Guang-hui Su

Guang-hui Su's AcademicInfluence.com Rankings

Guang-hui Su

Engineering

#7107

World Rank

#8469

Historical Rank

Mechanical Engineering

#700

World Rank

#754

Historical Rank

Applied Physics

#2390

World Rank

#2431

Historical Rank

engineering Degrees

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Engineering

Guang-hui Su's Degrees

PhD Mechanical Engineering National Taiwan University
Masters Mechanical Engineering National Taiwan University
Bachelors Mechanical Engineering National Taiwan University

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Guang-hui Su's Published Works

Number of citations in a given year to any of this author's works

Total number of citations to an author for the works they published in a given year. This highlights publication of the most important work(s) by the author

Published Works

Experimental and theoretical study on single-phase natural circulation flow and heat transfer under rolling motion condition (2009) (135)
Applications of ANNs in flow and heat transfer problems in nuclear engineering: A review work (2013) (102)
Numerical investigation on coalescence of bubble pairs rising in a stagnant liquid (2011) (101)
Effects of turbulence models on forced convection subcooled boiling in vertical pipe (2015) (82)
Heat transfer model of single-phase natural circulation flow under a rolling motion condition (2009) (77)
Analysis of safety margin of in-vessel retention for AP1000 (2010) (71)
Study on the characteristics of the sodium heat pipe in passive residual heat removal system of molten salt reactor (2013) (63)
Thermal hydraulic phenomena related to small break LOCAs in AP1000 (2011) (62)
Two-phase bubbly flow simulation using CFD method: A review of models for interfacial forces (2020) (62)
Review of conceptual design and fundamental research of molten salt reactors in China (2018) (61)
Research on the designed emergency passive residual heat removal system during the station blackout scenario for CPR1000 (2012) (57)
Experimental study on two-phase flow instability of natural circulation under rolling motion condition (2009) (57)
Flow blockage analysis of a channel in a typical material test reactor core (2009) (54)
Theoretical investigations on two-phase flow instability in parallel multichannel system (2008) (54)
Natural convection heat transfer in corium pools: A review work of experimental studies (2015) (54)
Numerical investigation on bubble dynamics during flow boiling using moving particle semi-implicit method (2010) (52)
A Review on Analysis of LWR Severe Accident (2015) (52)
Numerical research on thermal mixing characteristics in a 45-degree T-junction for two-phase stratified flow during the emergency core cooling safety injection (2019) (49)
Thermal hydraulic and stress coupling analysis for AP1000 Pressurized Thermal Shock (PTS) study under SBLOCA scenario (2017) (49)
Experimental investigation on nanofluid flow boiling heat transfer in a vertical tube under different pressure conditions (2016) (49)
Numerical simulation and optimization on valve-induced water hammer characteristics for parallel pump feedwater system (2008) (47)
Theoretical research on two-phase flow instability in parallel channels (2009) (47)
Simulation and analysis on 10-in. cold leg small break LOCA for AP1000 (2012) (46)
Preliminary evaluation of U3Si2-FeCrAl fuel performance in light water reactors through a multi-physics coupled way (2018) (45)
CFD investigation on thermal-hydraulic behaviors of a wire-wrapped fuel subassembly for sodium-cooled fast reactor (2018) (44)
Development of a safety analysis code for molten salt reactors (2009) (44)
Performance analysis of heat pipe radiator unit for space nuclear power reactor (2017) (43)
Experimental investigations on single-phase convection and steam-water two-phase flow boiling in a vertical rod bundle (2017) (43)
Transient behavior of the sodium–potassium alloy heat pipe in passive residual heat removal system of molten salt reactor (2013) (42)
Theoretical Study on the Flow Instability of Supercritical Water in the Parallel Channels (2012) (42)
Preliminary study of coupling CFD code FLUENT and system code RELAP5 (2014) (41)
Application of an Artificial Neural Network in Reactor Thermohydraulic Problem: Prediction of Critical Heat Flux (2002) (41)
Prediction of CHF in vertical heated tubes based on CFD methodology (2015) (40)
Severe accident analysis for a typical PWR using the MELCOR code (2014) (38)
Experimental research on heat transfer of natural convection in vertical rectangular channels with large aspect ratio (2010) (38)
Analysis on the neutron kinetics for a molten salt reactor (2009) (38)
The influence of ocean conditions on two-phase flow instability in a parallel multi-channel system (2008) (38)
Design and transient analyses of emergency passive residual heat removal system of CPR1000 (2012) (38)
A correlation of nanofluid flow boiling heat transfer based on the experimental results of AlN/H2O and Al2O3/H2O nanofluid (2017) (38)
Review of Thermal-Hydraulic Issues and Studies of Lead-based fast reactors (2020) (37)
Conceptual design and analysis of a multipurpose micro nuclear reactor power source (2018) (37)
Preliminary safety analysis of the PWR with accident-tolerant fuels during severe accident conditions (2015) (37)
The COPRA experiments on the in-vessel melt pool behavior in the RPV lower head (2016) (36)
Numerical study on the single bubble rising behaviors under rolling conditions (2019) (35)
The development of Module In-vessel degraded severe accident Analysis Code MIDAC and the relevant research for CPR1000 during the station blackout scenario (2014) (34)
Development of a new Pellet-Clad Mechanical Interaction (PCMI) model and its application in ATFs (2017) (34)
Analysis of CHF in saturated forced convective boiling on a heated surface with impinging jets using artificial neural network and genetic algorithm (2011) (34)
Study on secondary side flow of steam generator with coupled heat transfer from primary to secondary side (2013) (34)
Development of a steady state analysis code for a molten salt reactor (2009) (34)
COPRA: A large scale experiment on natural convection heat transfer in corium pools with internal heating (2016) (33)
Experimental research of liquid entrainment through ADS-4 in AP1000 (2014) (33)
Analysis of the loss of pool cooling accident in a PWR spent fuel pool with MAAP5 (2014) (32)
Theoretical Study on Density Wave Oscillation of Two-Phase Natural Circulation under Low Quality Conditions (2001) (32)
Natural convection heat transfer test for in-vessel retention at prototypic Rayleigh numbers – Results of COPRA experiments (2016) (32)
Development of a thermal–hydraulic analysis code for research reactors with plate fuels (2009) (31)
Design and transient analyses of emergency passive residual heat removal system of CPR1000. Part I: Air cooling condition (2011) (31)
Development of Fuel ROd Behavior Analysis code (FROBA) and its application to AP1000 (2012) (31)
Experimental study on the flow and thermal characteristics of two-phase leakage through micro crack (2019) (31)
Core thermal-hydraulic evaluation of a heat pipe cooled nuclear reactor (2020) (31)
Study on the coolant mixing phenomenon in a 45° T junction based on the thermal-mechanical coupling method (2018) (30)
The characteristics and correlation of nanofluid flow boiling critical heat flux (2018) (30)
A sub-channel analysis code for advanced lead bismuth fast reactor (2013) (30)
Numerical study on annular tube once-through steam generator using compressible flow model (2012) (30)
Experimental study on spray characteristics of pressure-swirl nozzles in pressurizer (2014) (30)
COPRA experiments on natural convection heat transfer in a volumetrically heated slice pool with high Rayleigh numbers (2016) (29)
Optimization study for thermal efficiency of supercritical water reactor nuclear power plant (2014) (29)
An evaluation of designed passive Core Makeup Tank (CMT) for China pressurized reactor (CPR1000) (2013) (29)
MELCOR simulation of core thermal response during a station blackout initiated severe accident in China pressurized reactor (CPR1000) (2015) (29)
Thermal-hydraulic analysis of a new conceptual heat pipe cooled small nuclear reactor system (2020) (29)
Thermal hydraulic investigations with different fuel diameters of pebble bed water cooled reactor in CFD simulation (2012) (28)
Global attractivity and permanence of a SVEIR epidemic model with pulse vaccination and time delay (2009) (28)
Applications of Artificial Neural Network for the Prediction of Flow Boiling Curves (2002) (28)
Experimental study on critical heat flux in bilaterally heated narrow annuli (2009) (28)
Probabilistic view of SiC/SiC composite cladding failure based on full core thermo-mechanical response (2018) (27)
Development of a thermal–mechanical behavior coupling analysis code for a dual-cooled annular fuel element in PWRs (2016) (27)
A mechanism of heat transfer enhancement or deterioration of nanofluid flow boiling (2020) (26)
Numerical research on the neutronic/thermal-hydraulic/mechanical coupling characteristics of the optimized helium cooled solid breeder blanket for CFETR (2017) (26)
Numerical prediction of subcooled wall boiling in the secondary side of SG tubes coupled with primary coolant (2014) (26)
Applications of genetic neural network for prediction of critical heat flux (2010) (25)
Preliminary design and thermal analysis of a liquid metal heat pipe radiator for TOPAZ-II power system (2016) (25)
Flow and heat transfer characteristics in plate-type fuel channels after formation of blisters on fuel elements (2019) (25)
An improved mechanistic critical heat flux model and its application to motion conditions (2012) (25)
Large eddy simulation on turbulent heat transfer in reactor vessel lower head corium pools (2018) (25)
Evaluation and optimization of tritium breeding, shielding and nuclear heating performances of the helium cooled solid breeder blanket for CFETR (2017) (25)
CFD investigation on thermal hydraulics of the passive residual heat removal heat exchanger (PRHR HX) (2018) (24)
Development of a MCNP–ORIGEN burn-up calculation code system and its accuracy assessment (2014) (24)
Theoretical study on the characteristics of critical heat flux in vertical narrow rectangular channels (2012) (24)
Prediction of LBB leakage for various conditions by genetic neural network and genetic algorithms (2017) (24)
Development of a thermal-hydraulic analysis code for CARR (2005) (24)
Two-dimensional numerical simulation of single bubble rising behavior in liquid metal using moving particle semi-implicit method (2013) (24)
Thermal-hydraulic analysis of the improved TOPAZ-II power system using a heat pipe radiator (2016) (23)
A simple novel analysis procedure for IVR calculation in core-molten severe accident (2011) (23)
The development of a zirconium oxidation calculating program module for Module In-vessel Degraded Analysis Code MIDAC (2014) (23)
Experimental investigation of a novel heat pipe thermoelectric generator for waste heat recovery and electricity generation (2020) (23)
Hydrodynamics of two-phase flow in a rod bundle under cross-flow condition (2016) (23)
Numerical analysis of the granular flow and heat transfer in the ADS granular spallation target (2018) (23)
Accident analyses for china pressurizer reactor with an innovative conceptual design of passive residual heat removal system (2014) (22)
Numerical analysis of the melt behavior in a fuel support piece of the BWR by MPS (2017) (22)
Simulations of unprotected loss of heat sink and combination of events accidents for a molten salt reactor (2013) (22)
Development of sub-channel code SACoS and its application in coupled neutronics/thermal hydraulics system for SCWR (2012) (22)
Three-dimensional study on steady thermohydraulics characteristics in secondary side of steam generator (2014) (22)
Steady and transient solutions of neutronics problems based on finite volume method (FVM) with a CFD code (2015) (22)
Pressure drop characteristics of vertically upward flow in inclined rod bundles (2016) (22)
Mechanism study and theoretical simulation on heat split phenomenon in dual-cooled annular fuel element (2016) (22)
CFD simulation of flow and heat transfer characteristics in a 5×5 fuel rod bundles with spacer grids of advanced PWR (2020) (21)
Numerical research on water hammer phenomenon of parallel pump-valve system by coupling FLUENT with RELAP5 (2017) (21)
Theoretical calculation of annular upward flow in a narrow annuli with bilateral heating (2003) (21)
The influence of ocean conditions on thermal-hydraulic characteristics of a passive residual heat removal system (2015) (21)
Experimental and theoretical investigation of liquid entrainment through small-scaled ADS-4 in AP1000 (2014) (21)
CFD analysis on subcooled boiling phenomena in PWR coolant channel (2015) (21)
Research on thermal hydraulic behavior of small-break LOCAs in AP1000 (2013) (21)
Three dimensional thermal hydraulic characteristic analysis of reactor core based on porous media method (2017) (21)
An improved Multiphase Moving Particle Semi-implicit method in bubble rising simulations with large density ratios (2018) (21)
Experimental research on transient critical heat flux in vertical tube under oscillatory flow condition (2011) (20)
Transient thermal–hydraulic analysis of a space thermionic reactor (2016) (20)
Numerical research on oscillation of two-phase flow in multichannels under rolling motion (2011) (20)
Experimental study of liquid sodium flow and heat transfer characteristics along a hexagonal 7-rod bundle (2019) (20)
Numerical investigation on thermal-hydraulic characteristics of NaK in a helical wire wrapped annulus (2019) (20)
COPRA experiment and numerical research on the behavior of internally-heated melt pool with eutectic salt (2018) (20)
Experimental investigations on single-phase convection and two-phase flow boiling heat transfer in an inclined rod bundle (2019) (20)
Investigation of severe accident scenario of PWR response to LOCA along with SBO (2015) (19)
Coupled analysis for new fuel design using UN and UC for SCWR (2013) (19)
Theoretical investigations on two-phase flow instability in parallel channels under axial non-uniform heating (2014) (19)
The comparison of designed water-cooled and air-cooled passive residual heat removal system for 300 MW nuclear power plant during the feed-water line break scenario (2013) (19)
Basic verification of THACS for sodium-cooled fast reactor system analysis (2015) (19)
Experimental study on heat transfer limit of high temperature potassium heat pipe for advanced reactors (2021) (19)
Numerical investigation of flow and heat transfer characteristics in plate-type fuel channels of IAEA MTR based on OpenFOAM (2021) (19)
Current achievements on bubble dynamics analysis using MPS method (2020) (19)
Local radial point interpolation method for the fully developed magnetohydrodynamic flow (2011) (18)
MELCOR severe accident analysis for a natural circulation small modular reactor (2017) (18)
Global attractivity and permanence of a delayed SVEIR epidemic model with pulse vaccination and saturation incidence (2009) (18)
Analysis of the Limiting Safety System Settings of a Fluoride Salt–Cooled High-Temperature Test Reactor (2014) (18)
Entrainment at T-junction: A review work (2014) (18)
A comparative study on preliminary performance evaluation of ATFs under normal and accident conditions with FRAP-ATF code (2018) (18)
Analysis of flow blockage accidents in rectangular fuel assembly based on CFD methodology (2018) (18)
Experimental investigation on the heat transfer performance of high-temperature potassium heat pipe for nuclear reactor (2021) (18)
Thermohydraulic and safety analysis on China advanced research reactor under station blackout accident (2007) (18)
Thermal-hydraulic analysis of EBR-II Shutdown Heat Removal Tests SHRT-17 and SHRT-45R (2015) (18)
Prediction of CHF in concentric-tube open thermosiphon using artificial neural network and genetic algorithm (2010) (17)
Numerical simulation of three-dimensional flow and heat transfer characteristics of liquid lead–bismuth (2021) (17)
Numerical simulation of Rayleigh-Taylor Instability with periodic boundary condition using MPS method (2018) (17)
Experimental investigation of gas lift pump in a lead-bismuth eutectic loop (2018) (17)
An experiment study of pressure drop and flow distribution in subchannels of a 37-pin wire-wrapped rod bundle (2020) (17)
The development and validation of the inter-wrapper flow model in sodium-cooled fast reactors (2018) (17)
Pressure drop characteristics of two-phase flow in a vertical rod bundle with support plates (2016) (16)
Preliminary study of parameter uncertainty influence on Pressurized Water Reactor core design (2013) (16)
Subchannel thermal-hydraulic analysis of the fuel assembly for liquid sodium cooled fast reactor (2013) (16)
Code development and safety analyses for Pb–Bi-cooled direct contact boiling water fast reactor (PBWFR) (2013) (16)
Study on onset of nucleate boiling in bilaterally heated narrow annuli (2010) (16)
Upwinding meshfree point collocation method for steady MHD flow with arbitrary orientation of applied magnetic field at high Hartmann numbers (2011) (16)
Research on the leak-rate characteristics of leak-before-break (LBB) in pressurized water reactor (PWR) (2014) (16)
Numerical investigation of the fluid-solid mixture flow using the FOCUS code (2017) (16)
Numerical investigation on startup characteristics of high temperature heat pipe for nuclear reactor (2021) (16)
Analysis of natural circulation operational characteristics for integrated pressurized water reactor (2016) (16)
Thermal-mechanical coupling behavior analysis on metal-matrix dispersed plate-type fuel (2017) (16)
Comparison of CORA & MELCOR core degradation simulation and the MELCOR oxidation model (2014) (16)
Preliminary accident analysis of Loss of Off-Site Power and In-Box LOCA for the CFETR helium cooled solid breeder blanket (2017) (16)
Thermal-hydraulic analysis of a fluoride-salt-cooled pebble-bed reactor with CFD methodology (2016) (16)
Development of TACOS code for loss of flow accident analysis of SCWR with mixed spectrum core (2012) (16)
Thermal‐hydraulic design features of a micronuclear reactor power source applied for multipurpose (2019) (16)
Experimental investigation on steam-water two-phase flow boiling heat transfer in a staggered horizontal rod bundle under cross-flow condition (2018) (16)
CFD simulation of secondary side fluid flow and heat transfer of the passive residual heat removal heat exchanger (2018) (16)
Depressurization study of supercritical fluid blowdown from simple vessel (2014) (16)
Development of a thermal-hydraulic analysis software for the Chinese advanced pressurized water reactor (2010) (15)
Analysis of KROTOS Steam Explosion Experiments Using the Improved Fuel-Coolant–Interaction Code TEXAS-VI (2013) (15)
A theoretical CHF model for downward facing surfaces and gaps under saturated boiling (2012) (15)
Preliminary thermal-hydraulic and safety analysis of China DFLL-TBM system (2013) (15)
Flow instability analysis of supercritical water-cooled reactor CSR1000 based on frequency domain (2012) (15)
Thermal‐hydraulic analysis of an open‐grid megawatt gas‐cooled space nuclear reactor core (2020) (15)
Experimental investigation on flow and heat transfer characteristics of single-phase flow with simulated neutronic feedback in narrow rectangular channel (2012) (15)
Numerical prediction of CHF based on CFD methodology under atmospheric pressure and low flow rate (2019) (14)
A code development for leak before break (LBB) leakage from supercritical to subcritical conditions (2018) (14)
Analyses of liquid entrainment through ADS-4 in AP1000 during a typical small break LOCA transient (2013) (14)
Subcooled pool boiling of water on a downward-facing stainless steel disk in a gap (2008) (14)
Thermal-Hydraulic Analyses of Transportable Fluoride Salt–Cooled High-Temperature Reactor with CFD Modeling (2016) (14)
From melt jet break-up to debris bed formation: A review of melt evolution model during fuel-coolant interaction (2022) (14)
Development and preliminary validation of a steam generator 3D thermohydraulics analysis code STAF (2016) (14)
Water hammer characteristics of integral pressurized water reactor primary loop (2013) (14)
Conceptual design and analysis of a megawatt power level heat pipe cooled space reactor power system (2020) (14)
Development of a multi-compartment containment code for advanced PWR plant (2018) (14)
Natural convection heat transfer of water in a horizontal gap with downward-facing circular heated surface (2008) (14)
Thermal–hydraulic and safety analysis for Chinese helium-cooled solid breeder TBM cooling system (2013) (14)
Scaling analysis of AP1000 ADS-4 entrainment and depressurization (2014) (14)
A simple novel and fast computational model for the LIVE-L4 (2013) (14)
Effects of power level on thermal-hydraulic characteristics of steam generator (2015) (13)
A Theoretical Model of Annular Upward Flow in a Vertical Annulus Gap (2003) (13)
Numerical analysis of the dissolution of uranium dioxide by molten zircaloy using MPS method (2017) (13)
Steady thermal hydraulic analysis for a molten salt reactor (2008) (13)
Numerical simulation on single Taylor bubble rising in LBE using moving particle method (2013) (13)
Review on heat transfer and ﬂow characteristics of liquid sodium (1): Single-phase (2017) (13)
Experimental research on the thermal hydraulic characteristics of sodium boiling in an annulus (2015) (13)
Preliminary transient thermal-hydraulic analysis for new coated UN and UC fuel options in SCWR (2014) (13)
Analysis of flow distribution instability in parallel thin rectangular multi-channel system (2016) (13)
Development of a subchannel analysis code for SFR wire-wrapped fuel assemblies (2018) (13)
Development of a neutronics/thermal-hydraulic coupling optimization code and its application on the CFETR HCSB blanket (2017) (13)
Comparative study on effect of air–water and steam–water mediums on liquid entrainment through ADS-4 in AP1000 (2015) (13)
Experimental research on the thermal hydraulic characteristics of liquid sodium flowing in annuli with low Peclet number (2015) (13)
An innovative method for prediction of liquid metal heat transfer rate for rod bundles based on annuli (2012) (13)
Thermal–hydraulic design and analysis code development for steam generator of CFR600 (2016) (13)
Effect of stratified interface instability on thermal focusing effect in two-layer corium pool (2019) (13)
Analysis of KROTOS KS-2 and KS-4 steam explosion experiments with TEXAS-VI (2016) (12)
Numerical research on natural convection in molten salt reactor with non-uniformly distributed volumetric heat generation (2010) (12)
Multiscale Thermal Hydraulic Study under the Inadvertent Safety Injection System Operation Scenario of Typical Pressurized Water Reactor (2017) (12)
LES and URANS study on turbulent flow through 3 × 3 rod bundle with spacer grid and mixing vanes using spectral element method (2021) (12)
Experimental study on natural convection heat transfer in a two-layer corium pool based on COPRA facility (2019) (12)
Numerical study on the thermal stratification characteristics of AP1000 pressurizer surge line (2019) (12)
Prediction of flow boiling heat transfer coefficient in horizontal channels varying from conventional to small-diameter scales by genetic neural network (2019) (12)
Utilization of 3D fuel modeling capability of BISON to derive new insights in performance of advanced PWR fuel concepts (2019) (12)
Study on the hydrogen risk in venturi scrubber filter of filtered containment venting system under PWR severe accident (2018) (12)
Three-dimensional numerical study on the effect of sidewall crust thermal resistance on transient MCCI by improved MPS method (2020) (12)
Comparison of Hydrogen Generation Rate between CORA-13 Test and MELCOR Simulation: Clad Solid-Phase Oxidation Models Using Self-Developed Code MYCOAC (2015) (12)
Experimental investigation on flow and heat transfer characteristics of lead–bismuth eutectic in circular tubes (2020) (12)
Numerical study on the heat transfer characteristics of LIVE-L4 melt pool with a partial solidification process (2014) (12)
Study on the characteristic points of boiling curve by using wavelet analysis and genetic neural network (2009) (11)
Study on CHF characteristics in narrow rectangular channel under complex motion condition (2020) (11)
Development of a thermal–hydraulic analysis software for a passive residual heat removal system (2012) (11)
Experimental analysis of flow and convective heat transfer in the water-cooled packed pebble bed nuclear reactor core (2020) (11)
Experimental research on the incipient boiling wall superheat of sodium (2013) (11)
Integrating a multi-layer deformation model in FRAPTRAN for accident Tolerant fuel analysis (2019) (11)
Computational Fluid Dynamics Analysis of a Fluoride Salt–Cooled Pebble-Bed Test Reactor (2014) (11)
Thermal Hydraulic Analysis of a Passive Residual Heat Removal System for an Integral Pressurized Water Reactor (2009) (11)
Experimental study on spray characteristics of pressure-swirl nozzle in China advanced PWR containment (2019) (11)
Analysis of accidental loss of pool coolant due to leakage in a PWR SFP (2015) (11)
Thermal-hydraulic analysis of the thermoelectric space reactor power system with a potassium heat pipe radiator (2020) (11)
Study of traveling wave reactor (TWR) and CANDLE strategy: A review work (2014) (11)
Conceptual design and analysis of heat pipe cooled silo cooling system for the transportable fluoride-salt-cooled high-temperature reactor (2017) (11)
Numerical study on flow and heat transfer characteristics in the rod bundle channels under super critical pressure condition (2010) (11)
Numerical investigation on the dissolution kinetics of ZrO2 by molten zircaloy using MPS method (2017) (10)
Thermal‐hydraulic analysis of gas‐cooled space nuclear reactor power system with closed Brayton cycle (2020) (10)
Minor actinide transmutation in a board type sodium cooled breed and burn reactor core (2015) (10)
Numerical simulation of a small high-temperature heat pipe cooled reactor with CFD methodology (2020) (10)
Experimental investigation of upper plenum entrainment in AP1000 (2015) (10)
Numerical investigation of buoyant effect on flow and heat transfer of Lithium–Lead Eutectic in DFLL–TBM (2012) (10)
Development of a thermal-hydraulic subchannel analysis code for motion conditions (2016) (10)
Investigation on the critical heat flux in typical 5 by 5 rod bundle at conditions prototypical of PWR based on CFD methodology (2020) (10)
Development of a three-field mechanistic model for dryout prediction in annular flow (2020) (10)
Local effect model development for the steam generator three dimensional thermal hydraulics analysis code (2020) (10)
Coupled neutronics/thermal hydraulics evaluation for thorium based fuels in thermal spectrum SCWR (2013) (10)
A comprehensive review of the leak flow through micro-cracks (in LBB) for nuclear system: Morphologies and thermal-hydraulic characteristics (2020) (10)
Experimental and theoretical study on transition boiling concerning downward-facing horizontal surface in confined space (2008) (10)
Comparative study of transient thermal–hydraulic characteristics of SCWRs with different core design (2013) (9)
Research on enhancement of natural circulation capability in lead–bismuth alloy cooled reactor by using gas-lift pump (2013) (9)
Experimental study on vertically upward steam-water two-phase flow patterns in narrow rectangular channel (2020) (9)
Thermoelectric characteristics analysis of thermionic space nuclear power reactor (2019) (9)
Preliminary safety assessment on two LOCAs under ITER-like condition for the optimized CFETR helium cooled solid breeder blanket (2017) (9)
Three dimensional neutronic/thermal-hydraulic coupled simulation of MSR in transient state condition (2014) (9)
Thermal hydraulic characteristics analysis of direct residual heat removal system for China pressurized reactor (2016) (9)
Neutronics and thermo-hydraulic design of supercritical-water cooled solid breeder TBM (2015) (9)
Automatic differentiation approach for solving one-dimensional flow and heat transfer problems (2021) (9)
Numerical study of tritium transport characteristics in Thorium Molten Salt Reactor with Solid Fuel (TMSR-SF) (2018) (9)
Experimental investigation of liquid entrainment in AP1000 ADS-4 branch line with air–water (2014) (9)
Study on the systematic thermal-hydraulic characteristics of helical coil once-through steam generator (2021) (9)
CFD modeling of liquid entrainment through vertical T-junction of fourth stage automatic depressurization system (ADS-4) (2021) (9)
PHEBUS FPT-1 simulation by using MELCOR and primary blockage model exploration (2016) (9)
Numerical analysis of simulant effect on natural convection characteristics in corium pools (2019) (9)
Experimental Study on Coolability of Particulate Core-Metal Debris Bed with Oxidization, (I) Fragmentation and Enhanced Heat Transfer in Zircaloy-50 wt%Ag Debris Bed (2005) (9)
Modification and update of FROBA-ROD code and its applications in fuel rod behavior analysis for PWRs (2019) (9)
Study on the reactor core barrel instantaneous characteristics in case of Loss of Coolant Accident (LOCA) scenarios for loop-type PWR (2017) (9)
Experimental investigation on flow regimes and transitions of steam-water two-phase flow in narrow rectangular horizontal channels (2021) (9)
Numerical Study on the Thermal Hydraulic Characteristics in a Wire-Wrapped Assembly of LFRs (2020) (9)
Development and application of a neutronics/thermal-hydraulics coupling optimization code for the CFETR helium cooled solid breeder blanket with mixed pebble beds (2017) (9)
Experimental investigation of liquid entrainment in ADS-4 depressurization line with steam–water (2015) (9)
MAAP5 Simulation of the PWR Severe Accident Induced by Pressurizer Safety Valve Stuck-Open Accident (2014) (9)
Numerical Simulation on Collapse of Vapor Bubble Using Particle Method (2014) (8)
Results of simulant effect on large corium pool behavior based on COPRA facility (2018) (8)
Simulation of the small modular reactor severe accident scenario response to SBO using MELCOR code (2016) (8)
Study of flow instability in parallel channel system for water cooled blanket (2019) (8)
Analysis of flow distribution in plate-type core affected by uneven inlet temperature distribution (2016) (8)
Improving the optimization algorithm of NTCOC for application in the HCSB blanket for CFETR Phase II (2018) (8)
Control of Canadian once-through direct cycle supercritical water-cooled reactors (2015) (8)
Thermal Hydraulic and Neutronics Coupling Analysis for Plate Type Fuel in Nuclear Reactor Core (2020) (8)
Numerical analysis on flow instability of parallel channels in steam generator for sodium‐cooled fast reactor (2020) (8)
Numerical research on the coupling optimization design rule of the CFETR HCSB blanket using the NTCOC code (2018) (8)
RELAP5 MOD3.2 modification and application to the transient analysis of a fluoride-salt-cooled high-temperature reactor (2017) (8)
Program development and study on supercritical CO2-cooled reactor sub-channel thermal hydraulic (2021) (8)
A new method for improving the tritium breeding and releasing performance of China Fusion Engineering Test Reactor phase II helium‐cooled ceramic breeder blanket (2020) (8)
Development of cladding oxidation analysis code [COAC] and application for early stage severe accident simulation of AP1000 (2015) (8)
Scaling and distortion analysis using a simple natural circulation loop for FHR development (2020) (8)
Code development and analysis on the operation of liquid metal high temperature heat pipes under full condition (2021) (8)
Ammonia-water mixture property code (AWProC) development, verification and Kalina cycle design for nuclear power plant (2016) (8)
Review on heat transfer and flow characteristics of liquid sodium (2): Two-phase (2018) (8)
Experimental investigations on start‐up performance of static nuclear reactor thermal prototype (2020) (8)
Development and verification of molten corium–concrete interaction code (2015) (8)
Study on the onset of nucleate boiling in narrow annular channel by genetic neural network (2010) (8)
Study of boron diffusion models and dilution accidents in nuclear reactor: A comprehensive review (2020) (8)
Improvement of RELAP5 code for density wave instability analysis in parallel narrow rectangular channels (2018) (8)
Models development of liquid drops entrainment at a T-junction with a large vertical up branch (2017) (8)
Experimental simulation of liquid entrainment in ADS-4 depressurization line in AP1000 (2016) (7)
Experimental research on flow instability in vertical narrow annuli (2007) (7)
Development of a Thermal-Hydraulic Analysis Code and Transient Analysis for a FHTR (2014) (7)
Numerical study on cooling characteristics in granular and liquid spallation targets (2017) (7)
Development of CHF models for inner and outer RPV gaps in a meltdown severe accident (2013) (7)
Development of the analysis tool for the water cooling type passive residual heat removal system of Chinese pressurized reactor (2016) (7)
Control system design and validation platform development for small pressurized water reactors (SPWR) by coupling an engineering simulator and MATLAB/Simulink (2017) (7)
Theoretical prediction of single bubble motion in vertically upward two-phase flow across inclined tube bundles (2019) (7)
Simulation of the PHEBUS FPT-1 experiment using MELCOR and exploration of the primary core degradation mechanism (2015) (7)
Development of a transient thermal-hydraulic code for analysis of China Demonstration Fast Reactor (2013) (7)
Experimental study on critical heat flux on a downward-facing stainless steel disk in confined space (2011) (7)
Experimental study of the helium flow characteristics in pebble-bed under the condition of CFETR's blanket module (2017) (7)
ECC condensation research in T-junction (2016) (7)
Experimental study on heat transfer performance between fluoride salt and heat pipes in the new conceptual passive residual heat removal system of molten salt reactor (2018) (7)
CFD study on onset of liquid entrainment through ADS-4 branch line in AP1000 (2021) (7)
Numerical study on the purge gas flow and heat transfer characteristics in helium cooled solid breeder blanket of CFETR (2018) (7)
Study on dryout point by wavelet and GNN (2010) (7)
Experimental research on heat transfer behavior of large scale two-layer salt melt pool based on COPRA facility (2020) (7)
Flow pattern effect on two-phase pressure drops in vertical upward flow across a horizontal tube bundle (2018) (7)
A new method on fluid-to-fluid scaling for heat transfer in tubes at supercritical pressures (2018) (7)
Hybrid medium model for conjugate heat transfer modeling in the core of sodium-cooled fast reactor (2020) (7)
Experiment study on thermal behavior of a horizontal high-temperature heat pipe under motion conditions (2022) (6)
Numerical Study of Integral Inherently Safe Light Water Reactor in Case of Inadvertent DHR Operation Based on the Multiscale Method (2018) (6)
Development of DETAC and its application to the hydrogen detonation analysis (2015) (6)
Development of a subchannel analysis code and its application to annular fuel assemblies (2019) (6)
Experimental study on fragmentation characteristics of molten aluminum/copper jet penetrating in sodium pool (2019) (6)
The Development of Candling Module Code in Module In-vessel Degraded Analysis Code MIDAC and the Relevant Calculation for CPR1000 During Large-Break LOCA (2016) (6)
Uncertainty analysis of Transportable Fluoride-salt-cooled High-temperature Reactor (TFHR) using coupled DAKOTA with RELAP-3D method (2017) (6)
Effects of nitrogen and carbon monoxide on the detonation of hydrogen-air gaseous mixtures (2019) (6)
Thermal-hydraulic design of water-cooled pressure tube blanket for a fusion driven subcritical reactor (2013) (6)
Thermoelectric performance study on a heat pipe thermoelectric generator for micro nuclear reactor application (2021) (6)
Large eddy simulation on the mixing characteristics of liquid sodium at the core outlet of sodium cooled fast reactors (SFR) (2021) (6)
Energy allocation optimization of the gas-cooled space nuclear reactor (2021) (6)
Operation and safety analysis of space lithium-cooled fast nuclear reactor (2022) (6)
Experimental Study on Heat Transfer of Single-Phase Flow and Boiling Two-Phase Flow in Vertical Narrow Annuli (2002) (6)
Design and heat transfer optimization of a 1 kW free-piston stirling engine for space reactor power system (2021) (6)
Experimental Investigation of Air-Water CCFL in the Pressurizer Surge Line of AP1000 (2016) (6)
Transient heat transfer in internally heated corium pool (2018) (6)
Licensing Considerations of a Fluoride Salt Cooled High Temperature Test Reactor (2013) (6)
Experimental study on flow characteristics of rectangular narrow channel (2020) (6)
Flow and heat transfer analysis of lead–bismuth eutectic flowing in a tube under rolling conditions (2021) (6)
Natural convection heat transfer of water on a horizontal downward facing stainless steel disk in a gap under atmospheric pressure conditions (2007) (6)
Linear parameter-varying modeling and control of the steam temperature in a Canadian SCWR (2017) (6)
Applications of Artificial Neural Network for the Prediction of Pool Boiling Curves (2002) (5)
Performance evaluation and efficiency enhancement of a space thermionic fuel element for thermal energy conversion and utilization (2020) (5)
Research on performance enhancement of nuclear fuel with SiC cladding by using high thermal conductivity fuels (2020) (5)
Thermal–hydraulic performance analysis of IPWR during full pressure start-up mode (2013) (5)
Flow Boiling Pressure Drop Characteristics in Rectangular Channels under Uniform and Non-Uniform Heating (2020) (5)
Development of a thermal–hydraulic analysis code for the Pebble Bed Water-cooled Reactor (2011) (5)
Experimental investigations on single-phase convection and critical heat flux in vertical tubes under oscillatory flow condition (2020) (5)
A new unidentified leak detection method based on the EVR ventilation condensate (2017) (5)
Thermal–hydraulic analysis of space nuclear reactor TOPAZ-II with modified RELAP5 (2019) (5)
Study effects of the kinetics of local composition diffusion on the melt pool coolability by developing a DBL-LIVE model (2016) (5)
Preliminary numerical investigation of TRISO-matrix interface debonding characteristics in fully ceramic microencapsulated fuel (2021) (5)
A three-dimensional axial fuel relocation framework with discrete element method to support burnup extension (2020) (5)
Design and R&D progress of Core Assembly Deformation Test Facility for China Demonstration Fast Reactor (2019) (5)
Thermal‐hydraulic design and analysis of a small modular molten salt reactor (MSR) with solid fuel (2018) (5)
3D-2D coupling multi-dimension simulation for the heat pipe micro-reactor by MOOSE&SAM (2021) (5)
Experimental study of raining effect on the inner surface of containment roof (2020) (5)
Investigation on thermo-mechanical performance of fully ceramic microencapsulated fuel (2021) (5)
A modified system analysis code for thermo-hydraulic calculation of hydrogen in a nuclear thermal propulsion (NTP) system (2021) (5)
The effects of core zoning on optimization of design analysis of molten salt reactor (2013) (5)
Review of the AFD-type CHF mechanistic model and its application to rod bundle (2020) (5)
Reactor Core Design and Analysis for a Micronuclear Power Source (2018) (5)
Design research for the porous hexagonal prism shaped fuel element adopted in nuclear thermal propulsion reactor based on neutronics and thermal-hydraulics coupled method (2021) (5)
Numerical analysis for a molten salt reactor in the presence of localized perturbations (2012) (5)
Experimental research on the characteristics of steam-water counter-current flow in the Pressurizer Surge Line assembly (2018) (5)
Experimental research on fragmentation characteristics of molten stainless steel discharged into sodium pool and comparison with molten copper (2020) (5)
Development of a thermal hydraulic code for an integral reactor (2013) (5)
Study on flow instability in natural circulation loop with parallel channels under moving condition (2021) (5)
Numerical investigation of natural convection characteristics of a heat pipe-cooled passive residual heat removal system for molten salt reactors (2020) (5)
Analytical model for CHF in narrow gaps with surface orientation effects (2011) (5)
Experimental study on critical heat flux in bilaterally heated narrow annuli (2009) (5)
Analysis of the dynamic pressure from ex-vessel steam explosion for pressurized water reactor (2017) (5)
Experimental investigation on narrow gap heat transfer with porous media under downward-facing horizontal heated surface (2009) (5)
Numerical investigation on heat transfer characteristics of helium‐xenon gas mixture (2020) (5)
Modeling of early stage droplet spreading based on numerical simulations (2020) (5)
Experimental research on assembly section stiffness and bending stiffness for sodium-cooled fast reactor (2020) (4)
Preliminary neutronic/thermal-hydraulic evaluation and safety system optimization of PWR loaded with fully ceramic microencapsulated fuel (2020) (4)
Numerical and Experimental Investigation on Core Assembly Thermal-Gradient-Induced Deformation of Sodium-Cooled Fast Reactor (2018) (4)
Development of a two-fluid based thermal-hydraulic subchannel analysis code with high-resolution numerical method (2021) (4)
Dynamic simulation of a space gas-cooled reactor power system with a closed Brayton cycle (2021) (4)
Numerical Solution on Spherical Vacuum Bubble Collapse Using MPS Method (2010) (4)
Experiment research on thermal mixing in horizontal T-junction: In-pipe temperature and flow characteristic research (2017) (4)
Heat transfer characteristics in super-low finned-tube bundles of moisture separator reheaters (2019) (4)
Analysis of Westinghouse MB2 test using the Steam-generator Thermohydraulics Analysis code STAF (2015) (4)
Numerical investigation on bubble condensation and coalescence of bubble pairs using moving particle semi-implicit method (2011) (4)
Coupled neutronics/thermal-hydraulics and safety characteristics of liquid-fueled Molten Salt Reactors (2016) (4)
Experimental research on dryout point of flow boiling in narrow annular channels (2006) (4)
The code development and thermo-hydrodynamic analysis of the reflood during severe accident in PWR (2017) (4)
Research on Enhancement of Natural Circulation Capability in Lead-Bismuth Alloy Cooled Reactor by Using Gas-Lift Pump (2012) (4)
A 3-D simulation tool for hydrogen detonation during severe accident and its application (2017) (4)
Preliminary design and analyses of the helium cooled ceramic breeder blanket for CFETR phase II (2020) (4)
Analysis of PWR RPV lower head SBLOCA scenarios with the failure of high-pressure injection system using MAAP5 (2014) (4)
Preliminary analysis on the thermal-mechanical behavior of dispersed plate-type fuel under reactivity insertion accident (2021) (4)
Oxygen transport analysis in lead-bismuth eutectic coolant for solid-phase oxygen control (2021) (4)
A study on the dynamic characteristics of the secondary loop in nuclear power plant (2020) (4)
Accident Tolerance Cladding Thermal Hydraulic Simulation and Oxidation Kinetic Sensitivity Analysis (2017) (4)
Numerical study of laminar flow and friction characteristics in narrow channels under rolling conditions using MPS method (2019) (4)
Improvement and validation of a sub‐channel analysis code for a lead‐cooled reactor with wire spacers (2020) (4)
Experimental study on the natural circulation capability and heat transfer characteristic of liquid lead bismuth eutectic (2019) (4)
Preliminary design study of a board type radial fuel shuffling sodium cooled breed and burn reactor core (2014) (4)
Theoretical Research on Flow Instability in Parallel Channels Under Motion Conditions (2013) (3)
Analysis on natural circulation capacity of the CARR (2007) (3)
Development of VTSAS 1.0 and application to an IPWR (2013) (3)
A practical methodology devoted to pool‐type phenomena simulation in safety analysis for sodium‐cooled fast reactor (2020) (3)
Numerical simulation of micro-crack leakage on steam generator heat transfer tube (2021) (3)
Spatial temperature distribution of fuel assembly pre-simulation for a new simple core degradation experiment (2019) (3)
Development of safety analysis code for SCWR and its LOCA analysis of CSR1000 (2018) (3)
Numerical research on local heat transfer distribution of liquid sodium turbulent flow in an annulus (2013) (3)
Density Wave Instability of Sodium Boiling Two-phase Flow in a Vertical Annulus at Low Pressure (2003) (3)
A Thermohydraulic Code for Low Temperature Nuclear Heating Reactor and Its Passive Residual Heat Removal Systems (2004) (3)
Convection of internal-heated two-layer fluids with deformable interface under swinging motion conditions (2020) (3)
Experimental Study on Al2O3/H2O Nanofluid Flow Boiling Heat Transfer Under Different Pressures (2016) (3)
Investigation of Pressure Drop for Fluid Flow Through Porous Media: Application to a Pebble-Bed Reactor (2010) (3)
The Research on Core Melting Process: Oxidation (2013) (3)
Experimental Study on Dryout Point in Vertical Narrow Annulus Under Low Flow Conditions (2004) (3)
Numerical study of bubble rising in quiescent liquid under rolling motion conditions using MPS – MAFL method (2019) (3)
An experiment‐based validation of a system code for prediction of passive natural circulation in sodium‐cooled fast reactor (2020) (3)
Reactivity feedback evaluation during the start-up of the heat pipe cooled nuclear reactors (2020) (3)
MELCOR simulation of the SBLOCA induced severe accident for the SMR in a floating nuclear power plant (2020) (3)
Development of fuel rod behavior analysis code and its application to supercritical CO2 cooled nuclear reactor (2021) (3)
A new method to simulate dispersion plate-type fuel assembly in a multi-physics coupled way (2022) (3)
Characteristic of Natural Circulation Temperature Fluctuation Under Rolling Motion Condition (2008) (3)
Generating Hexahedral Mesh for Wire-wrapped Fuel Assembly With RBF Mesh Deformation Method (2021) (3)
Analysis of flow instabilities in forced-convection steam generator (2006) (3)
Study on the Onset of Nucleate Boiling in Narrow Annular Channel by Using Wavelet and Wavelet Neural Network (2009) (3)
CFD Investigation of Thermal-Hydraulic Behaviors in Full Reactor Core for Sodium-Cooled Fast Reactor (2018) (3)
Flow blockage analysis for fuel assembly in a lead-based fast reactor (2021) (3)
Development of TSACO and application to Chinese HCCB TBM cooling system (2013) (3)
Development of a three-dimensional method for thermal-hydraulics/neutronics coupling analysis and its application on CFETR helium-cooled solid breeder blanket (2021) (3)
Theoretical investigation on the steady-state natural circulation characteristics of a new type of pressurized water reactor (2006) (3)
An investigation of numerical performance enhancement of RELAP5: Numerical stability, higher resolution and an alternative constitutive relation (2018) (3)
Analysis of the Particulate Debris Bed Quenching During Top and Bottom Flood (2014) (3)
Transient safety analysis for simplified accelerator driven system with gas-lift pump (2018) (3)
Fragmentation characteristics of molten materials jet dropped into liquid sodium pool (2019) (3)
Numerical investigation for the heat transfer mechanisms between subchannels of bar rod bundles cooled by liquid sodium (2021) (3)
An analysis of incipient boiling superheat in alkali liquid metals (2014) (3)
Experimental investigations on leak flow rate characteristics of water through axial artificial microcracks of steam generator tubes under back pressure conditions (2019) (3)
Numerical study on the thermal-hydraulic characteristics of the choked flow through micro cracks for various conditions (2020) (3)
PIV measurement and numerical investigation on flow characteristics of simulated fast reactor fuel subassembly (2020) (3)
Loss-of-Flow-Accidents (LOFA) Study for 100 MW IPWR (2014) (3)
Model application research for liquid entrainment through ADS-4 pipe in AP1000 (2017) (3)
Development of a transient module based on FROBA-ROD code and assessment for fuel rod performance under reactivity-initiated accident (2021) (3)
Experimental Study of Air-Steam–Mixture Condensation Underneath Containment Vessel Surface (2021) (3)
Numerical approaches and analysis of spray characteristics for pressuriser nozzles (2014) (2)
Design and evaluation of a high power density and high energy efficiency fuel element for space nuclear reactors (2021) (2)
FeCrAl Cladding Oxidation Kinetic and Steam Generator Auxiliary Feedwater Methods Sensitivity Analysis- - during a Short-Term Station Blackout Simulation of Surry Nuclear Power Plant (2018) (2)
Numerical Research on Steady Coupling of Neutronics and Thermal-Hydraulics for a Molten Salt Reactor (2008) (2)
Numerical Study of Bubble Rising and Coalescence Characteristics under Flow Pulsation Based on Particle Method (2019) (2)
Natural convection heat transfer of water in a horizontal circular gap (2007) (2)
Experimental study on helium pressure drop across randomly packed bed for fusion blanket (2017) (2)
Mechanism Study and Numerical Simulation on Blistering of Plate-Type Fuel (2016) (2)
Experimental Study on Thermal-Hydraulic Performance of Single-Phase Water Flow in Narrow Rectangular Channel (2009) (2)
Experimental investigation on hot water seal over an analogous U-shaped device (2018) (2)
Experimental study on leak flow rate characteristics of high pressure subcooled water through axial and circumferential microcracks of steam generator tubes under high back pressure conditions (2020) (2)
Experimental investigation on heat transfer characteristics of high temperature air in round tube (2021) (2)
Theoretical analysis of the characteristics of critical heat flux in vertical narrow rectangular channels under motion conditions (2015) (2)
Validation of TRACE capability to simulate unprotected transients in Sodium Fast Reactor using FFTF LOFWST Test #13 (2021) (2)
Performance of radial fuel shuffling sodium cooled Breed and Burn reactor core (2016) (2)
Natural Convection With Non-Uniform Heat Generation in Molten Salt Reactor (2009) (2)
Conceptual Design and Neutronics/Thermal-Hydraulic Coupling Optimization Analyses of Two Typical Helium Cooled Solid Breeder Blanket Modules for CFETR Phase II (2018) (2)
Preliminary optimization of emergency core cooling system with accident-tolerant fuels (2020) (2)
Numerical studies of stepwise radial fuel shuffling in a traveling wave reactor (2014) (2)
Preliminary development and validation of ACENA code for heavy liquid metal-gas two phase flow simulation (2021) (2)
3D Flow Field Analysis for a Traditional II+ PWR Containment Under Normal Condition (2014) (2)
Program development and preliminary CHF characteristics analysis for natural circulation loop under moving condition (2020) (2)
An Experimental Study on Coolability of Particulate Core-Metal Debris Bed With Oxidization (2004) (2)
Sub-Channel Analysis of Pb-Bi-Cooled Reactor With Modified COBRA-EN (2014) (2)
Analysis of AP1000 ex-vessel steam explosion behavior using TEXAS-V code (2015) (2)
NUMERICAL SIMULATION OF NATURAL CONVECTION HEAT TRANSFER FROM A DOWNWARD-FACING HORIZONTAL ROUND PLATE IN CONFINED SPACE (2007) (2)
Research on pressure drop characteristics in inverted half U-tube bundle under two-phase cross-flow condition (2018) (2)
Performance analysis of PRHRS in primary and secondary circuit for offshore floating nuclear plant (2021) (2)
Investigation on fuel cracking induced relocation behavior of dual-cooled annular fuel based on finite element simulation (2022) (2)
Performance analysis of automatic depressurization system in advanced PWR during a typical SBLOCA transient using MIDAC (2020) (2)
Flow characteristics of single-phase flow in narrow annular channels (2008) (2)
Parameter analysis of natural convection thermal characteristics in internally heated pool (2020) (2)
Experimental research on the influence of rolling motions on the convection behaviors inside two-layer corium pools (2020) (2)
Thermal-fluid-structure coupling analysis on plate-type fuel assembly under irradiation. Part-II Mechanical deformation and thermal-hydraulic characteristics (2020) (2)
Experimental Study on AlN/H2O and Al2O3/H2O Nanofluid Flow Boiling Heat Transfer and its Influence Factors in a Vertical Tube (2016) (2)
Development of thermal hydraulic analysis code of annular fuel under flow blockage condition (2021) (2)
Development a methodology for evaluating inter‐assembly heat transfer effect through reactor core in system safety analysis of sodium‐cooled fast reactor (2021) (2)
Development of TSAC1.0 and application to reactivity insertion accident of CARR (2011) (2)
Experimental Study on Coolability of Particulate Core-metal Debris Bed with Oxidization, (II) Fragmentation and Enhanced Heat Transfer in Zircaloy Debris Bed (2006) (2)
Transient Safety Analysis of a Transportable Fluoride-Salt-Cooled High-Temperature Reactor Using RELAP5-3D (2017) (2)
Start-up characteristics for the test facility of a prototype sodium heated OTSG (2021) (2)
Estimation of thermodynamic properties of the ternary molten salt system, LiF-NaF-BeF2, by the modified Peng-Robinson equation (2007) (2)
CFD Simulation of thermal hydraulic characteristics in a typical upper plenum of RPV (2021) (2)
Numerical study of oxygen transport characteristics in lead-bismuth eutectic for gas-phase oxygen control (2021) (2)
Thermo-Hydraulic Analysis of the Optimized Helium Cooled Solid Breeder Blanket for CFETR (2016) (2)
Investigations of near-wall bubble behavior in wire heaters pool boiling (2020) (1)
Analysis of heat flux and velocity effects on nucleation superheat in liquid metals based on dynamic effects (2014) (1)
Artificial neural network introductions (2021) (1)
Preliminary thermal-hydraulic influence of the poloidal nonuniform neutron wall loading on the CFETR HCCB blanket (2021) (1)
Theoretical Calculation of the Critical Heat Flux in Annular Upward Flow in Vertical Narrow Rectangular Channels (2009) (1)
Experimental study on molten corium-concrete interaction with simulant metal and oxide (2022) (1)
Simulation of FARO corium coolant interaction experiment with TEXAS-VI (2012) (1)
Pressure Drop Experiments of Liquid Sodium Flowing in a 7-Rod Bundle (2018) (1)
Measurement method for deformation and contact force of the fuel assembly for China fast reactor under thermal gradient (2020) (1)
Vapor condensation with low air mass fraction inside water seal branch tube under free convection (2021) (1)
Neutronics and Thermo-Hydraulic Analysis of Water-Cooled Blanket Based on PWR and SCWR Water Conditions for CFETR (2016) (1)
Research on Two-Phase Flow Instability in Parallel Multi-Channel Under Rolling Motion Condition (2008) (1)
Implementation of Liquid Metal Properties in RELAP5 MOD3.2 for Safety Analysis of Sodium-Cooled Fast Reactors (2017) (1)
Experimental and theoretical study on fluid-structure interaction and non-equilibrium of the flow through micro cracks (2020) (1)
Development of a steady thermal-hydraulic analysis code for the China Advanced Research Reactor (2007) (1)
Code development and characteristics analysis for Leak Before Break in the pipelines of Sodium-cooled Fast Reactor (2019) (1)
The Thermal-Hydraulic Analyses of Transients in PBWFR (2012) (1)
Research on scaling analysis and design parameters of integral test facilities for PWR (2021) (1)
Comparison of CORA and MELCOR Core Degradation Simulation and MELCOR Oxidation Model (2014) (1)
Thermal-fluid-structure coupling analysis for plate-type fuel assembly under irradiation. Part-I numerical methodology (2020) (1)
Review on Core Degradation and Material Migration Research in Light-Water Reactors (2018) (1)
COPRA and LIVE tests on transient and steady-state heat transfer in a melt pool (2016) (1)
Numerical Analysis of Bubble Rising Behavior in a Liquid Metal Using MPS (2011) (1)
ICONE23-1836 PRELIMINARY STUDY ON THE EFFECT OF ACCIDENT TOLERANT FUELS ON PWR SEVERE SBO (2015) (1)
Parallelization and application of SACOS for whole core thermal-hydraulic analysis (2021) (1)
Theoretical study of steady-state characteristics of natural circulation system (2020) (1)
Investigation of single bubble behavior under rolling motions using multiphase MPS method on GPU (2020) (1)
Numerical analysis of liquid fall type gas entrainment in pool-type fast reactor (2021) (1)
Numerical Analysis of the Corium Behavior Within the Fuel Support Piece by MPS (2016) (1)
Study on the Prediction of DNB-Type Critical Heat Flux in Rod Bundle Under Motion Conditions (2018) (1)
Preliminary prediction for survival time of fuel rod under critical heat flux (2021) (1)
Experimental investigation on thermal-hydraulic characteristics of narrow rectangular channels with simulated neutronic feedback (2014) (1)
Neutronic and Thermo-Hydraulic Analyses of Water-Cooled Blanket Based on Pressurized/Supercritical Water Conditions for CFETR (2019) (1)
Optimization of Moving Particle Semi-Implicit (MPS) Method and Studying of Flow Instability (2018) (1)
Numerical investigation of oxidation and dissolution behavior in the fuel cladding using MPS-CV method (2021) (1)
Numerical Investigation on Heat Removal Capacity of Passive Residual Heat Removal Heat Exchanger (2014) (1)
Simulation on Pellet-Cladding Mechanical Interaction (PCMI) of Accident Tolerant Fuel (ATF) With Coated Cladding (2017) (1)
Application of Film Dryout Model in Liquid Metal CHF Prediction (2014) (1)
Research of Liquid Entrainment Through ADS-4 in AP1000 (2014) (1)
Iron–Chromium–Aluminum (FeCrAl) Cladding Oxidation Kinetics and Auxiliary Feedwater Sensitivity Analysis—Short-Term Station Blackout Simulation of Surry Nuclear Power Plant (2018) (1)
Analysis of UO2-BeO Fuel Performance During Normal Conditions and RIA (2018) (1)
Numerical investigation of ballooning and burst for chromium coated zircaloy cladding (2021) (1)
An Investigation of Flow, Heat Transfer Characteristic of Annular Flow and Critical Heat Flux in Vertical Upward Round Tube (2006) (1)
New Methods of Studying Nuclear Reactor Thermohydraulics (2002) (1)
Numerical investigation on thermohydraulic performance of high temperature hydrogen in twisted rod channels (2021) (1)
Three-Dimensional Steady Simulation on Two-Phase Flow in Secondary Side of Steam Generator (2013) (1)
FISSION REACTORS 221 Analysis of the Limiting Safety System Settings of a Fluoride Salt-Cooled (2014) (1)
Development of Boron Dilution Model in COBRA-EN (2018) (1)
Numerical Investigation of Dissolution Reaction between UO 2 and Molten Zry-4 using MPS method (2018) (1)
Thermal-hydraulic research on rod bundle in the LBE fast reactor with grid spacer (2022) (1)
Development of a thermo-mechanical coupling code based on an annular fuel sub-channel code (2019) (1)
Experimental Study on the Critical Heat Flux of Nanofluid Flow Boiling Under Different Conditions (2018) (0)
Theoretical analysis for coupled thermal deformation behaviors of subassemblies in a single row in sodium-cooled fast reactors (2021) (0)
Transient thermal‐hydraulic analysis of heat pipe cooled passive residual heat removal system of molten salt reactor (2020) (0)
Thermal Hydraulic Analysis of a Passive Residual Heat Removal System for an Integral PressurizedWater Reactor (2015) (0)
Development of a New Method for Simulating Gas-to-Particle Conversion During Sodium Pool Fires in SFR Containment (2020) (0)
Development of Simulation Codes for Some Accidents in Pressurized Water Reactors (2008) (0)
ICONE19-43763 DESIGN AND TRANSIENT ANALYSES OF PASSIVE EMERGENCY FEEDWATER SYSTEM OF CPR1000 : PART I: AIR COOLING CONDITION (2011) (0)
Investigation of the Modified RELAP5 MOD 3.2 Capability to Simulate the Transients of the Fluoride-Salt High-Temperature Reactors (2016) (0)
Study on Thermal-Hydraulic Characteristics of Vertical Narrow Rectangular Channel With Large Aspect Ratio Under Transverse Uneven Heating (2018) (0)
COPRA Experiments on Melt Pool Behavior With Eutectic NaNO3-KNO3 Simulant (2018) (0)
Experimental Study on the Steam-Water Co-Current Flow Friction Multiplier of the AP1000 Surge Line (2017) (0)
Experimental Study on Spray Pattern of Pressure-Swirl Nozzle in Reactor Containment (2018) (0)
Validation of the ATHROC Code With NUPEC Tests (2016) (0)
Experimental Study on the Thermal Hydraulic Characteristics of Liquid Sodium Flowing in an Annulus (2014) (0)
Development and validation of transient thermal‐hydraulic evaluation code for a lead‐based fast reactor (2021) (0)
ICONE23-1792 DEVELOPMENT OF TRANSIENT THERMAL-HYDRAULIC ANALYSIS CODE FOR THE SPACE THERMIONIC REACTOR (2015) (0)
Development and Application of a UTSG Thermal-Hydraulic Analysis Code (2014) (0)
tudy on the characteristic points of boiling curve by using avelet analysis and genetic neural network (2009) (0)
Analysis of a Loss of Heat Removal Accident in a PWR Spent Fuel Pool (2014) (0)
Development and Verification of Thermal Hydraulic Subchannel Analysis Code for Motion Conditions (2016) (0)
Effect of Rolling Motion on Flow Instability of Parallel Rectangular Channels of Natural Circulation (2018) (0)
Development of Safety Analysis Code TACOS and Application to Fuel Qualification Test Loop (2017) (0)
Comparison of Transient Responses for SCWRs With Different Flow Path Designs Under Loss of Flow Accident (2012) (0)
ICONE19-43215 NUMERICAL RESEARCH ON THE THERMAL HYDRAULICS OF THE COOLANT IN A PEBBLE BED REACTOR CORE BY CFD (2011) (0)
Corrigendum to “Experimental study of liquid sodium flow and heat transfer characteristics along a hexagonal 7-rod bundle” [Appl. Therm. Eng. 149 (2019) 578–587.] (2019) (0)
Numerical Study on the Thermal Stratification Phenomenon in the Sodium-Cooled Fast Reactor (2019) (0)
ICONE23-1996 CFD SIMULATIONS OF THERMAL MIXING AT ECC SAFETY INJECTION FOR SINGLE PHASE AND AIR-WATER BUBBLY PHASE FLOW (2015) (0)
Study on the Improvement of TOPAZ-II system by Using a Heat Pipe Radiator (2015) (0)
Development of Technologies on Innovative-Simplified Nuclear Power Plant Using High-Efficiency Steam Injector: Part 14—Cooling Characteristics of the Particulate Core Material Debris Accumulated in Horizontal Narrow Gap (2006) (0)
CFD Analysis of Cross Flow in Rod Bundles Under Rolling Motion (2016) (0)
Numerical investigation on the dryout point of annular flow in the upward narrow annuli with bilateral heating (2007) (0)
The Code Development for the Thermo-Hydrodynamic Characteristics Study of Reflood Phase (2014) (0)
Thermal-Hydraulics Design of Water-Cooled Pressure Tube Blanket for a Fusion Driven Subcritical Reactor (2012) (0)
Numerical simulation on bubble growth and departure by MPS (2011) (0)
An investigation of characteristics of flow and heat transfer in the two-layer molten pool under swing motion condition (2022) (0)
Thermal hydraulic design and analysis of Thorium-based Advanced CANDU Reactor (TACR) (2017) (0)
Research on Natural Convection of Two-Layer Corium Pools (2020) (0)
Simulation of Molten Corium Concrete Interaction With the MOCO Code (2014) (0)
Experimental Study on Post-Dryout Heat Transfer of Dispersed Flow in Vertical Narrow Annuli (2004) (0)
Boiling incipience of liquid sodium flow in an annular channel based on wavelet analysis (2020) (0)
Upwinding Meshfree Point Collocation Method for Steady MHD Flow (2010) (0)
DEVELOPMENT OF AN IN-VESSEL SEVERE ACCIDENT ANALYSIS CODE MIDAC (2015) (0)
Numerical Research on Melt Pool Flow Characteristics Under Rolling Condition (2018) (0)
Experimental Investigation on Analogous U-Shaped Tube Water Seal in Front of Pressurizer Safety Valve (2016) (0)
Investigation on the Accident of Loss of Offsite Power of CARR (2010) (0)
Numerical Simulation on Single Bubble Rising Behavior in Liquid Metal Using Moving Particle Semi-implicit Method (2011) (0)
Numerical Simulation of Fuel Relocation at High Burnup With Discrete Element Method (2022) (0)
The Severe Accident Analysis of CPR1000 Based on MELCOR Code (2013) (0)
Preliminary verification of a transient analysis code TSACO for helium cooled system (2017) (0)
ICONE15-10451 Evaluation of Static Thermodynamic Properties of the Ternary Molten Salt System Li, Na, Be/F, Based on the Modified Peng-Robinson Equation (2007) (0)
Study on pool boiling and flow boiling with artificial neural networks (2010) (0)
CFD Simulation of a 61-pin Wire-wrapped Fuel Subassembly for Sodium Cooled Fast Reactor (2017) (0)
Impact of axial power distribution on thermal-hydraulic characteristics for thermionic reactor (2021) (0)
Thermal-Hydraulic Analysis of TOPAZ-II With Modified RELAP5 (2018) (0)
Numerical Study on the Heat Transfer Characteristics of COPRA-L1 Melt Pool Based on the LES Method (2016) (0)
Experimental and Simulative Investigation of ADS-4 Depressurization Process in AP1000 (2016) (0)
ICONE19-43372 Numerical Simulation of Opposing Mixed Convection Heat Transfer of Lithium-Lead in a Vertical Square Channel with Heat Source (2011) (0)
NUCLEAR ENGINEERING AND TECHNOLOGY (2019) (0)
Study on the thermal and geometrical parameters of helical coil once-through steam generator system (2021) (0)
Experimental Research on Dryout Point of Flow Boiling in Narrow Annuli (2006) (0)
Transient Thermal Behaviors of SBO Accident for a 200MW OFNP Under Heaving Motion Conditions (2018) (0)
Transient Analysis of CP300 Based on RELAP5/MOD3.4 (2014) (0)
Thermal-Hydraulic Analysis of Design Basis Accidents for Chinese Helium-Cooled Solid Breeder TBM (2012) (0)
Development and Basic Verification of Decay Heat Removal Analysis Code of Sodium-Cooled Fast Reactor (2018) (0)
THE STUDY OF SEVERE ACCIDENT MITIGATION MEASURES FOR A MARINE NUCLEAR POWER PALNT (2019) (0)
Numerical Research on Oscillation of Two-Phase Flow Under Rolling Motion (2010) (0)
Data for: Radiative and evaporative analysis of a liquid droplet layer for space applications (2019) (0)
Characterization and Experimental Investigation for the Dynamic Performance of the Hydraulically Suspended Passive Shutdown System in China Sodium-Cooled Fast Reactor (2018) (0)
SIMULATIONS ON NATURAL CONVECTION OF STRATIFIED MELT POOLS WITH VOLUMETRIC HEAT GENERATION (2019) (0)
Experimental Investigation of Liquid Entrainment in ADS-4 Branch Line (2014) (0)
DETONATION CHARACTERISTICS OF H2-AIR DILUTED WITH N2 IN SMOOTH TUBE (2019) (0)
Numerical simulation of Taylor bubble rising in liquid lead-bismuth eutectic based on MPS method (2013) (0)
Preliminary Analysis of Three ULOFAs Based on the Dual-Functional Lithium Lead Test Blanket Module Configuration in ITER (2010) (0)
ICONE19-43196 Prediction of Periodic Dryout Critical Heat Flux under Flow Oscillation Condition (2011) (0)
A Prediction of the Leakage Through Cracks for Leak Before Break (2014) (0)
Numerical Research on Fuel Rod Progression During Core Degradation Process Using MELCOR (2018) (0)
Validation of THACS for Sodium Cooled Fast Reactor Based on Benchmark Analysis of EBR-II (2014) (0)
Theoretical and Experimental Research on the Single-Phase and Incipient Boiling Heat Transfer of Liquid Metal Sodium (2017) (0)
ICONE23-1537 EFFECTIVENESS ANALYSIS OF SEVERE ACCIDENT MANAGEMENT STRATEGIES IN LOCA SCENARIOS FOR AP1000 (2015) (0)
Corrigendum to “Entrainment at T-junction: A review work” [Prog. Nucl. Energy 70 (January 2014) 221–241] (2014) (0)
Simulation on the Thermal Hydraulics of the Coolant in a Pebble Bed Reactor Core by CFD (2009) (0)
Development of a Thermal-Hydraulic Code for Chinese Helium-Cooled Ceramic Breeder TBM Cooling System (2013) (0)
EXPERIMENTAL INVESTIGATION ON INFLUENCE FACTORS OF NANOFLUIDS ON SATURATED POOL BOILING CHF FOR DOWNWARD FACING SURFACE (2019) (0)
Investigation on axial relocation of fragmented annular fuel under Loss of Coolant Accident conditions with discrete element method (2022) (0)
Hydraulic Characteristics Research on SG Under Tube Plugging Operations Using FLUENT (2018) (0)
Transient Study on Sodium Heat Pipe in Passive Heat Removal System of Molten Salt Reactor (2013) (0)
Single electron loss in the collisions of lowly charged ions and atomic hydrogen (2010) (0)
CFD Analysis of Subcooled Wall Boiling at Shell Side of Steam Generator With TSP (2014) (0)
Prediction of Post-Dryout Heat Transfer in Vertical Annular Channels Using Artificial Neural Network Method (2008) (0)
CFD Simulation of Thermal-Hydraulic Characteristics of Water Seal Structure in PWR Pressurizer (2017) (0)
Tritium Transport Characteristics Analysis in Molten Salt Reactor Under Transient Conditions (2018) (0)
Experimental Investigation and Model Analysis on Upper Plenum Entrainment in AP1000 (2018) (0)
Sensitivity Analysis of the SBLOCA Induced Severe Accident for a Natural Circulation Small Modular Reactors (2018) (0)
ICONE23-2163 SEVERE ACCIDENT ANALYSIS OF A PWR SPENT FUEL POOL IN CASE OF LOSS OF POOL COOLANT (2015) (0)
The Influence of Non-Uniform Heating on Two-Phase Flow Instability in Parallel Channels (2013) (0)
Natural Circulation Characteristics of an Integral Pressurized Water Reactor (2006) (0)
Validation of a Code and Effect of Turbulence Model on Predicting Thermal Stratification Phenomena in the Upper Plenum of SFR (2018) (0)
Experimental Research on Energy Release and Fragments Characteristics Under Molten Materials Discharged Into Liquid Sodium (2018) (0)
Experimental Research on Heat Transfer Characteristic of Liquid Lead-Bismuth Eutectic Flowing in Annular Channel (2018) (0)
Numerical Study on Flow and Heat Transfer in Concentric and Eccentric Annuli (2010) (0)
Experimental and Theoretical Research on Liquid Entrainment in AP 1000 ADS Blowdown Phase of SBLOCA (2015) (0)
Thermohydraulic and Safety Analysis for CARR Under Station Blackout Accident (2006) (0)
Thermal Hydraulic Studies of a Fluoride Salt Cooled High Temperature Test Reactor With Different CFD Methods (2014) (0)
Experimental Study on Natural Circulation in a Lead Bismuth Eutectic Loop (2017) (0)
Start-Up Simulation of the Improved TOPAZ-II Space Power System (2016) (0)
K-2206 Experimental Study on Heat Transfer of Boiling Two-Phase Flow in Narrow Annular Channel (2001) (0)
STUDY OF SEVERE ACCIDENT INDUCED BY SBLOCA FOR A MARINE NUCLEAR POWER PLANT (2019) (0)
ICONE23-1570 THE FLOW AND HEAT TRANSFER CHARACTERISTICS OF A PASSIVE RESIDUAL HEAT REMOVAL SYSTEM UNDER OCEAN CONDITIONS (2015) (0)
Safety Analyses for Pb-Bi-Cooled Direct Contact Boiling Water Fast Reactor (PBWFR) (2014) (0)
THREE DIMENSIONAL THERMAL HYDRAULIC COUPLING METHOD ON PWR STEAM GENERATOR USING CFD METHOD (2019) (0)
A Novel Point Estimate Procedure for IVR Calculations in Core-Molten Severe Accident (2010) (0)
Water Hammer Characteristics for Parallel Pumps Water Supply Systems (2008) (0)
Neurtonics/Thermal-hydraulic analyses of the CFETR HCCB blanket for multiple operation modes under the poloidal nonuniform neutron wall loading condition (2021) (0)
Steady-State Thermal-Hydraulic Analysis of a Particle-Bedded Boiling Water Reactor (2009) (0)
Transient and Safety Analysis Code for TP-1 Sodium Cooled TWR (2013) (0)
Steady-State Thermal-Hydraulic Analysis of a Plate Type Reactor (2008) (0)
ICONE19-43858 An improved critical heat flux prediction model for subcooled and low quality flow boiling under motion condition based on microscopic mechanism (2011) (0)
Meshless Local Petrov-Galerkin Method for the Steady Magnetohydrodynamic (MHD) Flow in Rectangular Ducts With Arbitrary Wall Conductivity (2010) (0)
ICONE23-1345 DEVELOPMENT AND VALIDATION OF STAF : A STEAM GENERATOR 3D THERMOHYDRAULICS ANALYSIS CODE BASED ON FLUENT (2015) (0)
Numerical Simulation of the Fluid-Solid Mixture Flow Based on the MPS method (2017) (0)
Experimental study on critical heat flux in bilaterally heated narrow annuli (2009) (0)
An Innovative Method for the Theoretical Investigation on the Critical Heat Flux of Nanofluid Flow Boiling With Nanoparticle Deposition (2021) (0)
The Optimization Design of Lower Plenum and Distribution Plates in MSR (2013) (0)
Coupled Analysis of Thermal Hydraulics and Neutronics for a Molten Salt Reactor (2017) (0)

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Guang-hui Su is affiliated with the following schools:

Hokkaido University
Kyushu University
Xi'an Jiaotong University

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