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8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety.

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1.Verification of Void Fraction Conversion Methodology by means of Differential Pressure Measurement during the Steam Explosion in the TROI Experiment

机译：在TROI实验中通过蒸汽爆炸过程中的压差测量来验证空隙率的转换方法
- 作者：S.H. Hong;K.S. Ha;J.H. Kim;S.W. Hong
- 会议名称：《8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety.》 | 2010年
- TROI;
- Steam Explosion;
- Void Fraction;
2.Preliminary Experimental and Numerical Assessment of a Secondary Scram System for Liquid Metal Cooled Reactors.

机译：液态金属冷却反应堆二级Scram系统的初步实验和数值评估。
- 作者：S. Vanmaercke;G. Van den Eynde;E. Tijskens;Y. Bartosiewicz
- 会议名称：《8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety.》 | 2010年
- scram system;
- liquid metal;
- DEM;
3.Numerical Calculations for Steam-Water CCFL Tests Using the 1/3rd Scale Rectangular Channel Simulating a PWR Hot Leg

机译：使用1/3比例矩形通道模拟压水堆热腿的蒸汽CCFL试验的数值计算
- 作者：Ikuo Kinoshita;Michio Murase;Yoichi Utanohara;Dirk Lucas;Christophe Vallée;Akio Tomiyama
- 会议名称：《8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety.》 | 2010年
- reflux condensation;
- PWR hot leg;
- countercurrent flow;
- steam-water experiment;
- numericalcalculation;
4.Argon Entrainment into Liquid Sodium in Fast Breeder Reactor

机译：快速繁殖反应器中氩气夹带进入液态钠
- 作者：A.W. Patwardhan;R.G. Mali;S.B. Jadhao;K.D. Bhor;G. Padmakumar;G. Vaidyanathan
- 会议名称：《8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety.》 | 2010年
- Gas entrainmsent;
- Turbulent kinetic energy;
- Re-submergence;
- Stirred tank;
- Vortex formation.ssw;
5.Investigation of Heat Transfer for Fluid Flow through Porous Media: Application to a Pebble-Bed Reactor

机译：多孔介质中流体流动的传热研究：在卵石床反应器中的应用
- 作者：Xiaoyu CAI;Suizheng QIU;Guanghui Su;Wenxi Tian
- 会议名称：《8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety.》 | 2010年
- Pebble-bed reactor;
- porous media;
- void fraction;
- heat transfer;
- pressure drop;
6.MSIV COMPARTMENT PRESSURE RESPONSE TO MSLB WITH TMD CODE

机译：使用TMD代码对MSLB的MSIV隔室压力响应
- 作者：ZHANG Guosheng
- 会议名称：《8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety.》 | 2010年
- TMD;
- Compartment;
- MSLB;
- Pressure response;
7.Numerical Study on Flow Distribution and Turbulent Flow in XT-ADS Rod Bundle Water Experiment

机译：XT-ADS棒束水实验中流量分布和湍流的数值研究
- 作者：A. Batta;A. Class;K. Litfin;T. Wetzel
- 会议名称：《8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety.》 | 2010年
- Fuel assembly;
- spacer;
- bundle flow;
- ADS;
8.Prediction Analyses of Feedwater System Transients in Lungmen Nuclear Power Plant Startup Tests with PCTRAN

机译：PCTRAN在龙门核电站启动测试中给水系统瞬态的预测分析
- 作者：Wei-Xiang Zhuang;Chunkuan Shih
- 会议名称：《8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety.》 | 2010年
- Feedwater system transient analysis;
- PCTRAN;
- ABWR;
- Lungmen Nuclear Power Plant;
9.Flow Distribution in the Inlet Plenum of Steam Generator

机译：蒸汽发生器入口进气口的流量分布
- 作者：A. W. Patwardhan;L. T. Patil;H. P. Khadamakar;G. Padmakumar;G. Vaidyanathan
- 会议名称：《8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety.》 | 2010年
- Steam Generator;
- Flow Distribution;
- Flow Distribution Devices;
- CFD;
10.LOFA Analysis of a Modified Liquid-metal Cooled Thermionic Reactor:TOPAZ-II

机译：改性液态金属冷却热离子反应器：TOPAZ-II的LOFA分析
- 作者：Hu Gu;Zhao Shouzhi
- 会议名称：《8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety.》 | 2010年
- TOPAZ-II;
- LOFA;
11.An Experimental Study on Boiling and Flow Phenomena in External Reactor Vessel cooling

机译：反应釜外部冷却中沸腾和流动现象的实验研究
- 作者：Yongchun LI;Yanhua YANG;Weihua ZHOU;Bo KUANG;Xu CHENG
- 会议名称：《8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety.》 | 2010年
- ERVC;
- boiling phenomena;
- REPEC test facility;
- natural circulation;
12.Evaluation on Spray System Effect of Ling’ao II NPP during Large

机译：临高II核电厂大型喷雾系统效果评价。
- 作者：Xingguan HUANG;Yanhua YANG
- 会议名称：《8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety.》 | 2010年
- Spray system;
- Ling’ao II;
- Steam;
- LOCA;
- Hydrogen safety;
- GASFLOW;
13.Optimization of Multilayer Fuel Assemblies for Supercritical Water-Cooled Reactors with Mixed Neutron Spectrum

机译：具有混合中子谱的超临界水冷堆多层燃料组件的优化
- 作者：Ting YANG;Xiaojing LIU;Xu CHENG
- 会议名称：《8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety.》 | 2010年
14.TRACE Analysis of Feedwater Pump Trip Event for Lungmen ABWR

机译：龙门ABWR给水泵跳闸事件的TRACE分析
- 作者：Jong-Rong Wang;Hao-Tzu Lin;Wei-Chen Wang;Chunkuan Shih
- 会议名称：《8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety.》 | 2010年
- TRACE;
- Lungmen;
- ABWR.;
15.FIRE WATER PERFORMANCE AS A SEVERE ACCIDENT MANAGEMENT MEASURE IN THE STATION BLACKOUT ACCIDENT

机译：消防性能作为车站停电事故中的重大事故管理措施
- 作者：Te-Chuan Wang;Lang-Chen Wang;Show-Chyuan Chiang
- 会议名称：《8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety.》 | 2010年
- Fire Water;
- Station blackout;
- MAAP5;
16.Design and Calibration of Instrumentation and Equipment for Molten Salt Facility

机译：熔盐设施仪器设备的设计与标定
- 作者：James Ambrosek;Nicholas Kuwahara;Mark Anderson;Kumar Sridharan
- 会议名称：《8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety.》 | 2010年
- Convection Coefficient;
- Molten Salt;
- Pressure Drop;
- FLiNaK;
17.Conjugate Heat Transfer to Supercritical Water Wire-Wrapped Rod

机译：将热量传递给超临界水绕线棒
- 作者：Yu Zhu;Eckart Laurien
- 会议名称：《8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety.》 | 2010年
- Conjugate heat transfer;
- Wire-wrapped rod;
- Supercritical water;
- Turbulence models.;
18.Analytical Tool for Evaluating Critical Power Ratio of Irradiated Fuel String in NRU Reactor

机译：NRU反应堆中辐照燃料串临界功率比的分析工具
- 作者：L.Q. Yuan;L.K.H. Leung
- 会议名称：《8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety.》 | 2010年
- Thermalhydraulics;
- Critical Power Ratio;
- Critical Heat Flux (CHF);
- Fuel Irradiation;
19.Effects ofWire Spacer Contact and Pellet-Cladding Eccentricity on Fuel Cladding Temperature under Natural Circulation Decay Heat Removal Conditions in Sodium-cooled Fast Reactor

机译：钠冷快堆自然循环衰变除热条件下线间隔接触和球团偏心对燃料包壳温度的影响
- 作者：Norihiro DODA;Hiroyuki OHSHIMA;Hideki KAMIDE;OsamuWATANABE;Yoshiyuki OHKUBO
- 会议名称：《8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety.》 | 2010年
- fast reactor;
- natural circulation;
- decay heat removal;
- core hot spot;
- uncertainty;
20.Study on Thermohydraulics Characteristic of Annular Tube Once-through Steam Generator using compressible model

机译：基于可压缩模型的环形管式直流蒸汽发生器热工水力特性研究
- 作者：Zhangli Wang;Wenxi Tian;Suizheng Qiu;Guanghui Su;Liang Zhao
- 会议名称：《8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety.》 | 2010年
- Annular tuber once-through steam generator;
- compressible fluid model;
- fluid network;
21.EXPERIMENTAL FACILITIES FOR MATERIALS AND THERMODYNAMIC RESEARCH Technological Experimental Circuits

机译：材料和热力学研究技术实验电路的实验设施
- 作者：P. Hájek;R. V(s）olák;M. Ru(z）icková
- 会议名称：《8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety.》 | 2010年
- Experimental research;
- loop;
- materials;
- thermodynamic;
- supercritical;
22.Assessment of the Wall and Interphase Friction Modules in SPACE Code

机译：评估SPACE规范中的壁面和相间摩擦模块
- 作者：B. J. Kim;M. K. Hwang;K. D. Kim;S. W. Lee
- 会议名称：《8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety.》 | 2010年
- SPACE code;
- Wall friction;
- Interfacial friction;
23.Study on the Atmospheric Diffusion Behavior of Radioactive Aerosol under Severe Accident Conditions

机译：严重事故条件下放射性气溶胶的大气扩散行为研究
- 作者：ZHANG Jigang;ZHOU Tao;LI Yang;GUO Miaomiao;Liu Ping
- 会议名称：《8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety.》 | 2010年
- Radioactive Aerosol;
- Atmospheric Diffusion;
- Severe Accident;
24.Surface Heat Flux and Temperature Measurements In Nucleate Pool Boiling

机译：核池沸腾中的表面热通量和温度测量
- 作者：Wei LIU;Kazuyuki TAKASE
- 会议名称：《8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety.》 | 2010年
- Measurement;
- Surface heat flux;
- Surface temperature;
- Nucleate pool boiling;
25.Growing Mechanism of Dendritic Oxide during Sodium Combustion

机译：钠燃烧过程中树状氧化物的生长机理
- 作者：Masahiro Nishimura;Hideki Kamide;Ken-ichiro Sugiyama;Shiro Otake
- 会议名称：《8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety.》 | 2010年
- Sodium;
- FR;
- Combustion;
- Oxidation;
- Dendritic oxide;
26.Prediction Analysis of Turbine Trip/Load Rejection Transients in Lungmen Nuclear Power Plant Startup Tests with PCTRAN

机译：用PCTRAN在龙门核电厂启动测试中对涡轮跳闸/甩负荷瞬态进行的预测分析
- 作者：Pi-hsuan Lai;Chunkuan Shih
- 会议名称：《8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety.》 | 2010年
- PCTRAN;
- Lungmen Nuclear Power Plant;
- turbine trip/load rejection transient analysis;
27.Thermal Responses of a Deep Burn High Temperature Reactor Core

机译：深度燃烧高温反应堆堆芯的热响应
- 作者：Hongbin Zhang;Michael Pope;Haihua Zhao
- 会议名称：《8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety.》 | 2010年
- Deep Burn;
- TRISO;
- RELAP5-3D;
- HPCC;
- LPCC.;
28.The element-free Galerkin method for the unsteady magnetohydrodynamic (MHD) flow in duct with arbitrary wall conductivity

机译：任意壁电导率的管道中非稳态磁流体动力学（MHD）流动的无元素Galerkin方法
- 作者：Xinghui Cai;G. H. Su;Suizheng Qiu;Wenxi Tian
- 会议名称：《》 | 2010年
- The element-free Galerkin method;
- unsteady magetohydrodynamic flow;
29.Fabrication and Design Aspects of High-Temperature Compact Diffusion Bonded Heat Exchangers

机译：高温紧凑型扩散粘结式换热器的制造和设计方面
- 作者：Sai K. Mylavarapu;Xiaodong Sun;Richard N. Christensen;Richard E. Glosup;Raymond R. Unocic
- 会议名称：《8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety.》 | 2010年
- Diffusion bonding;
- Alloy 617;
- Printed-circuit heat exchanger;
- High-temperature test facility;
30.Thermal-Hydraulic Analysis of an Intermediate LOCA Test at the ROSA Facility including Uncertainty Evaluation

机译：ROSA设施中的中间LOCA测试的热工液压分析，包括不确定性评估
- 作者：J. Freixa;T-W. Kim;A. Manera
- 会议名称：《8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety.》 | 2010年
- ROSA;
- TRACE;
- Uncertainty;
- LOCA;
- BEPU;
- PWR;
31.EPZDose, An Evaluation Code for Radioactive Materials Dispersion And Dose Consequences in Nuclear Emergency Situations

机译：EPZDose，核紧急情况下放射性物质扩散和剂量后果的评估代码
- 作者：Yi-Hsiang Cheng;Wei-Cheng Wang;Chia-Ying Chang;Shao-Shuan Chen;Chunkuan Shih
- 会议名称：《8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety.》 | 2010年
32.Study on Graphical Modeling and Simulation for the Secondary Loop of the Chinese 200Mwe HTR-PM

机译：中国200Mwe HTR-PM二次回路的图形建模与仿真研究
- 作者：Zhou Shuyong;Sui Zhe;Ma Yuanle;Li Fu and Shi Lei
- 会议名称：《8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety.》 | 2010年
- High-temperature Gas-cooled Reactor;
- Engineering simulator;
- HTR-PM;
- and Thermodynamicsystem;
33.Detection of Cavitation with Directional Microphone Placed outside Piping

机译：放置在管道外部的定向麦克风的气穴检测
- 作者：Yukinori NAGAYA;Michio MURASE
- 会议名称：《8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety.》 | 2010年
- cavitation;
- power plant;
- pipeline component;
- orifice;
- detection;
- microphone;
34.Numerical Simulations of Cap-bubbly Flows Using Fluent

机译：用Fluent进行泡状流的数值模拟。
- 作者：Xia Wang;Xiaodong Sun
- 会议名称：《8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety.》 | 2010年
35.Quality Assurance for RCM Implementation

机译：RCM实施的质量保证
- 作者：Chen Yu;Wang Qingqing
- 会议名称：《8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety.》 | 2010年
- RCM;
- Reliability-centered Maintenance;
- Quality assurance;
- Implementation;
36.Computational Fluid Dynamic Simulations of Jet Momentum Transport in Liquid Metals

机译：液态金属中射流动量传输的计算流体动力学模拟
- 作者：Lee Tschaepe;O. Omotowa;R. Davis;A. Ruggles;D. Pointer;A. Tokuhiro
- 会议名称：《8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety.》 | 2010年
- COMSOL;
- jet;
- turbulence;
- mercury;
- sodium.;
37.Study of the CPR1000 Containment Over-pressure Fragility Curve and improvement of Containment Filtration and Exhaust System

机译：CPR1000安全壳超压脆性曲线的研究及安全壳过滤排气系统的改进
- 作者：Jiming LIN;Peng CHEN;Shishun ZHANG
- 会议名称：《8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety.》 | 2010年
- Severe accident;
- fragility curve;
- CPR1000;
- Containment Filtration And Exhaust System;
38.New ideas for analyzing transient heat transfer characteristics of pulse reactor

机译：分析脉冲堆瞬态传热特性的新思路
- 作者：Jinfeng PENG;Fuyu ZHAO
- 会议名称：《8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety.》 | 2010年
- Pulse reactor;
- Transient heat transfer;
- System analysis;
39.A FACILITY FOR STEAM-GENERATORS AUTOMATIC PROTECTION OF NPP WITN FAST NEUTRONS REACTORS

机译：带有快速中子反应器的蒸汽发生器自动保护NPP的设备
- 作者：V. M. Poplavskij;S. G. Kaliakin;A. V. Drobyshev;N. S. Grachev
- 会议名称：《8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety.》 | 2010年
40.Development of Tritium Permeation Analysis Code (TPAC)

机译：t渗透分析代码（TPAC）的开发
- 作者：Eung S. Kim;Chang H. Oh;Mike Patterson
- 会议名称：《8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety.》 | 2010年
- Tritium permeation;
- TPAC;
41.Study on a Nuclear Spaceship for Interplanetary Cruise Reactor Thermal-hydraulics Design by using CFD code

机译：利用CFD代码研究核动力飞船用于行星际巡航反应堆热工水力设计
- 作者：Atsurou YOSHIDA;Tadashi NARABAYASHI;Masashi TSUJI
- 会议名称：《8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety.》 | 2010年
- CFD;
- Fast reactor;
- Fluent;
- Spaceship;
- Stirling engine;
42.Severe Accident Management and Research at CGNPC

机译：中广核集团重大事故管理与研究
- 作者：Min Xiao;Shishun Zhang;Jiliang Sun;Jiming Lin
- 会议名称：《8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety.》 | 2010年
- CGNPC;
- Severe Accident;
- Management;
- Research;
43.Thermophysical Properties of Lithium-Lead Eutectic Alloy for Use in Fusion Reactor Safety Analysis

机译：用于聚变反应堆安全性分析的锂铅共晶合金的热物理性质
- 作者：Ming JIN;Yunqing BAI;Yican WU
- 会议名称：《8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety.》 | 2010年