Based on the PWR best-estimate program RELAP5/MOD3.4,the reactor coolant system and the passive core cooling system of AP1000 were modeled and analyzed. Some key transient parameters were obtained,including RCS pressure,break discharge,cladding temperature,etc.
基于压水堆最佳估算程序RELAP5/MOD3.4,对AP1000的冷却剂系统和非能动堆芯冷却系统进行建模分析,得到了系统压力、破口流量、燃料包壳温度等关键参数的瞬态变化,计算结果与西屋公司采用NOTRUMP程序计算的结果基本一致。
参考来源 - AP1000冷管段小破口失水事故分析·2,447,543篇论文数据，部分数据来源于NoteExpress
应急堆芯冷却系统是核电站工程安全设施的一个组成部分。
The emergency core cooling system is a component part of engineered safety feature of a nuclear power plant.
除了上充功能，应急堆芯冷却系统运行时，离心上充泵用作高压安注的一部分。
In addition to the charging function, the centrifugal pumps also serve as the high head safety injection pumps during emergency core cooling system operation.
科学家们警告说紧急冷却系统可能失灵，核反应堆的堆芯熔毁可能会发生。
Scientists warned that emergency cooling systems could fail and a reactor meltdown could occur.
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