本篇论文对压水堆核电站进行了论述。
本篇论文对压水堆核电站进行了论述。
This paper has carried on the elaboration to the pressurized water reactor nuclear power station.
这要看核电站的类型，它是沸水堆还是压水堆。
It depends on the plant.It depends on whether it's a boiling-water reactor or a pressurized-water reactor.
文中简要介绍了国外压水堆核电站的发展趋势。
The paper presents the developing tendency of PWR NPP briefly.
研究了冷凝回流在压水堆中破口失水事故中的作用。
The effect of condensation reflux model in PWR LOCA analyses was investigated.
还介绍了保证压水堆核电站二回路水汽质量的措施。
Furthermore, this article introduces the techniques to ensure the water vapor quality in secondary circuit of PWR.
实验结果可用于合理选择压水堆安全壳喷淋系统参数。
The experimental results are useful for rational selecting parameters of containment spray system of PWR.
探讨了MOX燃料在国内压水堆核电站中的应用问题。
The application of MOX fuel in China's PWR is discussed in the end.
在目前，核电站中以压水堆和沸水堆所占的比例最大。
At present, the pressurized water reactor and boiling water nuclear power reactor in the largest proportion.
聚变-裂变混合堆可以为压水堆或快堆提供充足的核燃料。
The hybrid breeders can provide plenty of fissile material for PWR or FBR.
本文对水堆中的中子局部噪声和整体噪声进行了理论分析。
The local and global components of neutron noise in water reactor are ana-lysed.
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.
介绍了压水堆核电厂换料堆芯功率能力验证分析的原理和方法。
The Principle and methodology of pressurized water reactor nuclear power plant core power capability verification for reload are introduced.
本文介绍了压水堆核电厂蒸汽发生器的一维均相流瞬态分析模型。
This paper presents an one-dimensional homogeneous flow model for thermal-hydraulic transient behaviour of PWR steam generators.
压水堆核电站反应堆功率的控制是通过调节控制棒和硼浓度来实现的。
The control of the pressurized-water reactor's power is transited by accommodate -ting the control rod and boron concentration.
1月13日，海军陆战队营地，一箱箱的瓶装水堆方在一个临时遮蔽处下。
At Camp Leatherneck, cases of bottled water are piled high under a makeshift shelter on Jan. 13.
欧洲压水堆(EPR)是目前世界上最具代表性的新一代核电堆型之一。
European pressurized water reactor (EPR) is currently one of the most typical new generation reactor types.
本文介绍了压水堆噪声基准试验信号分析，并从中得出一些有用的结果。
This paper described benchmark test noise signal analysis of PWR and gets some useful results.
压水堆核电站一回路和乏燃料贮存水池的设备冷却水由海水冷却器提供。
The equipment cooling water used in primary circuit loop and spent fuel system is provided by seawater cooler in nuclear power station.
对于压水堆燃料组件而言，栅格稠密、几何形状复杂，对中子的吸收较强。
Considering fuel assembly for PWR, it is possessed of dense lattice, complex geometry and strong absorption of neutron.
本文主要分析压水堆在次临界或低功率下发生的失控提捧事故的瞬态特性。
This prensentation mainly analyzes the transient of uncontrolled RCCAwithdrawal from a subcritical or low power condition for PWR.
并详细论述和分析了一体化压水堆的技术基础，经济竞争力及其应用前景。
The paper analyzes in detail the technical basis, economic competition and application of IPWR.
针对压水堆核动力装置蒸汽发生器的水位控制提出一种分层模糊自适应控制方案。
A hierarchical adaptive fuzzy control scheme is proposed for steam generator level control of nuclear power plants.
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.
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).
压水堆核电厂的高压熔堆事故覆盖了大部分的严重事故序列，且具有很大的潜在威胁。
The high-pressure core melt accidents in PWR nuclear power plant which cover most of the severe accidents, have large potential risk.
本文简要介绍了我国第一座300MW压水堆型核电站——秦山核电厂的厂址选定情况。
This paper briefly describes the siting of Qingshan Nuclear Power Plant, the first 300MW PWR unit of China.
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.
强迫循环条件下，压水堆一回路主循环泵有效压头的损失随喷射泵阻力系数的增加而增加；
The loss of efficient head of circulation pump in the primary loop of PWR will increase with the increase of resistance coefficient of JetPump under forced circulation.
强迫循环条件下，压水堆一回路主循环泵有效压头的损失随喷射泵阻力系数的增加而增加；
The loss of efficient head of circulation pump in the primary loop of PWR will increase with the increase of resistance coefficient of JetPump under forced circulation.
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