本文对完全自然循环压水堆装置的稳态和动态特性进行了分析。
This Paper Presents analysis of the stationary and transient behaviours of natural circulation PWR.
从它自身的特殊性出发，得出自然循环压水堆的稳定性不如强迫循环压水堆好的初步结论。
Considering its inherent characteristics, we can come to the preliminary conclusion that the steady feature of natural circulation PWR is not better than those of forced circulation PWR.
该模型可用于分析压水堆核电厂U型管自然循环式蒸汽发生器的热工水力瞬态过程。
This model can be used to analyze thermal-hydraulic transient behaviour of inverted U-tube steam generators in PWR power plants.
通过试验验证了VVER-1000型压水堆在发生全厂失电的情况下，依靠其固有特性，可以建立起自然循环。
Through test , It has confirmed that will development natural circulation in case of blackout in VVER-1000 type nuclear power station , depend on itself intrinsic attributes.
分析了喷射泵在压水堆一回路自然循环过渡过程中的作用以及在不同流动条件下的阻力特性。
The effect of Jet-Pump in the transient procedure of natural circulation and the resistance behaviour of Jet-Pump in the different flow condition have been analyzed.
针对分散布置的核船压水堆一回路的特点，分析了船舶纵摇和横摇对自然循环能力的不同影响。
In view of the characteristics of the separate arranged PWR primary loop in nuclear power ship, the different influences of pitching and rolling on natural circulation ability have been analyzed.
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。
The natural circulation ability of PWR (pressurized water reactor) coolant system is one of inherent safeties of this kind NPP (nuclear power plant).
MR-100G和MR-1G是专门为区域供热和冷却系统提供能源、一回路系统自加压的全自然循环一体化压水堆。
MR-100G and MR-1G, the power supply system for district heating and cooling, are a self-pressurized, nature circulated integral PWR.
MR-100G和MR-1G是专门为区域供热和冷却系统提供能源、一回路系统自加压的全自然循环一体化压水堆。
MR-100G and MR-1G, the power supply system for district heating and cooling, are a self-pressurized, nature circulated integral PWR.
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