natural coolant circulation

基本解釋

The natural circulation ability of PWR (pressurized water reactor) coolant system is one of inherent safeties of this kind NPP (nuclear power plant).
壓水堆核電廠反應堆冷卻劑系統(tǒng)自然循環(huán)能力是這種類型核電廠固有的安全性之一。
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.
結果表明：起伏對強制循環(huán)下一廻路冷卻劑的流量和反應堆輸出功率的影響較小，而對自然循環(huán)能力的影響很大。