压水堆,PWR
1)PWR压水堆
1.PWR LOCA Analysis with Condensation Reflux Model;采用冷凝回流模型的压水堆失水事故分析
2.Fuzzy Control of Boron Concentration for Load Following on PWR;用于压水堆负荷跟踪运行的硼浓度模糊控制系统
3.The development trend of PWR technology;压水堆技术发展趋势概述
英文短句/例句

1.The Nuclear Core Design of 450MWt Pressurized Water Reactor45万千瓦(热)压水堆堆芯核设计
2.External Reactor Vessel Cooling Measure in Severe Accident for Pressurized Water Reactor Nuclear Power Plant压水堆核电厂严重事故下堆腔注水措施研究
3.The comparison of the computational results for reactor core of PWR and BWR are also presented.文中还给出了压水堆和沸水堆堆芯计算实例的比较。
4.Measurements for monitoring adequate cooling within the core of pressurized light water reactorsGB/T13632-1992监督压水堆堆芯充分冷却的测量要求
5.Preliminary study on thorium-uranium fuel cycle in the equilibrium core of PWR压水堆平衡堆芯钍铀燃料循环初步研究
6.Optimization of BurnablePoison Assignment for PWRLow Leakage Reload Core压水堆低泄漏换料堆芯可燃毒物的优化配置
7.Modeling and Simulation of the PWR Core and Its Control Systems;压水堆堆芯系统建模及其控制系统仿真研究
8.Radiant Deformation of PWR AFA17×17 Fuel Assembly and Core Loading of Deformed Fuel Assembly;压水堆AFA17×17燃料组件辐照变形及其堆芯装料
9.Simulation of Dynamic Mathematical Modeling for PWR Nuclear Power Plant Core Based on PSASP基于PSASP的压水堆核电站堆芯建模及仿真研究
10.The hybrid breeders can provide plenty of fissile material for PWR or FBR.聚变-裂变混合堆可以为压水堆或快堆提供充足的核燃料。
11.Helium leak testing of nuclear fuel rod for PWRGB/T11813-1996压水堆燃料棒氦质谱检漏
12.Metallographic examination for weld seam of nuclear fuel rod used in PWRGB/T11809-1998压水堆核燃料棒焊缝金相检验
13.Guide to design of nuclear fuel rods for PWRGB/T11925-1989压水堆核燃料棒设计导则
14.Classification for the items of pressurized water reactor nuclear power plantsGB/T17569-1998压水堆核电厂物项分级
15.Development of New Zirconium Alloys for PWR Fuel Rod Claddings压水堆燃料包壳新锆合金的发展(英文)
16.A Cold Stepping Driving Experiment for a Control Rod Drive Line of PWR压水堆控制棒驱动线的冷态步跃试验
17.Study of Boron Poisoning Experiments on Advanced PWR Zero-Power Core with Steel-Water Reflector Assembly先进压水堆铁水反射层组件零功率堆芯硼中毒实验研究
18.Trip analysis and online diagnosis regulation for loosing water level control of the PWR steam generator压水堆蒸发器水位调节失控跳堆分析及在线诊断调整
相关短句/例句

Pressurized water reactor压水堆
1.Application of linearized model to the stability analysis of the Pressurized Water Reactor;线性化模型在压水堆堆芯系统稳定性分析中的应用
2.The studies on the dissolution characteristics of simulated corrosion product of iron on pressurized water reactor primary coolant loops in aqueous solution of citric acid,hydrogen peroxide and citric acid-hydrogen peroxide have been performed.研究了压水堆主回路铁的模拟腐蚀产物在柠檬酸、过氧化氢、柠檬酸过氧化氢的水溶液中的溶解特性,结果表明:铁模拟腐蚀产物在柠檬酸水液中的溶解量随柠檬酸浓度增加而增大,随温度的升高而增大,在60℃不同pH值时溶解量值的排列次序为pH3。
3.In the embedded simulation of operation and control lor the marine pressurized water reactor (PWR),the digital-analog conversion device is used to input and output data,MATLAB,Relap5/MOD3 and Vega software are adapted to be federation members,and VR-Link/RTI is used to built HLA distributed sim- ulation structure.船用压水堆运行控制的嵌入式仿真通过数模转换装置进行数据的采集和输出,利用MATLAB、Relap5/MOD3、Vega进行联邦成员构建,在VR-Link/RTI构建的HLA分布式仿真平台上进行数据交互,以实现反应堆运行控制各相关部分的数学仿真、视景仿真,通过安全分析,讨论了船用压水堆运行控制的嵌入式仿真的安全性。
3)PWR nuclear power plant压水堆
1.According to the characteristics of the secondary circuit of PWR nuclear power plant, the heat to power conversion coefficient of extracted steam and reheat character\|istic coefficient are proposed.针对压水堆核电机组采用新蒸汽再热的特点 ,经过详细的理论分析和数学推导 ,提出了压水堆二回路加热器抽汽效率和新蒸汽再热特性系数 ,利用其得出了纯热量和带工质热量进出热力系统的定量分析法则 ,建立了压水堆二回路的热力系统经济性定量分析的数学模型 ,从而为优化设计、经济运行及经济性诊断提供了一套概念清晰、计算简捷的压水堆核电机组二回路的经济性定量分析理论。
2.An economic study is made for the characteristics of the secondary circuit of PWR nuclear power plant.针对压水堆核电机组采用新蒸汽再热的特点 ,利用压水堆二回路加热器抽汽效率的概念 ,提出了带工质热量进出热力系统的定量分析方法 ,建立了压水堆二回路热力系统的经济性定量分析数学模型 ,得出了一套概念清晰、计算简捷的压水堆核电机组二回路的定量分析方法 ,为优化设计、经济运行、经济性诊断提供了有力的工具 。
3.Through analysis and research of differences between thermodynamic system of PWR nuclear power plant and coal-fired power unit,unified physical and mathematical models of heat-economic analysis for thermodynamic system of PWR nuclear power plant is established.在建立了火电机组热经济性分析统一物理模型和数学模型的基础上,通过对压水堆核电机组二回路热力系统与火电机组热力系统的相同与不同之处进行分析与研究,建立了压水堆核电机组二回路热力系统热经济性分析统一物理模型和数学模型,统一物理模型的形式规范简明,由此导出的数学模型形式简单统一,物理意义明确,是核电机组进行热经济分析和能耗分析的重要工具,并通过实例验证了模型的正确性。
4)pressurized water reactor core, PWR core压水堆堆芯
5)pwr压水型堆
6)LPWR (light water PWR)轻水压水堆
延伸阅读

压水堆压水堆pressurizedwaterreactor使用加压轻水(即普通水)作冷却剂和慢化剂,且水在堆内不沸腾的核反应堆。燃料为加浓铀。20世纪80年代,被公认为是技术最成熟,运行安全、经济实用的堆型。其装机总容量约占所有核电站各类反应堆总和的60%以上。最早用作核潜艇的军用反应堆。1961年,美国建成世界上第一座商用压水堆核电站。压水堆由压力容器、堆心、堆内构件及控制棒组件等构成。压力容器的寿命期为40年。堆心装核燃料组件。压水堆