Multi-objective optimization of helical coil steam generator in high temperature gas reactors with genetic algorithm and response surface method

Jinxiang Sun, Ruibo Zhang, Mingjun Wang, +4

Energy

Response Surface MethodEngineeringEnergy EfficiencyMechanical EngineeringGenetic Algorithm +5

A deep-learning reduced-order model for thermal hydraulic characteristics rapid estimation of steam generators

Shaopeng He, Mingjun Wang, Jing Zhang, +3

International Journal of Heat and Mass Transfer

Nonlinear System IdentificationReduced Order ModelingEngineeringMachine LearningThermal Hydraulics +8

Theoretical research on two-phase flow instability in parallel channels

Y.J. Zhang, G.H. Su, X. B. Yang, +1

Nuclear Engineering and Design

Unsteady FlowEngineeringTwo-phase FlowFluid MechanicsFlow Physic +4

A sub-channel analysis code for advanced lead bismuth fast reactor

Jun Wang, Wenxi Tian, G.H. Su, +1

Progress in Nuclear Energy

Electrical EngineeringEngineeringNuclear EngineeringReactor PhysicsSub-channel Analysis Code +2

Code development and analysis on the operation of liquid metal high temperature heat pipes under full condition

Chenglong Wang, Jinlu Huang, Kailun Guo, +5

Annals of Nuclear Energy

EngineeringLiquid Metal CoolingHeat ExchangerMechanical EngineeringThermal Management +7

HEART, a specific code for thermal-electrical analysis of heat pipe cooled nuclear reactor

Zeqin Zhang, Chenglong Wang, Kailun Guo, +4

International Journal of Thermal Sciences

Specific CodeEngineeringNuclear Reactor EngineeringNuclear SafetyComputer Engineering +8

Experimental investigation of pressure fluctuation and steam transport under SGTR accident in Lead-cooled Fast Reactors

Qifan Yu, Yuliang Fang, Yafeng Zhao, +5

International Journal of Heat and Mass Transfer

EngineeringThermal HydraulicsReactor SafetySteam TransportHeat Transfer +5

Experimental study on sodium Screen-Wick heat pipe capillary limit

Yugao Ma, Hongxing Yu, Xueqing Wang, +8

Applied Thermal Engineering

EngineeringHeat Transfer EnhancementExperimental StudyThermodynamicsHeat Transfer +2

An experimental review of steam generator tube rupture accident in lead-cooled fast reactors: Thermal-hydraulic experiments classification and methods introduction

Qifan Yu, Suizheng Qiu, Chenglong Wang, +3

Progress in Nuclear Energy

EngineeringThermal HydraulicsLead-cooled Fast ReactorsReactor SafetyThermal-hydraulic Experiments Classification +3

Development of a thermal-hydraulic analysis code for CARR

Wenxi Tian, Suizheng Qiu, Yuting Guo, +2

Annals of Nuclear Energy

Core Thermal HydraulicsEngineeringThermal HydraulicsCalibrationThermal Analysis +7