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。
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。
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 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。
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