1)Thermal-hydraulic热工水力
1.Core physic models of the thermal-hydraulic operation analysis program for nuclear power plant;核动力装置热工水力运行分析程序中的堆芯物理模型
2.By founding the fuel salt model and graphite model respectively,the steady thermal-hydraulic characteristics of this Molten Salt Reactor core was simulated by numerical method.针对第四代国际核能论坛提出的新概念熔盐堆堆芯的具体特点,采用DRAGON程序计算了堆芯轴向和径向功率分布因子,并对熔盐堆的燃料盐和石墨慢化剂分别建立数学模型,通过数值方法对新概念熔盐堆的稳态热工水力特性进行了模拟。
3.A multi-channel model steady-state thermal-hydraulic analysis code was developed for China Advanced Research Reactor(CARR).针对中国先进研究堆(CARR)的具体特点开发了堆芯多通道热工水力计算程序ECARR。
英文短句/例句
1.In the experimental research of reactor thermohydraulic behavior on test facility, an electric heater is always used instead of a nuclear reactor.在利用热工水力台架进行反应堆热工水力研究时，一般采用电加热代替核释热。
2.GNPS 18-Months Fuel Cycles Core Thermal Hydraulic Design大亚湾核电站18个月换料堆芯热工水力设计
3.Development of Steady-State Thermal Hydraulic Analysis Code for Rectangle Channel Core矩形通道堆芯稳态热工水力分析程序的开发
4.Numerical Simulation on the Thermal-hydraulic Phenomena in the Fast Reactor Using MPS Method基于粒子法的快堆热工水力学现象的数值模拟
5.Thermal-Hydraulic Calculation and Test for Irradiation Target Assembly同位素辐照组件热工水力计算与试验研究
6.Development and Validation of Thermal-Hydraulic and Safety Analysis Code for CARR (TSACC)CARR热工水力与安全分析程序TSACC的开发与验证
7.Status and Trends of Thermal-Hydraulic System Codes for Nuclear Power Plants With Pressurized Water Reactors压水堆核电站热工水力系统程序的研发现状与趋势
8.Study about Thermal Hydraulic Static Characteristics Calculation of Nuclear Steam Generator;核电蒸汽发生器热工水力稳态特性计算分析研究
9.Simulation and Application about Hydraulic and Thermal Characteristic in Tidal Area;潮汐水域水力热力特性的模拟及工程应用
10.The interactional condition of district heating system and hot water supply system are analyzed.分析集中供热管网与热水供应热用户水力或热力工况变化时的相互影响规律。
11.A practical BWR thermal-hydraulic model has been introduced.本文介绍了一个实用的沸水堆热工一水力模型。
12.A THERMAL-HYDRAULIC MODEL FOR BWR SIMULATORS沸水堆堆芯模拟程序中的热工-水力模型
13.The Analysis of Hydraulic Condition in Indoor Hot Water Heat-Supply System;跨越式室内热水供暖系统水力工况分析
14.Numerical analysis of moisture,thermal and mechanical states for subway double-line tunnel constructed by artificial freezing method地铁双线隧道施工人工冻结水热力数值分析
15.Study on Structural Techniques of the Sealing Plate;热水器压力罐不锈钢压盖的结构工艺性研究
16.Hydraulic Conditions Experimental Study and Simulation of Ring-shaped Heat-supply Network with Multi-heat Sources;多热源环状管网水力工况的实验研究与仿真
17.Temperature and thermal stress analysis in membrane wall gasifier under varied work conditions水冷壁气化炉变工况温度及热应力分析
18.Actual Measurement of Hydraulic Regime of a Secondary Circuit and Scheme for Energy-saving Reconstruction某二级热网水力工况实测与节能改造方案
相关短句/例句
Thermohydraulics热工水力
1.A program using the FORTRAN77 language is developed; it makes use of many models including those for thermohydraulics, heat transfer, properties of fluid and solid and the core.介绍了一体化核动力装置的特点；建立了一套完整的数学物理模型，包括堆芯模型、基本的热工水力模型、传热学模型、计算方法模型、物性模型及辅助模型等；分析了一体化核动力装置的热工水力特性，根据模型编制了程序，经过实堆计算及ＲＥＴＲＡＮ０２ 验证，证明程序是正确、实用的；最后给出了程序的算例。
2.Major achievements in the area of thermohydraulics, nuclear fuel,peobabilistic safety assessment and severe accident researches are summarized.对在热工水力、核燃料、概率安全评估和严重事故研究领域中的主要成果，作了简要小结。
3)Thermal hydraulic热工水力
1.For the vertical U-tube natural circulation steam generator in nuclear power plant,the mathematical physical models and calculating code to predicate the thermal hydraulic behaviour are established.针对核电站立式U形管自然循环蒸汽发生器,建立了能够描述其稳态及瞬态热工水力特性的数学物理模型,并编制了计算程序。
2.For the vertical U-tube natural circulation steam generator in marine nuclear power plant,the mathematical physical models and calculating code to predicate the thermal hydraulic behaviours are established.针对船用立式U形管自然循环蒸汽发生器,建立了能够描述其稳态及瞬态热工水力特性的数学物理模型,并编制了计算程序。
4)Thermal-hydraulics热工水力
5)thermal-hydraulics热工水力学
1.Based on the structure design and the results of the neutronics calculation, the thermal-hydraulics design scheme on the Dual-cooled Lithium-Lead (DLL) Breeder Blanket for the fusion power reactor (named FDS-Ⅱ) is presented.依据结构设计和中子学计算结果给出了聚变发电反应堆FDS-Ⅱ双冷锂铅(DLL)包层热工水力学设计方案。
6)thermodynamics and hydraulic analysis热工水力分析
延伸阅读
反应堆稳态热工水力设计反应堆稳态热工水力设计reactor steady state ther-mo-hydraulic design fonyingdul wentol regong shL一l一she一l反应堆稚态热工水j7设计(reaetor steadystate thermohydraulie design)根据安全和经济适用的原则确定一个优化的堆芯冷却方案，分析计算反应堆在各种给定的稳态工况下的热工参数。其中包括堆芯冷却剂压力、温度及流量分布、燃料元件温度和偏离泡核沸腾比等参数。 并联通道模型反应堆堆芯是由许多结构类同的嫌料组件组成的。几种典型的嫌料组件被表示在图1“墙”，相邻通道间有流体的横向流动和混流交混，因此，在通道之间有质量、动量及能量交换。 在反应堆稳态热工水力设计中，要计算堆芯各类有束伸控制的 嫩料组件一~一一2、‘~一一.嗽料棒冷却剂通遭、一~一丫/ 无束捧控制 的姗料组件一测口陈水堆组月沸水堆组件高温气冷堆组件 图1反应堆燃料组件中。在反应堆热工水力分析中，把堆芯按其热流密度和通道内详细的热工参数。堆芯最高燃料温度及最小偏离泡核沸腾比等参数必须满足安全准则的要求。设计中运用了下述术语:①平均通道:具有平均热流密度、平均冷却剂流量、焙升和名义几何参数的通道，②热通道:堆芯内具有最大焙升的燃料冷却剂通道，它是合理地集中了核的和工程的诸不利因素影响的通道;③热通道因子:通道的局部状态和平均状态的参数比值。
