围螺栓和总螺栓力及密封的影响。试验了该类型国产垫中杂质硫对回路水质的影响,分析了国产不锈钢石墨缠绕垫应用于核设备人孔密封结构中的可靠性。
In this paper, the domestic stainless steel expanded graphite winding gaskets with 1: 1 steel manhole model container are summarized. On the basis of the cold mechanical properties test, they are placed in the large hot test bench circuit. With the actual operation of the nuclear island main equipment Conditions and slightly harsh parameters, the results of thermal cycling test. The change of the angle and the separation of the bolt force, the manhole cover and the manhole seat flange in the whole process of opening, heating and pressurizing, normal operation and cooling shutdown were studied and their sealing performance was also studied. And simulates the impact of one of the bolts on the surrounding bolt and the total bolt force and seal after it is broken. The influence of impurity sulfur in the domestic pad on the water quality of the circuit was tested. The reliability of the domestic stainless steel graphite spiral wound pad used in the manhole sealing structure of nuclear equipment was analyzed.