PWR
美 [.pi dʌb(ə)lju 'ɑr] 
英 [.piː dʌb(ə)ljuː 'ɑː(r)]
- na.Pwr
- 网络压水堆(pressurized water reactor)；电源指示灯；压水反应堆
词形变化
复数：PWRs
英汉解释
英英解释
例句
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。
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。
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。
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。
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]。
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。
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。
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。
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。
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。
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。
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）
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。
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]。
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。
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。
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。
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。
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。
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
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
The Accidents Mitigation Concept of French PWR Nuclear Power Plant
法国压水堆核电厂事故缓解对策
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
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
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
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
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
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）
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
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
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
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
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
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
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
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
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
Modal testing and identification of a PWR fuel assembly PWR
堆燃料组件的模式化试验与验证
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
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
