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International topical meeting on nuclear reactor thermal hydraulics

召开年：2015
召开地：Chicago, IL(US)
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1.DEVELOPMENT HEAT TRANSFER CORRELATIONS FOR SUPERCRITICAL CO_2 IN NATURAL CIRCULATION LOOP

机译：自然循环中超临界CO_2的发展传热相关性
- 作者：Guangxu Liu;Yanping Huang;Junfeng Wang
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- Supercritical carbon dioxide;
- natural circulation;
- heat transfer correlation;
- buoyancy;
2.HEAT TRANSFER FROM FINNED SURFACE IN DOWNWARD-FACING SUBCOOLED FLOW BOILING

机译：向下的过冷过流沸腾过程中翅片表面的传热
- 作者：Abdul R. Khan;Nejdet Erkan;Koji Okamoto
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- Heat Transfer;
- Fin;
- Flow Boiling;
3.Experimental and numerical investigation of double wall bayonet tubes performances in pool type integral test facility

机译：池式整体测试装置中双壁刺刀管性能的实验和数值研究
- 作者：D. Rozzia;A. Del Nevo;M. Tarantino
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
4.CFD SIMULATION OF SUPERCRITICAL FLOW AND HEAT TRANSFER IN A THREE ROD WIRE WRAPPED BUNDLE

机译：三杆包裹线束中超临界流动和传热的CFD模拟
- 作者：K. Podila;Y.F. Rao
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- CFD;
- Supercritical flows;
- heat transfer;
- Thermalhydraulics;
- Rod bundles;
5.VESTA Test Facility for Severe Accident Researches at KAERI

机译：KAESTI的严重事故研究的VESTA测试设施
- 作者：Hwan Yeol Kim;Sang Mo An;Jaehoon Jung;Kwang Soon Ha;Jin Ho Song
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
6.Printed Circuit Heat Exchanger Design, Analysis and Experiment

机译：印刷电路换热器的设计，分析和实验
- 作者：Seungjoon Baik;Seong Gu Kim;Seongmin Son;Hyeon Tae Kim;Jeong Ik Lee
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- Supercritical CO_2;
- S-CO_2 Brayton Cycle;
- Printed Circuit Heat Exchanger;
- CFD;
7.SINGLE-PHASE AND TWO-PHASE CFD SIMULATIONS OF THE COOLANT FLOW INSIDE A BRUCE/DARLINGTON CANDU FLOW CHANNEL

机译：布鲁斯/达林顿坎杜流道内冷却剂流的单相和两相CFD仿真
- 作者：F. Abbasian;G. I. Hadaller;R. A. Fortman
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
8.Synthesis of CRUD and its Effects On Pool and Subcooled Flow Boiling

机译：CRUD的合成及其对水池和过冷沸腾的影响
- 作者：Carolyn Coyle;Jacopo Buongiorno;Thomas McKrell;Robert Cohen
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- CRUD;
- boiling heat transfer;
- critical heat flux;
- surface manufacturing;
9.ASSESSMENT OF RELAP5/MOD3.3 FOR SUBCOOLED BOILING, FLASHING AND CONDENSATION IN A VERTICAL ANNULUS

机译：RELAP5 / MOD3.3对垂直环形管道中过冷沸腾，闪烁和冷凝的评估
- 作者：Caleb S. Brooks;William D. Fullmer;Clayton D. Lietwiler
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- RELAP5;
- subcooled boiling;
- flashing;
- condensation;
- validation;
10.EXPERIMENTAL INVESTIGATION ON TRANSIENT HEAT TRANSFER CHARACTERISTICS OF C-SHAPE HEATING ROD BUNDLE USED IN PRHR HX

机译：PRHR HX使用的C形加热棒束瞬态传热特性的实验研究
- 作者：ZHANG Yuhao;LU Daogang;WU Guanghao;DU Zheng
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- C-shaped heating rod bundle;
- PRHR HX;
- transient heat transfer characteristics;
- IRWST;
11.Boiled-up level and boiling two-phase flow dynamics in 5×5 heated rod bundle during boil-off process under atmospheric pressure conditions

机译：5×5加热棒束沸腾过程中大气压条件下沸腾液位和沸腾两相流动动力学
- 作者：Takahiro Arai;Masahiro Furuya;Taizo Kanai;Kenetsu Shirakawa;Yoshihisa Nishi
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- Boiling two-phase flow;
- 5×5 heated rod bundle;
- void fraction;
- two-phase mixture level;
- boil-off;
12.QUENCHING OF A HEATED ROD: PHYSICAL PHENOMENA AND HEAT TRANSFER

机译：加热棒的淬火：物理现象和传热
- 作者：Arnab Dasgupta;P. P. Kulkarni;G.J. Gorade;D.K. Chandraker;A.K. Nayak;P.K. Vijayan;S.P. Walker
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- Rewetting;
- Quenching;
- Heat-flux;
- Surface temperature;
13.MODELING THE MECHANICAL INTEGRITY OF AIRFOIL PRINTED CIRCUIT HEAT EXCHANGERS

机译：机翼印刷电路换热器的机械完整性建模
- 作者：Ian Jentz;Mark Anderson;Xiaodong Sun
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- Printed Circuit Heat Exchanger;
- Mechanical Integrity;
- Stress Modeling;
14.IMPACT OF FLOW INDUCED VIBRATION ACOUSTIC LOADS ON THE DESIGN OF THE PEACH BOTTOM REPLACEMENT STEAM DRYER

机译：流激振动声负荷对桃底置换蒸汽干燥机设计的影响。
- 作者：David R. Forsyth;Leslie F. Wellstein;Robert C. Theuret;David A. Suddaby;John Rommel;Ken Ainger
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
15.NUMERICAL PREDICTION OF FLOW INDUCED VIBRATIONS IN NUCLEAR REACTOR APPLICATIONS

机译：核反应器应用中流动诱发振动的数值预测
- 作者：E. ter Hofstede;A. Shams;A.H. van Zuijlen
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- Fluid Structure Interaction;
- Nuclear Reactor;
- Computational Fluid Dynamics;
- Strong Coupling;
16.Heat Transfer Origin of Thermal Shock Fracture and its Application for LWR Fuel during Reflood

机译：热冲击断裂的传热起源及其在LWR中的应用
- 作者：Youho Lee;Hee Cheon NO
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- Thermal shock;
- Fuel safety;
- Quenching;
- Thermal-hydraulic - mechanical coupling;
- 10 CFR 50.46;
17.THERMAL CYCLING TESTING OF DISTRIBUTED FIBER OPTIC TEMPERATURE SENSORS FOR HIGH-TEMPERATURE APPLICATIONS

机译：高温应用中的分布式光纤温度传感器的热循环测试
- 作者：Darius D. Lisowski;Craig D. Gerardi;Steve W. Lomperski
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- Distributed fiber optic sensor;
- Rayleigh scattering;
- temperature sensor;
- coating;
- stability;
18.EUROPEAN OUTLOOK FOR LMFR THERMAL HYDRAULICS

机译：LMFR热液压欧洲展望
- 作者：F. Roelofs;A. Shams;J. Pacio;V. Moreau;P. Planquart;K. van Tichelen;I. Di Piazza;M. Tarantino
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- Liquid Metal;
- Fast Reactor;
- Thermal-hydraulics;
19.CFD ANALYSIS OF FLOWING FIELD IN 5×5 ROD BUNDLE WITH MULTI-GRIDS

机译：多网格5×5杆束流场的CFD分析
- 作者：J.B. Zhao;X.Y. Zhang;L. Qiao
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- 5×5 rod bundle;
- multi-grids;
- CFD analysis;
- flow field;
- heat transfer;
20.VALIDATION TEST PLAN OF A CANDU-6 MODERATOR TANK SCALED-DOWN TEST FACILITY

机译：CANDU-6调节器储罐简化测试设施的验证测试计划
- 作者：Bo W. Rhee;Hyoung T. Kim;Michael D. Atkins;Tongbeum Kim
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- Validation test plan;
- CANDU-6;
- Moderator circulation;
- Scaling analysis;
- Scaled-down test facility;
- CFD analysis;
21.ANALYSIS OF METAL VESSEL WALL ABLATION EXPERIMENT WITH HIGH TEMPERATURE LIQUID BY MPS METHOD

机译：MPS法分析高温液体容器壁烧蚀实验
- 作者：Daisuke Masumura;Yoshiaki Oka;Akifumi Yamaji;Masahiro Furuya
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- severe accident;
- ablation;
- particle method;
- the MPS method;
- stratification;
22.FCI TEST RESULTS UNDER CONDITIONS OF PARTIALLY FLOODED CAVITY AND FLOODED REACTOR IN THE TROI

机译：TROI部分充水腔和充液反应器条件下的FCI测试结果
- 作者：S.W. HONG;Y.S Na;S. H. Hong;J. H. SONG
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- FCI;
- Cavity;
- Rector;
- Submerged;
- Free Fall;
23.USE OF CFD TO PREDICT CRITICAL HEAT FLUX IN ROD BUNDLES

机译：使用CFD预测杆束中的临界热通量
- 作者：Z. E. Karoutas;Y. Xu;L. David Smith Ⅲ;P. F. Joffre;Y. Sung
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- CFD;
- CHF;
- LDV;
- Rod Bundle;
- Mixing;
24.COMPREHENSIVE CHARACTERIZATION OF MOTION OF A HELICAL STRUCTURE DUE TO FLOW INDUCED VIBRATION

机译：流动引起的振动的螺旋结构运动的综合表征
- 作者：P.L. Harmon;W.R. Marcum
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- Helix;
- Flow Induced Vibrations;
- Index of Refraction;
- Fluid Structure Interactions;
25.SYMBOLIC DYNAMICS APPLIED IN THE IDENTIFICATION OF FLOW PATTERNS INSIDE TUBE BANKS

机译：符号动力学在管网内部流动模式识别中的应用
- 作者：Alexandre Vagtinski de Paula;Sergio Vicosa Moeller
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- Tube banks;
- turbulent flow;
- symbolic dynamics;
- flow patterns;
26.Concept Design and Thermal-hydraulic Analysis for Helium-cooled ADS

机译：氦冷却ADS的概念设计和热工水力分析
- 作者：Tianji Peng;Zhiwei Zhou;Xuanyu Sheng;Long Gu
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- ADS;
- Helium-cooled;
- Prismatic block core;
- Solid target;
27.DEVELOPMENT OF A THERMAL-MECHANICAL-MATERIAL BEHAVIOR ANALYSIS CODE FOR THE DISPERSION-PLATE-TYPE FUEL

机译：分散板式燃料热力学行为分析代码的开发
- 作者：Yingwei Wu;Qing Lu;Yangbin Deng;Dalin Zhang;Wenxi Tian;Suizheng Qiu;Guanghui Su
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- Dispersion-plate-type fuel;
- thermal-mechanic-material analysis code;
- asymmetric heat transfer;
- blistering;
28.THE FINDINGS OBTAINED DURING THE OECD/NEA BSAF ACTIVITY WITH THE EMPLOYMENT OF THE SAMPSON CODE

机译：加入桑普森法典后，经合组织/新经济和社会事务安全局开展活动期间得出的结论
- 作者：M. Naitoh;M. Pellegrini;A. Takahashi;H. Mizouchi;H. Suzuki;H. Okada
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- Fukushima Daiichi;
- OECD/NEA BSAF;
- SAMPSON;
- Severe Accident;
29.MECHANISTIC MODELING OF TWO-PHASE FLOW AROUND SPACER GRIDS WITH MIXING VANES

机译：混合叶片两相流绕网的力学建模
- 作者：B. M. Waite;D. R. Shaver;M. Z. Podowski
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
30.INTERFACE TRACKING SIMULATIONS OF BUBBLY FLOWS IN THE PWR RELEVANT GEOMETRIES

机译：压水堆相关几何中气泡流动的界面跟踪模拟
- 作者：Jun Fang;Michel Rasquin;Igor A. Bolotnov
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- DNS;
- two-phase bubbly flows;
- subchannel;
31.SPECTRAL ANALYSIS OF THE TURBULENT ENERGY SPECTRUM IN SINGLE AND TWO-PHASE BUBBLY FLOWS IN DIFFERENT GEOMETRIES BASED ON DIRECT NUMERICAL SIMULATION RESULTS

机译：基于直接数值模拟结果的不同几何形状中单相和两相气泡流的湍流能谱的光谱分析
- 作者：C.S. Brown;I.A. Bolotnov
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- DNS;
- Energy spectrum;
- two-phase flow;
- spectral analysis;
32.CTF VALIDATION ACTIVITIES

机译：CTF验证活动
- 作者：T. Blyth;C. Dances;M. Avramova;R. Salko
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- CTF;
- CASL;
- Validation;
33.AN EXPLANATION OF BORAX-1, SPERT-1 AND THE SL-1 ACCIDENT

机译：BORAX-1，SPERT-1和SL-1事故物的解释
- 作者：Robert E. Henry;Michael Epstein;Hans K. Fauske
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- Steam Explosions;
- Rapid Oxidation;
34.SIMULATION OF FARO L-28 AND L-31 TESTS TO ASSESS MOLTEN JET FRAGMENTATION MODELING IN MAAP

机译：FARO L-28和L-31测试的模拟，以评估MAAP中的分段射流碎片建模
- 作者：A. Le Belguet;E. Beuzet;M. Torkhani
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- Jet fragmentation;
- MAAP code;
- FARO experiment;
- MFCI;
- Reactor safety analysis;
35.SIMULATION OF EX-VESSEL MELT JET BREAKUP AND SENSITIVITY ON MODEL PARAMETERS AND ACCIDENT CONDITIONS

机译：模型参数和事故工况下的船外熔喷破裂和敏感性模拟
- 作者：Kiyofumi Moriyama;Hyun Sun Park
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- Severe accident;
- Ex-vessel debris coolability;
- Melt jet breakup;
- Sensitivity analysis;
36.DEVELOPMENT OF TEXAS-V CODE SURROGATE MODEL FOR ASSESSMENT OF STEAM EXPLOSION IMPACT IN NORDIC BWR

机译：北欧BWR蒸汽爆炸影响评估的TEXAS-V代码替代模型的开发
- 作者：D. Grishchenko;S. Basso;S. Galushin;P. Kudinov
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- Severe accident;
- ex-vessel steam explosion;
- sensitivity study;
- surrogate model;
- IDPSA;
- ROAAM+;
37.INITIAL CONDITION EFFECTS ON KELVIN-HELMHOLTZ INSTABILITIES AND DEVELOPMENT OF A ROUND JET

机译：初始条件对开尔文-赫尔莫茨的不稳定性和回合射流的发展
- 作者：Amy B. McCleney;Philippe M. Bardet
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- Turbulence;
- Round Jet;
- Kelvin Helmholtz instabilities;
- Initial Conditions Effects;
- Validation;
38.PULSED INJECTION TRACER MIXING IN ANNULAR LIQUID FILMS

机译：环形液体薄膜中的脉冲式注射跟踪混合
- 作者：A. Saxena;J. Eiholzer;H.-M. Prasser
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- Dryout;
- liquid film;
- annular flow;
- BWR;
- mixing;
39.NUMERICAL SIMULATION OF ANISOTROPIC ABLATION OF SILICEOUS CONCRETE -ANALYSIS OF CCI-3 MCCI EXPERIMENT BY MPS METHOD

机译：硅质混凝土各向异性消融的数值模拟-MPS法分析CCI-3 MCCI实验
- 作者：Xin Li;Akifumi Yamaji
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- MCCI;
- MPS method;
- Siliceous concrete ablation;
- Aggregates;
40.THE ENERGETICS OF COOLANT-BUBBLE-COVERGAS INTERACTIONS ASSOCIATED WITH LMR OUT-OF-REACTOR SOURCE TERM EXPERIMENTS

机译：与LMR反应堆外源项实验相关的冷却液-泡沫-盖层相互作用的能量学
- 作者：John C. Petrykowski;Hamza Mohamed
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- Safety;
- accidents;
- thermalhydraulics;
- extreme events;
41.Typical Accidents Analysis on the Loss of Flow and External Neutron Source Changing Accidents for A 800 MWth ADS

机译：800 MWth ADS流失损失和外部中子源变化事故的典型事故分析
- 作者：Tianyu Lu;Jianqiang Shan;Junli Gou;Bin Zhang;Bo Zhang;Li Ge;Yuan Yuan;Zijiang Yang
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- ADS;
- LOFA;
- reactivity insertion;
- RELAP5;
42.EXPERIMENTAL AND NUMERICAL INVESTIGATIONS OF INTERACTION BETWEEN HEAVY LIQUID METAL AND WATER FOR SUPPORTING THE SAFETY OF LFR GEN. Ⅳ REATOR DESIGN

机译：液态金属与水相互作用以支持LFR发电机安全性的实验和数值研究。 Ⅳ反应器设计
- 作者：A. Del Nevo;N. Giannini;A. Pesetti;N. Forgione
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- Generation Ⅳ;
- HLM-water interaction;
- LIFUS5/Mod2 facility;
- SIMMER-Ⅲ;
43.Experimental and Numerical Study on Heat Transfer of Supercritical Water Flowing Upward in 2×2 Rod Bundles

机译：超临界水在2×2棒束中向上流动的传热实验与数值研究
- 作者：M. Zhao;H.Y.Gu;X.Cheng;H.B.Li;Q.R.Yang
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- Supercritical water;
- heat transfer;
- 2 ×2 rod bundles;
- spacer grids;
44.PRELIMINARY STRUCTURAL ASSESSMENT OF A PRINTED CIRCUIT HEAT EXCHANGER WITH S-SHAPED FINS

机译：带S型鳍的印刷电路换热器的初步结构评估
- 作者：X. Zhang;X. Sun;R.N. Christensen;M. Anderson
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- PCHE;
- GFR;
- S-CO_2 cycle;
- S-shaped fin;
- stress concentration;
- ASME;
45.EXPERIMENTAL AND NUMERIC AL ACTIVITIES IN SUPPORT OF THE DESIGN OF ASTRID SODIUM-GAS HEAT EXCHANGER

机译：实验研究和数值模拟在支持钠盐气体换热器设计中的作用
- 作者：F.Vitillo;X.Jeanningros;L.Cachon;C.Galati;P.Olympio;S. Madeleine
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- PMHE;
- Innovative PMHE;
- CFD;
- ASST model;
- LDV;
- PIV;
- Maldistribution;
- Porous Media;
46.A REVIEW OF AREVA'S EXPERIMENTAL VALIDATION OF STATE-OF-THE-ART SINGLE-PHASE CFD METHODS WITH APPLICATION TO PWR FUEL ANALYSIS AND DESIGN

机译：先进的单相CFD方法在AREVA实验验证中的应用及其在压水堆燃料分析和设计中的应用
- 作者：A. Hatman;A. Chatelain;K. Goodheart;M. Martin;T. Keheley
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- CFD Validation;
- Pressure Loss;
- Hydraulic Force;
- Thermal Mixing;
47.COMPUTATIONAL FLUID DYNAMICS ANALYSIS OF THE FLUID FLOW AND HEAT TRANSFER IN THE CORE BYPASS REGION OF A PWR

机译：压水堆核心旁路区域的流体流动和传热的计算流体动力学分析
- 作者：Clifford I;Vasiliev A;Zerkak O;Ferroukhi H;Pautz A
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- Computational fluid dynamics;
- Core bypass;
- Heat transfer;
48.COMPUTATIONAL FLUID DYNAMICS BENCHMARK USING AP1000~® 1/4-SCALE UPPER HEAD TEST DATA

机译：使用AP1000〜®1/4比例上头测试数据的计算流体动力学基准
- 作者：William L. Moody;Teresa A. Bissett;Yiban Xu;Gregory A. Meyer
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- CFD Benchmark;
- Unsteady RANS;
- Uncertainty analysis;
- Scale model test;
49.ANALYSIS ON ANTICIPATED TRANSIENT WITHOUT SCRAM (ATWS) ACCIDENTS OF THE HTR-10GT

机译：HTR-10GT的无瞬态意外事故的分析
- 作者：Mingang Lang;Yujie Dong
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- HTR-10GT;
- ATWS;
- THERMIX;
- safety;
50.ANALYSES OF LOCAS IN THE PRIMARY HEAT TRANSFER SYSTEM OF THE HELIUM COOLED PEBBLE BED BLANKET CONCEPT

机译：氦冷却卵石床毛毯初始传热系统中的LOCAS分析。
- 作者：Bruno Gonfiotti;Sandro Paci;Dario Carloni;Lorenzo V. Boccaccini
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- HCPB;
- Ex-Vessel LOCA;
- In-Vessel LOCA;
- fusion power plant;
- DEMO;
51.NUMERICAL SOLUTION OF HEAT TRANSFER PROCESS IN A PRISMATIC VHTR CONSIDERING CORE BYPASS AND CROSS FLOW

机译：考虑核心绕过和横流的VHTR中传热过程的数值解
- 作者：Li WANG;Qiusheng LIU;Katsuya FUKUDA
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- VHTR;
- Core bypass flow;
- Cross flow;
- CFD;
- Turbulence model;
52.MODELING OF THE THERMAL HYDRAULICS OF VERY-HIGH-TEMPERATURE REACTORS WITH THE SYSTEM CODE ATHLET

机译：用系统代码运动员对超高温反应器的水力模型进行建模
- 作者：D. von der Cron;H. V. Hristov;A. Seubert
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- VHTR;
- pebble bed;
- prism;
- ATHLET;
- heat conduction;
53.STUDY OF ABNORMAL HEAT TRANSFER DURING FORCED AND NATURAL CONVECTION SCENARIOS IN A PRISMATIC CORE OF A VHTR: NUMERICAL AND EXPERIMENTAL RESULTS

机译：VHTR固有核中强迫和自然对流情况下的异常传热研究：数值和实验结果
- 作者：Francisco I. Valentin;Narbeh Artoun;Ryan Anderson;Masahiro Kawaji
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- Forced convection;
- heat transfer;
- VHTR;
- high temperature gas reactor;
54.IMPROVEMENT AND VALIDATION OF THE WALL HEAT TRANSFER PACKAGE OF RELAP5/MOD3.3

机译：RELAP5 / MOD3.3的壁面传热套件的改进和验证
- 作者：Xiaofei Xiong;Jianqiang Shan;Junli Gou
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- RELAP5/MOD3.3;
- wall heat transfer package;
- code verification;
55.EPRI MAAP5 FUKUSHIMA DAIICHI ANALYSIS

机译：Eh Pri Well P5福岛第一核电站安娜LY S
- 作者：David L. Luxat;Jeff R. Gabor;Richard M. Wachowiak;Rosa L. Yang
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- Fukushima Daiichi;
- severe accident analysis;
- core melt progression;
- MAAP;
56.INTERFACIAL STABILITY IN VERTICAL SWIRLING ANNULAR TWO-PHASE FLOW

机译：垂直涡旋两相流的界面稳定性
- 作者：Li Liu;Bofeng Bai
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- Swirling annular two-phase flow;
- interfacial waves;
- K-H instability;
- stability criterion;
57.RCIC GOVERNING EQUATION SCOPING STUDIES FOR SEVERE ACCIDENTS

机译：严重事故的RCIC指导方程范围研究
- 作者：Kyle Ross;Jeff Cardoni
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- Severe accident;
- reactor core isolation cooling;
- RCIC;
- impulse turbine;
58.Past and Future RD at IRSN on Corium Progression and Related Mitigation Strategies in a Severe Accident

机译：严重事故中IRSN的过去和未来研发工作，涉及珊瑚进程和相关缓解策略
- 作者：Didier Jacquemain;Didier Vola;Renaud Meignen;Jean-Michel Bonnet;Florian Fichot;Emmanuel Raimond;Marc Barrachin
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- In-vessel melt retention;
- fuel-coolant interaction;
- molten core concrete interaction;
- corium cooling;
59.FUKUSHIMA DAIICHI UNIT 1 EX-VESSEL PREDICTION: CORE MELT SPREADING

机译：FUKUSHIMA DAIICHI UNIT 1船外预测：核心融合
- 作者：M. T. Farmer;K. R. Robb;M. W. Francis
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- Fukushima;
- severe accident;
- ex-vessel;
- spreading;
60.CORIUM-RELATED IMPROVEMENTS IN THE EDF VERSION OF MAAP CODE IN THE FRAME OF SEVERE ACCIDENT STUDIES

机译：严重事故研究框架中MAAP代码的EDF版本中与皮质有关的改进
- 作者：E. Beuzet;N. Bakouta;M. Boissavit;F. Haurais;A. Le Belguet;V. Lombard;M. Torkhani
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- MAAP;
- cladding degradation;
- corium stratification;
- FCI;
- MCCI;
- HPME;
61.Core melt stabilization concepts for existing and future LWRs and associated RD needs

机译：满足现有和未来轻水堆以及相关研发需求的核心熔体稳定概念
- 作者：Manfred Fischer;Sevostian V. Bechta;Vladimir V. Bezlepkin;Ryoichi Hamazaki;Alexei Miassoedov
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- Severe accident mitigation;
- LWR;
- core catcher;
62.COMPUTATIONAL MULTI-FLUID DYNAMICS PREDICTIONS OF DNB

机译：DNB的计算多流体动力学预测
- 作者：S. Mimouni
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- DNB;
- critical heat flux;
- boiling flow;
63.FABRICATION AND TESTING OF A HIGH-TEMPERATURE PRINTED CIRCUIT HEAT EXCHANGER

机译：高温印刷电路换热器的制造与测试
- 作者：Minghui Chen;Xiaodong Sun;Richard N. Christensen;Isaac Skavdahl;Vivek Utgikar;Piyush Sabharwall
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- PCHE;
- thermal-hydraulic performance;
- compact heat exchangers;
- VHTR;
- diffusion bonding;
64.CFD Modeling of Sodium-Oxide Deposition in Sodium-Cooled Fast Reactor Compact Heat Exchangers

机译：钠冷快堆紧凑型换热器中氧化钠沉积的CFD模型
- 作者：E. Tatli;J. P. Mazzoccoli;P. Ferroni
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
65.Surrogate spacer grid design for fluid-structure interactions studies in fuel bundles

机译：替代间隔栅设计，用于燃料束中的流固耦合研究
- 作者：Noah A. Weichselbaum;Shadman Hussain;Pierre Korysko;Morteza Rahimi-Abkenar;Philippe M. Bardet;Majid T. Manzari
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- PWR Fuel Assembly;
- Fluid Structure Interaction;
- Particle Image Velocimetry;
- Digital Image Correlation;
66.TOWARDS THE DEVELOPMENT OF A FULL-SCALE TRANSIENT CFD MODEL TO SIMULATE THE STATIC AND DYNAMIC IN-CORE MASS FLUX DISTRIBUTION IN A CLASSICAL GERMAN PWR

机译：旨在建立全瞬态CFD模型以模拟经典德国压水堆中静态和动态的内部磁通量分布
- 作者：Dong-Yuan Sheng;Marcus Seidl
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- PWR;
- vessel CFD;
- pressure drop;
- flow distribution;
- mixing;
67.Experimental Study on Natural Circulation and Gas Injection Enhanced Circulation in KYLIN-Ⅱ Mixed Circulation Loop

机译：KYLIN-Ⅱ混合循环回路自然循环和注气增强循环的实验研究
- 作者：Sheng Gao;Liuli Chen;Kefeng Lv;ChenchongYue;Mariano Tarantino;Qunying Huang;Yican Wu
- 会议名称：《International topical meeting on nuclear reactor thermal hydraulics》 | 2015年
- Lead-Bismuth eutectic coolant;
- Natural circulation;
- LOFA transient;