PWR
美 [.pi d?b(?)lju 'ɑr] 
英 [.pi? d?b(?)lju? 'ɑ?(r)]
- na.Pwr
- 網(wǎng)絡(luò)壓水堆(pressurized water reactor)；電源指示燈；壓水反應(yīng)堆
詞形變化
復(fù)數(shù)：PWRs
英漢解釋
英英解釋
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.
模型對新型壓水堆在穩(wěn)態(tài)自然循環(huán)過程中可能出現(xiàn)的流動形式和換熱狀態(tài)進(jìn)行了充分考慮。
Pratt & Whitney Rocketdyne ( PWR ) is a United States company that designs and produces rocket engines that use liquid propellants.
以下簡稱洛克達(dá)因）是美國的一家主要從事液體燃料火箭發(fā)動機(jī)設(shè)計研發(fā)的公司。
GO methodology was applied to analyze the reliability of PWR purification system with common cause failures.
應(yīng)用GO法分析了共因失效對壓水堆凈化系統(tǒng)可靠性的影響。
This paper presents laboratory research results of cement solidification of borate acid liquid wastes and concentrates arising from PWR.
本文介紹了壓水堆核電站產(chǎn)生的硼酸廢液和濃縮廢液水泥固化的實驗室研究結(jié)果。
An adaptive-cost-function optimal controller design for a PWR nuclear reactor.
壓水堆自適應(yīng)成本函數(shù)最優(yōu)化控制裝置設(shè)計…[中國核科技信息與經(jīng)濟(jì)研究院]。
The results show that the common cause failures greatly affect the reliability of PWR purification system.
結(jié)果表明，共因失效對壓水堆凈化系統(tǒng)可靠性有很大影響。
The departure from nucleate boiling (DNB) is important concerning about the safety of a PWR.
偏離泡核沸騰（DNB）對于壓水堆安全具有重要意義。
Before installing or removing an IF cable, turn off the ODU-PWR power switch on the IF board.
在安裝、拆除中頻電纜前，必須關(guān)閉中頻板的電源輸出開關(guān)。
Furthermore, this article introduces the techniques to ensure the water vapor quality in secondary circuit of PWR .
還介紹了保證壓水堆核電站二回路水汽質(zhì)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.
對壓水堆負(fù)荷跟蹤運行進(jìn)行了研究，提出將一種三維模糊控制系統(tǒng)應(yīng)用于硼濃度自動調(diào)節(jié)的設(shè)計方案。
The author studied on the modeling and simulation of PWR core and its control systems.
本文對壓水堆堆芯及其控制系統(tǒng)進(jìn)行了建模與仿真研究。
PAINTS AND VARNISHES. PAINTS FOR THE NUCLEAR INDUSTRY. TEST OF BEHAVIOUR IN IONISING RADIATIONS (PWR).
核工業(yè)涂料.受電離輻射時狀態(tài)的試驗（壓水反應(yīng)堆）
Control rods are used in a PWR typically to change the power level and also to shut down the reactor.
控制棒是在一個加壓水冷卻反應(yīng)堆里使用的，用來改變能量的級別，也可以用來停止反應(yīng)堆。
Plutonium recycling in a fuel-MOX 900-NW(e) PWR: physical analysis of accident behaviors.
钚在900兆瓦（電）全混合氧化物燃料壓水堆中的再循環(huán)：事故行為物理分析…[中國核科技信息與經(jīng)濟(jì)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.
影響系統(tǒng)操作完整性的錯誤，如已檢測到的地址奇偶錯，或者無效的PWR_GOOD信號。
Now typically in a PWR this is typically a configuration for a PWR.
現(xiàn)在在壓水式反應(yīng)堆里，這是個典型的，結(jié)構(gòu)，對一個壓水式反應(yīng)堆來說。
This paper first looks back to vary control programs and the development of control system of pressurized water reactor (PWR).
本文首先回顧了國內(nèi)外壓水堆的各種控制方案以及控制系統(tǒng)得發(fā)展現(xiàn)狀。
The 300 MW PWR unit is the first nuclear power station designed and built in China.
我國自行設(shè)計制造的第一座核電站為30萬千瓦壓水堆核電站。
RCP leak rate is a quite important parameter in PWR for its radioactivity, which is required to be calculated every day.
一回路冷卻劑的泄漏率是壓水堆核電廠放射性控制相關(guān)的一個重要物理量，需要定期進(jìn)行監(jiān)測。
Computer simulation of PWR nuclear power station's liquid ejections around the sea area and statistics analysis of the inspected data
核電站液態(tài)流出物在受納海域中分布的計算機(jī)模擬和監(jiān)測數(shù)據(jù)統(tǒng)計分析
Prediction of flow induced damping of a PWR fuel assembly in case of seismic and LOCA load case PWR
堆燃料組件在地震和冷卻劑喪失情況下流動誘導(dǎo)衰減預(yù)測
The Accidents Mitigation Concept of French PWR Nuclear Power Plant
法國壓水堆核電廠事故緩解對策
Specific Radioactivity Produced by the Secondary Charged Particle Nuclear Reaction in the Primary Circuit Water of PWR
壓水反應(yīng)堆一回路水中二次帶電粒子核反應(yīng)產(chǎn)物的比活度
Microcomputer simulation of the centrality parameter modeling for PWR nuclear power plant reactor core
壓水堆核電站堆芯集中參數(shù)模型的微機(jī)仿真
Research on Economy Quantitative Analysis Theory for the Secondary-Circuit of PWR Nuclear Cogeneration Plant
熱電聯(lián)產(chǎn)壓水堆機(jī)組二回路經(jīng)濟(jì)性定量分析理論的研究
Design for Improving Operational Sequence of Granulation and Compression in Production of Elements for PWR Nuclear Power Station
壓水堆核電站元件生產(chǎn)制粒、壓制工序改進(jìn)設(shè)計
A Computer Code for Calculating Initial Temperature Distribution of Instrumented Fuel Element for PWR in Pile Experiment
壓水堆堆內(nèi)試驗儀表化燃料元件初始溫度分布計算程序
Characterization of Decommissioned PWR Vessel Internals Material Samples: Tensile and SSRT Testing (Non proprietary Version)
退役的壓水堆容器內(nèi)部構(gòu)件材料樣本描述：拉伸和慢應(yīng)變速率試驗（非專有版）
Experiments and CFD calculations on coolant mixing in PWR - Application to boron dilution transient analysis
壓水堆中冷卻劑混合的試驗和計算流體動力學(xué)計算
PC-Based Simulation of the Centrality Parameter Modeling for PWR Nuclear Power Plant Reactor Core
壓水堆核電站運行堆芯物理過程的PC仿真
Analysis of mechanisms induced by sliding and corrosion: dedicated apparatus for PWR environments
滑動和腐蝕引發(fā)的機(jī)理分析：壓水堆環(huán)境下專用設(shè)備
Research on Coolant Flow Governing Methods for Marine PWR Nuclear Power Plant under Ideal Steady-state Programming
船用壓水堆核動力裝置雙恒定運行方案下的冷卻劑流量調(diào)節(jié)方案
Application of Nonlinear Iteration Semi-analytical Nodal Method in the PWR Fuel Management Calculation
非線性迭代半解析節(jié)塊方法在壓水堆燃料管理計算中的應(yīng)用
Effect of yield strength on stress corrosion crack propagation under PWR and BWR environments of hardened stainless steels
壓水堆和沸水堆環(huán)境下淬火不銹鋼屈服強(qiáng)度對應(yīng)力腐蝕裂紋擴(kuò)展影響
Development of A Compact Severe Accident Simulator for PWR Nuclear Power Plants
壓水堆核電站嚴(yán)重事故緊湊型仿真機(jī)開發(fā)
Comprehensive Control of PWR Pressurizer Using Typical Fuzzy Controllers
采用典型模糊控制器實現(xiàn)壓水堆穩(wěn)壓器的綜合控制
Metallographic examination for weld seam of nuclear fuel rod used in PWR
壓水堆核燃料棒焊縫金相檢驗
Modal testing and identification of a PWR fuel assembly PWR
堆燃料組件的模式化試驗與驗證
Aging problems and life evaluation for the key metallic components in PWR nuclear power plant
壓水堆核電廠關(guān)鍵金屬部件的老化和壽命評估
Development of the Method and Code System for Three Dimension Hexagonal PWR Core Fuel Management Calculation
三維六角形組件壓水堆堆芯燃料管理計算及程序系統(tǒng)研究
