| 单词 | pwr. | ||||
| 释义 | pwr.
例句释义: 力量,动力 1. The detailed geometry characteristics of the new PWR as well as the flow patterns and heat transfer conditions were considered in the model. 模型对新型压水堆在稳态自然循环过程中可能出现的流动形式和换热状态进行了充分考虑。 www.ceps.com.tw 2. Pratt & Whitney Rocketdyne ( PWR ) is a United States company that designs and produces rocket engines that use liquid propellants. 以下简称洛克达因）是美国的一家主要从事液体燃料火箭发动机设计研发的公司。 instapedia.com 3. GO methodology was applied to analyze the reliability of PWR purification system with common cause failures. 应用GO法分析了共因失效对压水堆净化系统可靠性的影响。 www.ceps.com.tw 4. This paper presents laboratory research results of cement solidification of borate acid liquid wastes and concentrates arising from PWR. 本文介绍了压水堆核电站产生的硼酸废液和浓缩废液水泥固化的实验室研究结果。 dictsearch.appspot.com 5. An adaptive-cost-function optimal controller design for a PWR nuclear reactor. 压水堆自适应成本函数最优化控制装置设计…[中国核科技信息与经济研究院]。 210.82.31.83 6. The results show that the common cause failures greatly affect the reliability of PWR purification system. 结果表明，共因失效对压水堆净化系统可靠性有很大影响。 www.ceps.com.tw 7. The departure from nucleate boiling (DNB) is important concerning about the safety of a PWR. 偏离泡核沸腾（DNB）对于压水堆安全具有重要意义。 www.aest.org.cn 8. Before installing or removing an IF cable, turn off the ODU-PWR power switch on the IF board. 在安装、拆除中频电缆前，必须关闭中频板的电源输出开关。 wenku.baidu.com 9. Furthermore, this article introduces the techniques to ensure the water vapor quality in secondary circuit of PWR . 还介绍了保证压水堆核电站二回路水汽质量的措施。 dictsearch.appspot.com 10. The load following of pressurized water reactor(PWR)is studied. A three-dimensional fuzzy control system of boron concentration is designed. 对压水堆负荷跟踪运行进行了研究，提出将一种三维模糊控制系统应用于硼浓度自动调节的设计方案。 www.chemyq.com 1. The author studied on the modeling and simulation of PWR core and its control systems. 本文对压水堆堆芯及其控制系统进行了建模与仿真研究。 dictsearch.appspot.com 2. PAINTS AND VARNISHES. PAINTS FOR THE NUCLEAR INDUSTRY. TEST OF BEHAVIOUR IN IONISING RADIATIONS (PWR). 核工业涂料.受电离辐射时状态的试验（压水反应堆） www.mapeng.net 3. 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。 open.163.com 4. Plutonium recycling in a fuel-MOX 900-NW(e) PWR: physical analysis of accident behaviors. 钚在900兆瓦（电）全混合氧化物燃料压水堆中的再循环：事故行为物理分析…[中国核科技信息与经济研究院]。 210.82.31.83 5. An error that affects the integrity of system operation such as a detected address parity error or an invalid PWR _GOOD signal. 影响系统操作完整性的错误，如已检测到的地址奇偶错，或者无效的PWR_GOOD信号。 dictsearch.appspot.com 6. Now typically in a PWR this is typically a configuration for a PWR. 现在在压水式反应堆里，这是个典型的，结构，对一个压水式反应堆来说。 open.163.com 7. This paper first looks back to vary control programs and the development of control system of pressurized water reactor (PWR). 本文首先回顾了国内外压水堆的各种控制方案以及控制系统得发展现状。 www.yidu.edu.cn 8. The 300 MW PWR unit is the first nuclear power station designed and built in China. 我国自行设计制造的第一座核电站为30万千瓦压水堆核电站。 dictsearch.appspot.com 9. RCP leak rate is a quite important parameter in PWR for its radioactivity, which is required to be calculated every day. 一回路冷却剂的泄漏率是压水堆核电厂放射性控制相关的一个重要物理量，需要定期进行监测。 www.ceps.com.tw 10. Computer simulation of PWR nuclear power station's liquid ejections around the sea area and statistics analysis of the inspected data 核电站液态流出物在受纳海域中分布的计算机模拟和监测数据统计分析 ilib.cn 1. Prediction of flow induced damping of a PWR fuel assembly in case of seismic and LOCA load case PWR 堆燃料组件在地震和冷却剂丧失情况下流动诱导衰减预测 inis-china.atominfo.com.cn 2. The Accidents Mitigation Concept of French PWR Nuclear Power Plant 法国压水堆核电厂事故缓解对策 www.35kv.cn 3. Specific Radioactivity Produced by the Secondary Charged Particle Nuclear Reaction in the Primary Circuit Water of PWR 压水反应堆一回路水中二次带电粒子核反应产物的比活度 www.ilib.cn 4. Microcomputer simulation of the centrality parameter modeling for PWR nuclear power plant reactor core 压水堆核电站堆芯集中参数模型的微机仿真 ilib.cn 5. Research on Economy Quantitative Analysis Theory for the Secondary-Circuit of PWR Nuclear Cogeneration Plant 热电联产压水堆机组二回路经济性定量分析理论的研究 www.ilib.cn 6. Design for Improving Operational Sequence of Granulation and Compression in Production of Elements for PWR Nuclear Power Station 压水堆核电站元件生产制粒、压制工序改进设计 ilib.cn 7. A Computer Code for Calculating Initial Temperature Distribution of Instrumented Fuel Element for PWR in Pile Experiment 压水堆堆内试验仪表化燃料元件初始温度分布计算程序 www.ilib.cn 8. Characterization of Decommissioned PWR Vessel Internals Material Samples: Tensile and SSRT Testing (Non proprietary Version) 退役的压水堆容器内部构件材料样本描述：拉伸和慢应变速率试验（非专有版） inis-china.atominfo.com.cn 9. Experiments and CFD calculations on coolant mixing in PWR - Application to boron dilution transient analysis 压水堆中冷却剂混合的试验和计算流体动力学计算 inis-china.atominfo.com.cn 10. PC-Based Simulation of the Centrality Parameter Modeling for PWR Nuclear Power Plant Reactor Core 压水堆核电站运行堆芯物理过程的PC仿真 ilib.cn 1. Analysis of mechanisms induced by sliding and corrosion: dedicated apparatus for PWR environments 滑动和腐蚀引发的机理分析：压水堆环境下专用设备 inis-china.atominfo.com.cn 2. Research on Coolant Flow Governing Methods for Marine PWR Nuclear Power Plant under Ideal Steady-state Programming 船用压水堆核动力装置双恒定运行方案下的冷却剂流量调节方案 ilib.cn 3. Application of Nonlinear Iteration Semi-analytical Nodal Method in the PWR Fuel Management Calculation 非线性迭代半解析节块方法在压水堆燃料管理计算中的应用 www.ilib.cn 4. Effect of yield strength on stress corrosion crack propagation under PWR and BWR environments of hardened stainless steels 压水堆和沸水堆环境下淬火不锈钢屈服强度对应力腐蚀裂纹扩展影响 inis-china.atominfo.com.cn 5. Development of A Compact Severe Accident Simulator for PWR Nuclear Power Plants 压水堆核电站严重事故紧凑型仿真机开发 ilib.cn 6. Comprehensive Control of PWR Pressurizer Using Typical Fuzzy Controllers 采用典型模糊控制器实现压水堆稳压器的综合控制 scholar.ilib.cn 7. Metallographic examination for weld seam of nuclear fuel rod used in PWR 压水堆核燃料棒焊缝金相检验 blog.globalimporter.net 8. Modal testing and identification of a PWR fuel assembly PWR 堆燃料组件的模式化试验与验证 inis-china.atominfo.com.cn 9. Aging problems and life evaluation for the key metallic components in PWR nuclear power plant 压水堆核电厂关键金属部件的老化和寿命评估 ilib.cn 10. Development of the Method and Code System for Three Dimension Hexagonal PWR Core Fuel Management Calculation 三维六角形组件压水堆堆芯燃料管理计算及程序系统研究 ilib.cn 1. Ultrasonic Testing Standards Comparison of Heavy Forgings for PWR Pressure Vessel 压水堆承压容器厚大锻件超声检测标准的比较 www.ilib.cn 2. PWR containment radiation levels calculation relate to core conditions PWR堆芯不同状况下安全壳内辐射水平的计算 www.ilib.cn 3. Research on control strategy of marine PWR nuclear power plant under ideal steady-state programming 船用核动力装置双恒定运行方案控制策略研究 ilib.cn 4. Reactor Core Characteristics of PWR and Its Evolvement 压水堆堆芯设计特点及其演变 www.ilib.cn 5. Transient Analysis on Heat Transfer and Hydraulic of Passive Containment Vessel of Advance PWR 先进堆非能动安全壳热工水力瞬态分析及研究 www.ilib.cn 6. Low-leakage Loading Pattern Optimization for PWR NPP Reload Core Using Genetic Algorithms 遗传算法在压水堆核电厂低泄漏换料堆芯装载方案优化中的应用 service.ilib.cn 7. Overview of Research Development on Key Technologies for Advanced PWR Nuclear Power Plant 先进压水堆核电站关键技术研究开发综述 ilib.cn 8. Transient Characteristic Research on Passive Residual Heat Removal System of Chinese Advanced PWR 中国先进压水堆非能动余热排出系统瞬态特性研究 www.ilib.cn 9. Establishment of Rule Base for PWR Pressurizer Fuzzy Controller by Genetic Algorithm 用遗传算法构造压水堆核电站稳压器模糊控制规则库 www.ilib.cn 10. Simulation Model of Natural Circulation in PWR Coolant System under Ocean Conditions 海洋条件下冷却剂系统自然循环仿真模型 www.ilib.cn 1. Seismic behaviour of PWR reactor cores whole cores: Coupling between assemblies 压水堆整个堆芯的地震性能：组件间的耦合 inis-china.atominfo.com.cn 2. The Simulation Research for The Dynamic Performance of Integrated PWR 一体化压水堆动态特性的仿真研究 service.ilib.cn 3. Thermo-Economics Analysis for the Secondary-Circuit of PWR Nuclear Power Plant 压水堆核电机组二回路定量分析方法的研究 ilib.cn 4. Numerical Simulation of Pump-Stopping Water Hammer in Tertiary Circulating Water System of PWR Nuclear Power Plant 压水堆核电厂三回路停泵水锤数值模拟 www.ilib.cn 5. Analysis of Natural Circulation Ability in PWR Coolant System under Ocean Condition 简谐海洋条件下堆芯冷却剂系统自然循环能力分析 ilib.cn 6. Experimental Research on Passive Residual Heat Remove System for Advanced PWR 先进压水堆非能动余热排出技术试验研究 www.ilib.cn 7. Research on Steady Characteristic of Passive Residual Heat Removal System of Chinese Advanced PWR 中国先进压水堆非能动余热排出系统稳态特性研究 www.ilib.cn 8. Large-scale PWR Power Plants Participating in Peak-load Regulation of Grid Middle Load 探讨大型压水堆核电机组参与电网中间负荷调峰 www.ilib.cn 9. Research on Properties of PWR Main Pipe Line of Nuclear Electric Power Plant 核电厂压水堆主管道材料性能的研究 www.ilib.cn 10. Innovation on Structure of All Automatic Multi-Studs Four Synchronous Installing Machine Used in PWR 压水堆核电厂用全自动多螺栓四同步安装机的结构创新研究 www.ilib.cn 1. Research on embedded simulation of marine PWR about operation and control 船用压水堆运行控制的嵌入式仿真研究 service.ilib.cn 2. Radioactive source term of PWR nuclear power plant for operational states 压水堆核电厂运行工况下的放射性源项 blog.globalimporter.net 3. Fuzzy controller design method for PWR steam generator level control 压水堆蒸汽发生器水位模糊控制器的设计方法 www.ilib.cn 4. Innovative PWR design concept with low primary circuit pressure 低一回路压力的创新压水堆设计概念 inis-china.atominfo.com.cn 5. Research on Ideal Steady-State Programming of Marine PWR Nuclear Power Plant 船用压水堆核动力装置双恒定运行方案静态特性研究 www.ilib.cn 6. Exponential experiments on PWR spent fuel assemblies 压水堆乏燃料组件指数实验 inis-china.atominfo.com.cn 7. Study on Virtual Simulation Technology for Operation and Control of PWR 压水堆运行控制的虚拟仿真技术研究 www.ilib.cn 8. Design criteria for control room evacuation of PWR nuclear power plants 压水堆核电厂控制室撤离设计准则 bz.qs100.com 9. Ageing management review for main components of PWR nuclear power plant 压水堆核电站主要设备的老化管理评述 inis-china.atominfo.com.cn 10. Modeling on a PWR Power Conversion System with System Program 基于系统程序的压水堆核电厂热力系统建模 www.ilib.cn 1. Thermal-hydraulic Tests on Passive Containment Cooling System of Advanced PWR 非能动安全壳冷却系统热工水力单项试验 www.ilib.cn 2. Modeling in fast dynamics of accidents in the primary circuit of PWR type reactors 压水堆一回路事故的快速动态建模 inis-china.atominfo.com.cn 3. The mass velocity effect on the over-temperature protection limit in PWR reactors 压水堆中质量速度对过热保护限的影响 inis-china.atominfo.com.cn 4. 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 www.ilib.cn 5. Experimental Study on Heat Transfer Characteristic of T-Junction in Cooling System of PWR 压水堆主系统T型三通管传热实验研究 www.ilib.cn 6. Modeling and Analysis of Full Scope Simulation System for PWR Power Unit 压水堆核电机组全仿真系统建模与分析 www.ilib.cn 7. Reliability and Safety of Steam-Generator of PWR Nuclear Power Plant 压水反应堆核电厂的蒸汽发生器的可靠性及安全性 service.ilib.cn 8. Real-Time Simulation and Safety Analysis Code for the PWR Core 压水堆堆芯安全分析程序实时仿真的分析研究 ilib.cn 9. Proposals for nuclear data activities from PWR core design 堆芯设计核数据活动的建议 inis-china.atominfo.com.cn 10. 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 www.ilib.cn 1. Subcriticality measurements in PWR spent fuel pit PWR 堆乏燃料贮存池次临界状态测量 inis-china.atominfo.com.cn 2. Safety Analysis Code for Multi-Region, Multi-Node and Multi-Type PWR Core 多区变节点压水堆堆芯通用安全分析程序的研制 www.ilib.cn 3. Research on Uncertainty of Design Parameters for PWR Fuel Rod 压水堆燃料棒设计参数不确定性研究 www.ilib.cn 4. Radiation risk analysis of tritium in PWR nuclear power plant 压水堆核电站中氚的辐射风险分析 inis-china.atominfo.com.cn 5. Development of New Cladding Materials for PWR Fuel Element in France 法国压水堆燃料元件新一代包壳材料的发展 service.ilib.cn 6. A formula of neutron multiplication during actual process of start-up of PWR 反应堆实际提棒的中子倍增公式 service.ilib.cn 7. Issues for Special Attention in Design of PWR Structure 压水堆结构设计中应注意的问题 www.ilib.cn 8. Analysis of Heat Transfer of U-Shaped Tube for PWR Steam Generator 蒸汽发生器U型管换热特性分析 service.ilib.cn 9. Heat transfer tube material of PWR steam generator 压水堆蒸汽发生器传热管材料 ckrd.cnki.net 10. Halden In-Reactor Test to Exhibit PWR Axial Offset Anomaly 展示压水堆轴向偏移异常的哈顿反应堆堆内试验 inis-china.atominfo.com.cn 1. Key Issues in Life Management of PWR Reactor Internals 压水堆堆内构件寿命管理中的关键问题 service.ilib.cn 2. STEERING ANGLE SENSOR FR WIN PWR SUPPLY RH ICE HEAD UNIT PWR SUPPLY 方向盘转角传感器前右车窗电源音响主机电源提供 wenku.baidu.com 3. Research of Fuzzy Control of PWR Nuclear Power System 压水堆核动力系统模糊控制研究 service.ilib.cn 4. MISAP Code Validation for the Passive Residual Heat Removal System of Advanced PWR 先进堆非能动余热排出系统MISAP程序验证分析 www.ilib.cn 5. Research Progress on Passive Safety System of Advanced PWR 先进压水堆非能动安全系统研究进展 www.ilib.cn 6. Design rules for mechanical components of pwr nuclear islemds 压水堆核电厂核岛机械设备设计规范 blog.globalimporter.net 7. Water Vapor Quality in Secondary Circuit of PWR 压水堆核电站二回路的水汽质量 service.ilib.cn 8. Virtual Simulation of Operation and Control of PWR Based on High Level Architecture 基于高层体系结构的压水堆运行控制虚拟仿真 www.ilib.cn 9. The traveller: a new look for PWR fresh fuel packages 旅行者：对压水堆新燃料包装容器的新探求 inis-china.atominfo.com.cn 10. Research on Design Criteria for PWR Fuel Rod 压水堆燃料棒若干设计准则的研讨 www.ilib.cn 1. Selection of Emergency Release Source Term and Partition of EPZ in the Chinese PWR NPP 压水堆核电站应急源项的选定和应急计划区的划分 www.ilib.cn 2. Guide to design of nuclear fuel rods for PWR 压水堆核燃料棒设计导则 blog.globalimporter.net 3. Virtual Simulation of Pressurizer of Marine PWR Based on Vega 基于Vega的船用压水堆稳压器的虚拟仿真 www.ilib.cn 4. Periodic Safety Review of PWR 压水堆定期安全审评 www.chinanuclear.cn 5. Development of Nuclear Fuel Element for PWR in China 我国压水堆核电燃料元件的发展 service.ilib.cn |
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