压水堆核电站

压水堆核电站运行堆芯物理过程的PC仿真和演示平台研制

The Person-Computer Simulation And Demonstrate platform Research on PWR Nuclear Power Plant Physics-Running

我国2×600MW压水堆核电站的投资研究和电力成本分析

The Capital Investment and Electricity Cost of 2 × 600 MW PWR Nuclear Power Plant in China

KWU压水堆核电站重要特点&限制系统在设计中的应用

The Important Characteristic of KWU PWR Nuclear Power Plant & Application of the Limitation System

1000MW和600MW压水堆核电站的电力成本分析

The Electric Costs Analysis of 1000 MW and 600 MW PWR Nuclear Power Plant

本文概述KWU压水堆核电站限制系统的功能和优点。

This paper summaries the function and advantage of the limitation system of KWU PWR nuclear power plant .

自主化1000MW级压水堆核电站核蒸汽供应系统概念设计

Conceptual Design of NSSS for 1000 MW PWR Nuclear Power Plant of China

本文论述了600MW压水堆核电站蒸汽发生器设计的自主化、材料和制造的国产化。

The paper discusses the self-reliant design , and fabrication of a600MW PWR unit 's steam generator with domestic supplied materials .

电力系统全过程仿真所需要的火电厂动力系统的数学模型、水电厂动态模型、压水堆核电站模型以及发电自动控（AGC）模型等已在电力系统全过程仿真软件中得到实现。

The dynamic models , such as thermal power plant , hydroelectric power plant , nuclear power plant and the automatic generation control ( AGC ), which are necessary for power system full simulation are implemented in power system full dynamic simulation software .

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 .

苏联压水堆核电站燃料组件的科研与生产概况

Research and Production for Nuclear Fuel Assemblies of PWR in USSR

压水堆核电站蒸汽发生器二次侧的清洗与检查

Mechanical cleaning and TV inspection for secondary-side in PWR steam generators

压水堆核电站主冷却剂泵泵壳的实验应力分析

Experimental stress analysis for reactor coolant pump case of PWR NPP

压水堆核电站二回路热力系统的设计特点

Design Features of the Secondary Loop Thermal Systems of PWR unit

压水堆核电站&回路辅助设备的布置设计

Arrangement Design of Primary Loop Auxiliary Equipment for pressurized-Water Reactor Power Plants

压水堆核电站氚的辐射风险分析

Radiation Risk Analysis of Tritium in PWR Nuclear Power Plants

用于电力系统动态模拟的压水堆核电站数学模型

Pressurized Water Reactor Nuclear Power Plant Model for Power System Dynamic Simulation

压水堆核电站严重事故紧凑型仿真机开发

Development of A Compact Severe Accident Simulator for PWR Nuclear Power Plants

用遗传算法构造压水堆核电站稳压器模糊控制规则库

Establishment of Rule Base for PWR Pressurizer Fuzzy Controller by Genetic Algorithm

内陆压水堆核电站放射性液态流出物对水环境的影响

Water Environmental Impact of Radioactive Liquid Effluents from Inland Nuclear Power Plant

压水堆核电站大型湿蒸汽汽轮机的性能比较

Comparison of Large Wet Steam Turbine Characteristics for Nuclear Power Station PWR

压水堆核电站主蒸汽湿度测量

Measurement of the Main Steam Moisture of PWR Power Plant

压水堆核电站二回路蒸汽循环及其改进

The Steam Cycle of PWR Secondary System and Its Improvement

压水堆核电站在役检查用无损检测技术发展概况

Development Status of NDT Technology for PWR NPP In-Service Inspection

压水堆核电站不锈钢水池的焊接

Welding of Stainless Steel Pool of Pressurized Water Reactor Nuclear Power Station

压水堆核电站的用钢量及要求

The Quantity and Requirement to the Steel for PWR Nuclear Power Plant

压水堆核电站放射性核素体内污染早期医学干预

Early medical intervention after internal contamination with radionuclides in PWR

大型压水堆核电站堆本体主屏蔽三维离散纵标计算分析

Analysis of the PWR Primary Shield with 3-D S_N Method

30万千瓦压水堆核电站的主要设计特征

The Main Design Features of 300 MW PWR Power Stations

痕量硼分析在压水堆核电站的应用

Application of trace boron analysis in nuclear power plant of pressurized water reactor

压水堆核电站的启动与初期运行

Startup and Early Operation of PWR Nuclear Power Plants