压水堆主管道双端断裂事故下管路系统的力和力矩分析

FORCE AND MOMENT ANALYSIS OF PIPE SYSTEM FOR A DOUBLE END BREAK LOSS OF COOLANT ACCIDENT(LOCA)IN PRIMARY LOOP OF PWR

文章引入了国外采用的经验数据和公式，分析了其缺陷性，并从流体瞬变和流体力学理论出发对压水堆主管道双端断裂进行了分析和研究。先用特征线法求得回路系统在失水事故工况下的压力、流量变化曲线，再用控制体体积积分方法较为精确地计算出主管道的１１个断点分别断裂时，其他各点的受力和力矩。

LOCA in the primary loop system of the pressurized water reactor is a serious accident.The loss of the accident is due to the situation and size of break point.Meanwhile,because of its complicacy,many of the research works are based on experience data and empirical formula.In the paper, LOCA in primary loop,especially about the double end break accident, is rearched and analyzed based on the theory and methods of fluid mechanics.The pressure and flow of loop system under LOCA are obtained using characteristic line method. Based on the above results,the force and moment of pipe system can be accuratly gotten by control volume intergrating method.All these resuls are very important for nuclear safety design and analysis of the PWR plant.