A process for development of the Pilot Type HTHP Solenoid Valve used in a PWR power plant is described in this paper.
本文介绍了一种用于压水堆动力装置的间接操作式高温高压电磁阀的开发过程。
This model can be used to analyze thermal-hydraulic transient behaviour of inverted U-tube steam generators in PWR 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。
Control rods are used in a PWR typically to change the power level and also to shut down the reactor.
控制棒是在一个加压水冷却反应堆里使用的，用来改变能量的级别，也可以用来停止反应堆。
This prensentation mainly analyzes the transient of uncontrolled RCCAwithdrawal from a subcritical or low power condition for PWR.
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。
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.
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。
In order to carry out power transient tests for PWR fuel element in China Advanced research Reactor (carr), the research and conceptual design of 3he pressure control loop were completed.
为使中国先进研究堆(CARR)具备开展压水堆燃料瞬态试验的能力，本工作对氦- 3回路进行研究与初步设计。
In addition, due to temperature and poisoning negative feedbacks, PWR NPP can withstand certain disturbances including step power.
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。
There are four types for PWR pressure-relieving devices: direct acting safety valve, pilot-operated pressure relief valve, power-operated pressure relief valve and safety valve with auxiliaries.
PWR的压力释放装置主要有四种类型：直接作用式安全阀、先导操作压力释放阀、动力作用式压力释放阀和具有辅助装置的安全阀。
The PWR in-core temperature detection device, which is one of measures to ensure reactor safety operation, is to monitor and diagnose reactor thermal power output and in-core power distribution.
压水反应堆堆内温度测量装置是监测反应堆热功率输出及堆内功率分布情况、保证反应堆安全运行的手段之一。该装置以热电偶作为测量元件，用不锈钢作保护外套。
The key safety problem of a steam generation of PWR nuclear power plant is its instrumentation and control of water level, thus the reliability and safety is most important.
压水反应堆核电厂的蒸汽发生器的关键安全性问题就是其液位的仪表检测及控制问题，因此其可靠性与安全性就是极重要的因素。
The high-pressure core melt accidents in PWR nuclear power plant which cover most of the severe accidents, have large potential risk.
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 paper reports the model of the reactor core of the PWR nuclear power plant and established the suitable core physics-mathematics model for microcomputer simulation.
阐述了PWR核电站堆芯的模型化问题，提出了适用于微机仿真的核电站堆芯的物理数学模型。
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.
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。
This paper briefly describes the siting of Qingshan Nuclear Power Plant, the first 300MW PWR unit of China.
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。
The nuclear reactor coolant pump (RCP) is one of the core equipments in PWR nuclear Power Plant.
核主泵是压水型反应堆核电站中的核心设备之一。
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 PWR core thermal-hydraulic design, including the design objective, criteria and main design parameters, specifically that for the Qin-Shan Nuclear Power Plant is described.
本文介绍了压水堆堆芯的热工-水力设计，其中包括了设计任务、准则和主要设计参数，并对秦山核电厂的热工和水力设计作了较详细的描述。
The design and construction rules applicable to mechanical components of PWR nuclear Islands (RCC-M) are a part of the collection of design and construction rules for nuclear power plants.
压水堆核岛机械设备的设计和建造规则(RCC - m)是核电厂设计和建造规则系列规范之一。
This paper describes duties, design criteria and major equipments of exhaust air cleaning for PWR nuclear power plants.
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。
As a dynamic equipment in the PWR units, the reliability of the pumps is key to the security of whole nuclear power station.
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。
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.
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。
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