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Lumped parameter method application in nuclear engineering - AP1000 DVI line break accident analysis by RELAP5

机译:集总参数方法在核工程中的应用-RELAP5分析AP1000 DVI断线事故

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Based on the PWR best estimate program RELAP5/MOD3.3, the reactor coolant system and the passive core cooling system of AP1000 Nuclear Power Plant were modeled and analyzed. Some key transient parameters were obtained, including RCS pressure, break discharge, etc. The result is in close agreement with the result generated by NOTRUMP code from West-inghouse (USA). The calculation results show that safeguard system of AP1000 can effectively reduce the pressure of the first loop, also can prevent core uncovered. The safety of API000 during a small break Loss of Coolant Accident caused by DVI line breaking is verified.
机译:基于压水堆最佳估算程序RELAP5 / MOD3.3,对AP1000核电站的反应堆冷却剂系统和被动堆芯冷却系统进行了建模和分析。获得了一些关键的瞬态参数,包括RCS压力,中断排放等。结果与美国West-inghouse的NOTRUMP代码产生的结果非常一致。计算结果表明,AP1000的保障系统可以有效降低一回路压力,还可以防止岩心裸露。验证了由DVI断线引起的短暂中断期间冷却液损失事故中API000的安全性。

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