font-family:宋体,Helvetica,sans-serif" font-family:宋体,Helvetica,sans-serif"微机瞬态分析仪(PCTRAN)已被用于数值生成类似事故条件下的电站安全系统响应数据。已经考虑在蒸汽管线的A回路中中断1000cm 2。这种大小的断裂被认为是大断裂,这被认为是过去多次严重事故的原因。此外,还假定场外交流电源不可用。模拟的持续时间为300秒,因为核电站的大多数安全功能应该在事故发生后50秒内做出反应。结果表明,SCRAM在断口出现后的22.5秒内启动,将核心热功率峰值限制在标称值的105%左右。燃料元件和燃料包壳的峰值温度分别在1850oC和620oC左右,均在安全范围内。反应堆压力容器内部压力没有发生重大变化,没有出现故障迹象。同样,安全系统将反应堆安全壳建筑内的压力控制在2.5 bar以内,这表明不存在因超压而导致安全壳失效的可能性。 Finally, the readings from radiation monitor show that there is no noticeable release of radioactive elements to the environment during the accident. Therefore, it may be concluded that the release of radioactive elements in the surrounding environment during a steam-line break accident is very unlikely provided that the plant safety systems are fully functional.