steam-electric generating station
蒸汽发电厂，蒸汽电站
The temperature of reheat steam directly influences the efficiency of a power station.
再热蒸汽温度直接影响电站的经济性。
Design of on Line Monitoring Wetness Fraction System in Steam Turbine of Nuclear Power Plant;
核电站汽轮机入口蒸汽湿度在线测量系统设计
Main steam safety valve is the protective device against overpressure in the steam system of nuclear island.
主蒸汽安全阀是压水堆核电站核岛内主蒸汽系统的超压保护装置。
Qinshan Phase Ⅱ Nuclear Power Plant Main Steam Isolation Valve Vibration and Noise Analysis;
秦山二期核电站主蒸汽隔离阀振动与噪音分析
On the Steam Flow Distribution of Complex System of Utility Boiler;
大容量电站锅炉复杂系统蒸汽流量分布研究
Study and Application of the Noise Reduction Technology for Boiler Steam Purging in Power Plant;
电站锅炉蒸汽吹管降噪技术的研究与应用
Study on Operation-optimization of Gas-Steam Combined Cycle Plant Unit;
燃气—蒸汽联合循环电站机组运行优化研究
Leak Testing for Manufacturing and Shutdown of Nuclear Power Station Steam Generator
核电站蒸汽发生器制造和停堆期间的泄漏检验
electric [steam] traction
电力 [蒸汽] 牵引 (力)
Ir. D.F. Woudagemaal (D.F. Wouda Steam Pumping Station)
迪-弗-伍达蒸汽泵站
The Research on Method of Measuring Steam Wetness in Nuclear-power Plant Turbine Based on Double-region-heating;
基于双区加热法的核电站汽轮机蒸汽湿度测量的方法研究
Nuclear Power Plant Turbine Steam Humidity Measuring Method Based on Image Technology;
基于图像技术的核电站汽轮机蒸汽湿度测量方法的研究
The newest ones heat the steam to as much as 600°C-a state physicists call “supercritical”.
最新型的发电站能够将蒸汽升温至600°C——物理学家们称为“超临界”态。
Design and Test of Westinghouse PWR Steam Generators
西屋公司压水堆核电站蒸汽发生器的设计与试验
CSDVS fail open event analysis and handling measure of CANDU nuclear power plant
重水堆核电站主蒸汽旁排阀故障分析和应对策略
Theoretical and Experimental Study on the Optimization of Dryer in Steam Generators for Nuclear Power Station;
核电站蒸汽发生器干燥器结构优化理论与试验研究
Strategy Study for Raw Material Procurement Used in Reactor Pressure Vessel and Steam Generator at AP1000 NPP;
AP1000核电站压力容器、蒸汽发生器原材料采购策略研究
