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.
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.
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.
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.
本文介绍了压水堆核电站排风净化的任务、设计准则和主要设备。
This paper describes duties, design criteria and major equipments of exhaust air cleaning for PWR nuclear power plants.
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.
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.
压水堆核电站依靠控制棒实现反应堆功率的快速调节和特殊情况下的紧急停堆。
The control rods are used to implement quick regulation of the reactor power and emergent shutdown of the reactor in pressurized water nuclear power station.
此外，由于温度和中毒负反馈，压水堆核电站能承受一定的干扰，包括分步功率。
In addition, due to temperature and poisoning negative feedbacks, PWR NPP can withstand certain disturbances including step power.
本文介绍日本压水堆核电站蒸汽发生器传热管破损情况，破损原因和防止传热管破损的措施。
The paper presents status of failure incidents of PWR steam generator heat transfer tubes in Japan as well as causes of failure and measures used for protection.
压水堆核电站计算机支持系统CSSNPP是为操作员以及相关人员培训研制的一个核电站计算机支持系统。
The computer supported system for nuclear power plant (CSSNPP) is a specialized system aiming to train operators and relative staffs.
当1969年开始建设时，Metsamor用的是VVER440型230反应堆，最早的压水堆核电站的设计样板之一，是由苏联在1956年- 1970年间开发的。
When construction began in 1969, Metsamor was a VVER 440, Model 230, an example of one of the earliest pressurized-water nuclear plant designs, developed by the Soviets between 1956 and 1970.
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.
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.
用内转换电子穆斯堡尔谱学方法，配合X衍射能谱研究了秦山核电站一期压水堆三回路海水中涡轮叶片的腐蚀。
The stainless steels used in Qinshan nuclear power station have been studied by using the conversion electron Mssbauer spectroscopy, accompanying with X ray diffraction.
标准化核电站系统(简称SNUPPS)是西屋电气公司建造的众多压水反应堆之一。
SNUPPS, or Standardized Nuclear Unit Power Plant System, is one of a series of pressurized-water reactors built by Westinghouse.
核主泵是压水型反应堆核电站中的核心设备之一。
The nuclear reactor coolant pump (RCP) is one of the core equipments in PWR nuclear Power Plant.
作为压水堆核电机组中的水力能动设备，泵类产品的可靠性对整个核电站的安全起着及其关键的作用。
As a dynamic equipment in the PWR units, the reliability of the pumps is key to the security of whole nuclear power station.
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.
失水事故是核电站设计的基准事故之一，是压水堆事故分析关注的重点。
Loss of coolant accident is considered as design basis accident in the design of nuclear power plant. It is the key point of accident analysis for pressurized water reactor plant.
失水事故是核电站设计的基准事故之一，是压水堆事故分析关注的重点。
Loss of coolant accident is considered as design basis accident in the design of nuclear power plant. It is the key point of accident analysis for pressurized water reactor plant.
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