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.
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.
其堆芯流动采用自然循环。
Natural circulation is adopted in the flowage of reactor core.
试验是为确定自然循环池式核供热堆的热工水力学参数而进行的。
The purpose of this experiment was to determine the themohydraulic parameters in pool-type nuclear heating reactor with natural circulation.
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.
通过实验研究了一体化自然循环反应堆压力壳上部自稳压气空间对于自然循环两相流系统启动过程中流动稳定性的影响。
The influence of the gas space on the top of an integral reactor vessel on the flow stability in the start up process of a natural circulation two phase flow system is studied experimentally.
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.
结果表明：起伏对强制循环下一回路冷却剂的流量和反应堆输出功率的影响较小，而对自然循环能力的影响很大。
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.
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).
它包括脉冲堆自然循环分析程序（MC-FLOW）、堆芯热工水力分析程序（MC-THAS）和脉冲堆瞬态分析程序（MC-TRAN）。
They are the natural circulation flow analysis code (MC-FLOW), the core thermal hydraulic analysis code (MC-THAS) and the pulsed reactor transient analysis code (MC-TRAN).
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.
针对研发的采用一体化布置、全功率自然循环的低温核反应堆电站，建立了一个可用于大功率运行范围控制系统仿真的动态数学模型。
This paper discusses the considerations in the modeling of a new type of nuclear power plant for its control system simulation in a wide power range.
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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