The naturalcirculation ability of PWR (pressurized water reactor) coolant system is one of inherent safeties of this kind NPP (nuclear power plant).
压水堆核电厂反应堆冷却剂系统自然循环能力是这种类型核电厂固有的安全性之一。
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The results show that heaving has less effect upon the primary Loop's coolant flow rate and PWR output power in case of forced circulation but strongly influences natural circulation ability.