Sui-zheng Qiu

Sui-zheng Qiu's AcademicInfluence.com Rankings

Sui-zheng Qiu

Engineering

#5239

World Rank

#6486

Historical Rank

Nuclear Engineering

#16

World Rank

#17

Historical Rank

Mechanical Engineering

#453

World Rank

#497

Historical Rank

Applied Physics

#1470

World Rank

#1502

Historical Rank

engineering Degrees

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Engineering

Sui-zheng Qiu's Degrees

PhD Nuclear Engineering University of California, Berkeley

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Sui-zheng Qiu'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

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)
Recent progress of CFD applications in PWR thermal hydraulics study and future directions (2021) (95)
Metallurgical study on erosion and corrosion behaviors of steels exposed to liquid lead bismuth flow (2005) (93)
Effects of turbulence models on forced convection subcooled boiling in vertical pipe (2015) (82)
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)
Flow blockage analysis of a channel in a typical material test reactor core (2009) (54)
Natural convection heat transfer in corium pools: A review work of experimental studies (2015) (54)
Theoretical investigations on two-phase flow instability in parallel multichannel system (2008) (54)
A Review on Analysis of LWR Severe Accident (2015) (52)
Numerical investigation on bubble dynamics during flow boiling using moving particle semi-implicit method (2010) (52)
A review on thermohydraulic and mechanical-physical properties of SiC, FeCrAl and Ti3SiC2 for ATF cladding (2020) (50)
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)
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)
Experimental study on heat pipe thermoelectric generator for industrial high temperature waste heat recovery (2020) (45)
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)
Prediction of CHF in vertical heated tubes based on CFD methodology (2015) (40)
Analysis on the neutron kinetics for a molten salt reactor (2009) (38)
Severe accident analysis for a typical PWR using the MELCOR code (2014) (38)
The influence of ocean conditions on two-phase flow instability in a parallel multi-channel system (2008) (38)
Experimental study on startup performance of high temperature potassium heat pipe at different inclination angles and input powers for nuclear reactor application (2020) (38)
Experimental research on heat transfer of natural convection in vertical rectangular channels with large aspect ratio (2010) (38)
Design and transient analyses of emergency passive residual heat removal system of CPR1000 (2012) (38)
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)
Full-scale numerical study on the flow characteristics and mal-distribution phenomena in SG steam-water separation system of an advanced PWR (2020) (36)
Numerical study on the single bubble rising behaviors under rolling conditions (2019) (35)
Study on secondary side flow of steam generator with coupled heat transfer from primary to secondary side (2013) (34)
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)
Analysis of CHF in saturated forced convective boiling on a heated surface with impinging jets using artificial neural network and genetic algorithm (2011) (34)
Development of a steady state analysis code for a molten salt reactor (2009) (34)
Development of a new Pellet-Clad Mechanical Interaction (PCMI) model and its application in ATFs (2017) (34)
COPRA: A large scale experiment on natural convection heat transfer in corium pools with internal heating (2016) (33)
Analysis of the loss of pool cooling accident in a PWR spent fuel pool with MAAP5 (2014) (32)
Natural convection heat transfer test for in-vessel retention at prototypic Rayleigh numbers – Results of COPRA experiments (2016) (32)
Core thermal-hydraulic evaluation of a heat pipe cooled nuclear reactor (2020) (31)
Development of a thermal–hydraulic analysis code for research reactors with plate fuels (2009) (31)
Experimental study on the flow and thermal characteristics of two-phase leakage through micro crack (2019) (31)
Development of Fuel ROd Behavior Analysis code (FROBA) and its application to AP1000 (2012) (31)
Design and transient analyses of emergency passive residual heat removal system of CPR1000. Part I: Air cooling condition (2011) (31)
Experimental study on spray characteristics of pressure-swirl nozzles in pressurizer (2014) (30)
A sub-channel analysis code for advanced lead bismuth fast reactor (2013) (30)
Study on the coolant mixing phenomenon in a 45° T junction based on the thermal-mechanical coupling method (2018) (30)
Numerical study on annular tube once-through steam generator using compressible flow model (2012) (30)
The characteristics and correlation of nanofluid flow boiling critical heat flux (2018) (30)
MELCOR simulation of core thermal response during a station blackout initiated severe accident in China pressurized reactor (CPR1000) (2015) (29)
Optimization study for thermal efficiency of supercritical water reactor nuclear power plant (2014) (29)
Study on safety boundary of flow instability and CHF for parallel channels in motion (2018) (29)
Thermal-hydraulic analysis of a new conceptual heat pipe cooled small nuclear reactor system (2020) (29)
COPRA experiments on natural convection heat transfer in a volumetrically heated slice pool with high Rayleigh numbers (2016) (29)
An evaluation of designed passive Core Makeup Tank (CMT) for China pressurized reactor (CPR1000) (2013) (29)
Thermal hydraulic investigations with different fuel diameters of pebble bed water cooled reactor in CFD simulation (2012) (28)
Experimental study on critical heat flux in bilaterally heated narrow annuli (2009) (28)
Global attractivity and permanence of a SVEIR epidemic model with pulse vaccination and time delay (2009) (28)
Preliminary neutronic and thermal-hydraulic analysis of a 2 MW Thorium-based Molten Salt Reactor with Solid Fuel (2016) (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 prediction of subcooled wall boiling in the secondary side of SG tubes coupled with primary coolant (2014) (26)
Three-dimensional study on the hydraulic characteristics under the steam generator (SG) tube plugging operations for AP1000 (2019) (26)
Evaluation and optimization of tritium breeding, shielding and nuclear heating performances of the helium cooled solid breeder blanket for CFETR (2017) (25)
Flow and heat transfer characteristics in plate-type fuel channels after formation of blisters on fuel elements (2019) (25)
Applications of genetic neural network for prediction of critical heat flux (2010) (25)
Optimization analysis of a segmented thermoelectric generator based on genetic algorithm (2020) (25)
Preliminary design and thermal analysis of a liquid metal heat pipe radiator for TOPAZ-II power system (2016) (25)
Large eddy simulation on turbulent heat transfer in reactor vessel lower head corium pools (2018) (25)
An improved mechanistic critical heat flux model and its application to motion conditions (2012) (25)
Theoretical study on the characteristics of critical heat flux in vertical narrow rectangular channels (2012) (24)
Two-dimensional numerical simulation of single bubble rising behavior in liquid metal using moving particle semi-implicit method (2013) (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)
Coupled Neutronics/Thermal-Hydraulics for Analysis of Molten Salt Reactor (2013) (24)
Development of a MCNP–ORIGEN burn-up calculation code system and its accuracy assessment (2014) (24)
CFD investigation on thermal hydraulics of the passive residual heat removal heat exchanger (PRHR HX) (2018) (24)
Thermal-hydraulic analysis of the improved TOPAZ-II power system using a heat pipe radiator (2016) (23)
Experimental investigation of a novel heat pipe thermoelectric generator for waste heat recovery and electricity generation (2020) (23)
Numerical analysis of the granular flow and heat transfer in the ADS granular spallation target (2018) (23)
The development of a zirconium oxidation calculating program module for Module In-vessel Degraded Analysis Code MIDAC (2014) (23)
A simple novel analysis procedure for IVR calculation in core-molten severe accident (2011) (23)
Hydrodynamics of two-phase flow in a rod bundle under cross-flow condition (2016) (23)
Mechanism study and theoretical simulation on heat split phenomenon in dual-cooled annular fuel element (2016) (22)
Three-dimensional study on steady thermohydraulics characteristics in secondary side of steam generator (2014) (22)
Numerical analysis of the melt behavior in a fuel support piece of the BWR by MPS (2017) (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)
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)
Numerical study on the turbulent mixing in channel with Large Eddy Simulation (LES) using spectral element method (2019) (22)
Full-scale numerical study on the thermal-hydraulic characteristics of steam-water separation system in an advanced PWR UTSG. Part two: Droplets separation process (2020) (22)
Accident analyses for china pressurizer reactor with an innovative conceptual design of passive residual heat removal system (2014) (22)
Numerical research on water hammer phenomenon of parallel pump-valve system by coupling FLUENT with RELAP5 (2017) (21)
CFD analysis on subcooled boiling phenomena in PWR coolant channel (2015) (21)
An improved Multiphase Moving Particle Semi-implicit method in bubble rising simulations with large density ratios (2018) (21)
Research on thermal hydraulic behavior of small-break LOCAs in AP1000 (2013) (21)
The influence of ocean conditions on thermal-hydraulic characteristics of a passive residual heat removal system (2015) (21)
Three dimensional thermal hydraulic characteristic analysis of reactor core based on porous media method (2017) (21)
CFD simulation of flow and heat transfer characteristics in a 5×5 fuel rod bundles with spacer grids of advanced PWR (2020) (21)
Theoretical calculation of annular upward flow in a narrow annuli with bilateral heating (2003) (21)
Experimental investigations on single-phase convection and two-phase flow boiling heat transfer in an inclined rod bundle (2019) (20)
Experimental research on transient critical heat flux in vertical tube under oscillatory flow condition (2011) (20)
Numerical research on oscillation of two-phase flow in multichannels under rolling motion (2011) (20)
COPRA experiment and numerical research on the behavior of internally-heated melt pool with eutectic salt (2018) (20)
Numerical investigation on thermal-hydraulic characteristics of NaK in a helical wire wrapped annulus (2019) (20)
Transient thermal–hydraulic analysis of a space thermionic reactor (2016) (20)
Experimental study of liquid sodium flow and heat transfer characteristics along a hexagonal 7-rod bundle (2019) (20)
Theoretical investigations on two-phase flow instability in parallel channels under axial non-uniform heating (2014) (19)
Basic verification of THACS for sodium-cooled fast reactor system analysis (2015) (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)
Investigation of severe accident scenario of PWR response to LOCA along with SBO (2015) (19)
Numerical approach to study the thermal-hydraulic characteristics of Reactor Vessel Cooling system in sodium-cooled fast reactors (2019) (19)
Numerical investigation of flow and heat transfer characteristics in plate-type fuel channels of IAEA MTR based on OpenFOAM (2021) (19)
Experimental study on heat transfer limit of high temperature potassium heat pipe for advanced reactors (2021) (19)
Coupled analysis for new fuel design using UN and UC for SCWR (2013) (19)
Preliminary design of the I2S-LWR containment system (2020) (19)
Current achievements on bubble dynamics analysis using MPS method (2020) (19)
Investigation on the characteristics of the flow and heat transfer in bilaterally heated narrow annuli (2007) (19)
DEM-CFD simulation of helium flow characteristics in randomly packed bed for fusion reactors (2018) (18)
Thermohydraulic and safety analysis on China advanced research reactor under station blackout accident (2007) (18)
MELCOR severe accident analysis for a natural circulation small modular reactor (2017) (18)
Local radial point interpolation method for the fully developed magnetohydrodynamic flow (2011) (18)
Entrainment at T-junction: A review work (2014) (18)
Thermal-hydraulic analysis of EBR-II Shutdown Heat Removal Tests SHRT-17 and SHRT-45R (2015) (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)
Experimental investigation on the heat transfer performance of high-temperature potassium heat pipe for nuclear reactor (2021) (18)
Experimental investigation of flow and convective heat transfer on a high-Prandtl-number fluid through the nuclear reactor pebble bed core (2018) (18)
Analysis of flow blockage accidents in rectangular fuel assembly based on CFD methodology (2018) (18)
Three-dimensional numerical simulation of the HECLA-4 transient MCCI experiment by improved MPS method (2019) (18)
Numerical simulation of three-dimensional flow and heat transfer characteristics of liquid lead–bismuth (2021) (17)
Experimental investigation of gas lift pump in a lead-bismuth eutectic loop (2018) (17)
Prediction of CHF in concentric-tube open thermosiphon using artificial neural network and genetic algorithm (2010) (17)
Numerical simulation of Rayleigh-Taylor Instability with periodic boundary condition using MPS method (2018) (17)
Comparison of Modeling Options for Delayed Neutron Precursor Movement in a Molten Salt Reactor (2009) (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)
The characteristics and correlation of saturated pool boiling critical heat flux for downward-facing plain heating surface (2020) (17)
Depressurization study of supercritical fluid blowdown from simple vessel (2014) (16)
Preliminary study of parameter uncertainty influence on Pressurized Water Reactor core design (2013) (16)
Fast-neutron multiplicity analysis based on liquid scintillation. (2016) (16)
Development of TACOS code for loss of flow accident analysis of SCWR with mixed spectrum core (2012) (16)
Thermal-hydraulic analysis of a fluoride-salt-cooled pebble-bed reactor with CFD methodology (2016) (16)
CFD simulation of secondary side fluid flow and heat transfer of the passive residual heat removal heat exchanger (2018) (16)
Comparison of CORA & MELCOR core degradation simulation and the MELCOR oxidation model (2014) (16)
Upwinding meshfree point collocation method for steady MHD flow with arbitrary orientation of applied magnetic field at high Hartmann numbers (2011) (16)
Pressure drop characteristics of two-phase flow in a vertical rod bundle with support plates (2016) (16)
Study on onset of nucleate boiling in bilaterally heated narrow annuli (2010) (16)
Code development and safety analyses for Pb–Bi-cooled direct contact boiling water fast reactor (PBWFR) (2013) (16)
Research on the leak-rate characteristics of leak-before-break (LBB) in pressurized water reactor (PWR) (2014) (16)
Development of a Solidification Model for TEXAS-VI Code and Application to FARO L14 Analysis (2013) (16)
Numerical investigation on startup characteristics of high temperature heat pipe for nuclear reactor (2021) (16)
Subchannel thermal-hydraulic analysis of the fuel assembly for liquid sodium cooled fast reactor (2013) (16)
Numerical investigation of the fluid-solid mixture flow using the FOCUS code (2017) (16)
Thermal‐hydraulic design features of a micronuclear reactor power source applied for multipurpose (2019) (16)
Thermal-mechanical coupling behavior analysis on metal-matrix dispersed plate-type fuel (2017) (16)
Experimental investigation on steam-water two-phase flow boiling heat transfer in a staggered horizontal rod bundle under cross-flow condition (2018) (16)
A theoretical CHF model for downward facing surfaces and gaps under saturated boiling (2012) (15)
Development and validation of boron diffusion model in nuclear reactor core subchannel analysis (2019) (15)
Numerical study on the thermal stratification characteristics in the upper plenum of sodium-cooled fast reactor (SFR) (2020) (15)
Upgrade of FROBA code and its application in thermal-mechanical analysis of space reactor fuel (2018) (15)
Thermal‐hydraulic analysis of an open‐grid megawatt gas‐cooled space nuclear reactor core (2020) (15)
Analysis of KROTOS Steam Explosion Experiments Using the Improved Fuel-Coolant–Interaction Code TEXAS-VI (2013) (15)
Development of a thermal-hydraulic analysis software for the Chinese advanced pressurized water reactor (2010) (15)
Preliminary thermal-hydraulic and safety analysis of China DFLL-TBM system (2013) (15)
CFD investigation of the cold wall effect on CHF in a 5 × 5 rod bundle for PWRs (2021) (15)
Experimental investigation on saturated pool boiling CHF for downward facing heating surface with different sizes and aspect ratio (2019) (15)
Flow instability analysis of supercritical water-cooled reactor CSR1000 based on frequency domain (2012) (15)
Experimental investigation on flow and heat transfer characteristics of single-phase flow with simulated neutronic feedback in narrow rectangular channel (2012) (15)
Scaling analysis of AP1000 ADS-4 entrainment and depressurization (2014) (14)
Development of a multi-compartment containment code for advanced PWR plant (2018) (14)
Passive decay heat removal system design for the integral inherent safety light water reactor (I2S-LWR) (2020) (14)
From melt jet break-up to debris bed formation: A review of melt evolution model during fuel-coolant interaction (2022) (14)
Thermal–hydraulic and safety analysis for Chinese helium-cooled solid breeder TBM cooling system (2013) (14)
Thermal-Hydraulic Analyses of Transportable Fluoride Salt–Cooled High-Temperature Reactor with CFD Modeling (2016) (14)
Experimental investigation of steam-air condensation on containment vessel (2020) (14)
A code development for leak before break (LBB) leakage from supercritical to subcritical conditions (2018) (14)
Development and preliminary validation of a steam generator 3D thermohydraulics analysis code STAF (2016) (14)
Fluoride-salt-cooled high-temperature reactors: Review of historical milestones, research status, challenges, and outlook (2022) (14)
A simple novel and fast computational model for the LIVE-L4 (2013) (14)
Steam condensation on a downward-facing plate in presence of air (2019) (14)
Conceptual design and analysis of a megawatt power level heat pipe cooled space reactor power system (2020) (14)
Validation of a methodology for thermal stratification analysis in sodium‐cooled fast reactors (2018) (14)
Water hammer characteristics of integral pressurized water reactor primary loop (2013) (14)
Analyses of liquid entrainment through ADS-4 in AP1000 during a typical small break LOCA transient (2013) (14)
Numerical prediction of CHF based on CFD methodology under atmospheric pressure and low flow rate (2019) (14)
Experimental study of single-phase flow and heat transfer in rectangular channels under uniform and non-uniform heating (2020) (13)
An investigation of flow characteristics and critical heat flux in vertical upward round tube (2006) (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)
Study of tritium transport characteristics in a transportable fluoride‐salt‐cooled high‐temperature reactor (2018) (13)
Numerical analysis of the dissolution of uranium dioxide by molten zircaloy using MPS method (2017) (13)
Development of a neutronics/thermal-hydraulic coupling optimization code and its application on the CFETR HCSB blanket (2017) (13)
Steady thermal hydraulic analysis for a molten salt reactor (2008) (13)
Effects of power level on thermal-hydraulic characteristics of steam generator (2015) (13)
Numerical simulation on single Taylor bubble rising in LBE using moving particle method (2013) (13)
An innovative method for prediction of liquid metal heat transfer rate for rod bundles based on annuli (2012) (13)
The development of high fidelity Steam Generator three dimensional thermal hydraulic coupling code: STAF-CT (2020) (13)
Preliminary Analysis of a Fully Ceramic Microencapsulated Fuel Thermal–Mechanical Performance (2019) (13)
Development of a subchannel analysis code for SFR wire-wrapped fuel assemblies (2018) (13)
Effect of stratified interface instability on thermal focusing effect in two-layer corium pool (2019) (13)
Preliminary transient thermal-hydraulic analysis for new coated UN and UC fuel options in SCWR (2014) (13)
Experimental research on the thermal hydraulic characteristics of liquid sodium flowing in annuli with low Peclet number (2015) (13)
Comparison of Hydrogen Generation Rate between CORA-13 Test and MELCOR Simulation: Clad Solid-Phase Oxidation Models Using Self-Developed Code MYCOAC (2015) (12)
Three-dimensional numerical study on the effect of sidewall crust thermal resistance on transient MCCI by improved MPS method (2020) (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)
Development of a kinetic model for safety studies of liquid-fuel reactors (2015) (12)
Numerical research on natural convection in molten salt reactor with non-uniformly distributed volumetric heat generation (2010) (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)
Analysis of KROTOS KS-2 and KS-4 steam explosion experiments with TEXAS-VI (2016) (12)
Multiscale Thermal Hydraulic Study under the Inadvertent Safety Injection System Operation Scenario of Typical Pressurized Water Reactor (2017) (12)
Experimental investigation on flow and heat transfer characteristics of lead–bismuth eutectic in circular tubes (2020) (12)
Study on the hydrogen risk in venturi scrubber filter of filtered containment venting system under PWR severe accident (2018) (12)
Design and analysis of a free-piston stirling engine for space nuclear power reactor (2020) (12)
Numerical study on the heat transfer characteristics of LIVE-L4 melt pool with a partial solidification process (2014) (12)
Experimental study on natural convection heat transfer in a two-layer corium pool based on COPRA facility (2019) (12)
Multidimensional multiphysics modeling of TRISO particle fuel with SiC/ZrC coating using modified fission gas release model (2020) (12)
Development and validation of a new module in the ATHROC for simulation of aerosol particles removal by spray in containment (2020) (12)
Study of traveling wave reactor (TWR) and CANDLE strategy: A review work (2014) (11)
Experimental study and optimized design on electromagnetic pump for liquid sodium (2019) (11)
CFD simulation on the flow characteristics in the PWR lower plenum with different internal structures (2020) (11)
Experimental research on the incipient boiling wall superheat of sodium (2013) (11)
Experimental Study on Flow Technology and Steel Corrosion of Lead-Bismuth (2002) (11)
Numerical study on flow and heat transfer characteristics in the rod bundle channels under super critical pressure condition (2010) (11)
Experimental analysis of flow and convective heat transfer in the water-cooled packed pebble bed nuclear reactor core (2020) (11)
Thermal-hydraulic analysis code development for sodium heated once-through steam generator (2019) (11)
Development of subcooled wall boiling model considering bubble sliding in narrow rectangular channel (2022) (11)
Thermal Hydraulic Analysis of a Passive Residual Heat Removal System for an Integral Pressurized Water Reactor (2009) (11)
Computational Fluid Dynamics Analysis of a Fluoride Salt–Cooled Pebble-Bed Test Reactor (2014) (11)
Study on CHF characteristics in narrow rectangular channel under complex motion condition (2020) (11)
Experimental study on transient performance of heat pipe-cooled passive residual heat removal system of a molten salt reactor (2020) (11)
Experimental study on spray characteristics of pressure-swirl nozzle in China advanced PWR containment (2019) (11)
Radiative and evaporative characteristics analysis of a liquid droplet layer for space applications (2019) (11)
Conceptual design and analysis of heat pipe cooled silo cooling system for the transportable fluoride-salt-cooled high-temperature reactor (2017) (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)
Performance analysis of alkali metal thermoelectric converter and segmented thermoelectric generator hybrid system based on a comprehensive model (2021) (11)
Development of a thermal–hydraulic analysis software for a passive residual heat removal system (2012) (11)
Study on the characteristic points of boiling curve by using wavelet analysis and genetic neural network (2009) (11)
Research on two-phase flow instability in parallel rectangular channels (2014) (11)
Development of an OpenFOAM solver for numerical simulations of shell-and-tube heat exchangers based on porous media model (2022) (10)
Minor actinide transmutation in a board type sodium cooled breed and burn reactor core (2015) (10)
Transient thermal-hydraulic evaluation of lead-bismuth fast reactor by coupling sub-channel and system analysis codes (2018) (10)
Large eddy simulation on the turbulent mixing phenomena in 3×3 bare tight lattice rod bundle using spectral element method (2020) (10)
Theoretical investigation of two-phase flow instability between parallel channels of natural circulation in rolling motion (2019) (10)
Experimental study of the steam condensate dripping behavior on the containment dome (2019) (10)
A comprehensive review of the leak flow through micro-cracks (in LBB) for nuclear system: Morphologies and thermal-hydraulic characteristics (2020) (10)
Local effect model development for the steam generator three dimensional thermal hydraulics analysis code (2020) (10)
Experimental and theoretical study on transition boiling concerning downward-facing horizontal surface in confined space (2008) (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)
Thermal-hydraulic analysis of pellet bed reactor for space nuclear electric propulsion (2020) (10)
Development of a three-field mechanistic model for dryout prediction in annular flow (2020) (10)
Numerical investigation of buoyant effect on flow and heat transfer of Lithium–Lead Eutectic in DFLL–TBM (2012) (10)
Experimental investigation of upper plenum entrainment in AP1000 (2015) (10)
The development and verification of thermal-hydraulic code on passive residual heat removal system of Chinese advanced PWR (2006) (10)
Coupled neutronics/thermal hydraulics evaluation for thorium based fuels in thermal spectrum SCWR (2013) (10)
Numerical simulation of a small high-temperature heat pipe cooled reactor with CFD methodology (2020) (10)
Thermal‐hydraulic analysis of gas‐cooled space nuclear reactor power system with closed Brayton cycle (2020) (10)
Numerical investigation on the dissolution kinetics of ZrO2 by molten zircaloy using MPS method (2017) (10)
Development of a thermal-hydraulic subchannel analysis code for motion conditions (2016) (10)
Comparative analysis of auxiliary feedwater system and passive safety system under typical accident scenarios for integrated pressurized water reactor (IPWR) (2019) (10)
Experimental Evaluation on Heat Transfer Limits of Sodium Heat Pipe with Screen Mesh for Nuclear Reactor System (2022) (9)
Study on the systematic thermal-hydraulic characteristics of helical coil once-through steam generator (2021) (9)
PHEBUS FPT-1 simulation by using MELCOR and primary blockage model exploration (2016) (9)
Research on enhancement of natural circulation capability in lead–bismuth alloy cooled reactor by using gas-lift pump (2013) (9)
Neutronics and thermo-hydraulic design of supercritical-water cooled solid breeder TBM (2015) (9)
Experimental investigation of liquid entrainment in AP1000 ADS-4 branch line with air–water (2014) (9)
Best estimate plus uncertainty analysis of the China advanced large-scale PWR during LBLOCA scenarios (2020) (9)
Core design and analysis of a lead-bismuth cooled small modular reactor (2019) (9)
Assessment of the severe accident code MIDAC based on FROMA, QUENCH-06&16 experiments (2021) (9)
Experimental study on vertically upward steam-water two-phase flow patterns in narrow rectangular channel (2020) (9)
Study on the reactor core barrel instantaneous characteristics in case of Loss of Coolant Accident (LOCA) scenarios for loop-type PWR (2017) (9)
Numerical analysis of simulant effect on natural convection characteristics in corium pools (2019) (9)
Migration–deposition coupling characteristics and influence of corrosion products on heat transfer in steam generators (2022) (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)
Experimental study on the heat transfer characteristics of fluoride salt in the new conceptual passive heat removal system of molten salt reactor (2018) (9)
Automatic differentiation approach for solving one-dimensional flow and heat transfer problems (2021) (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)
Modification and update of FROBA-ROD code and its applications in fuel rod behavior analysis for PWRs (2019) (9)
Experimental investigation of liquid entrainment in ADS-4 depressurization line with steam–water (2015) (9)
Comparative study of transient thermal–hydraulic characteristics of SCWRs with different core design (2013) (9)
MAAP5 Simulation of the PWR Severe Accident Induced by Pressurizer Safety Valve Stuck-Open Accident (2014) (9)
Experimental investigation on flow regimes and transitions of steam-water two-phase flow in narrow rectangular horizontal channels (2021) (9)
Experimental and numerical study on helium flow characteristics in randomly packed pebble bed (2019) (9)
CFD modeling of liquid entrainment through vertical T-junction of fourth stage automatic depressurization system (ADS-4) (2021) (9)
Numerical study of tritium transport characteristics in Thorium Molten Salt Reactor with Solid Fuel (TMSR-SF) (2018) (9)
Thermal hydraulic characteristics analysis of direct residual heat removal system for China pressurized reactor (2016) (9)
Three dimensional neutronic/thermal-hydraulic coupled simulation of MSR in transient state condition (2014) (9)
Numerical Study on the Thermal Hydraulic Characteristics in a Wire-Wrapped Assembly of LFRs (2020) (9)
Investigations on post-dryout heat transfer in bilaterally heated annular channels (2006) (8)
Experimental study on thermal hydraulic characteristics of natural circulation loop under motion condition (2022) (8)
Code development and analysis on the operation of liquid metal high temperature heat pipes under full condition (2021) (8)
Development of thermal hydraulic design code for SFR steam generators (2019) (8)
Improvement of RELAP5 code for density wave instability analysis in parallel narrow rectangular channels (2018) (8)
Thermal Hydraulic and Neutronics Coupling Analysis for Plate Type Fuel in Nuclear Reactor Core (2020) (8)
Study of flow instability in parallel channel system for water cooled blanket (2019) (8)
Scaling and distortion analysis using a simple natural circulation loop for FHR development (2020) (8)
Experimental investigation of liquid entrainment in vertical up tee branch with double-end gas inlets (2015) (8)
CFD simulation on the transient process of coolant mixing phenomenon in reactor pressure vessel (2021) (8)
Results of simulant effect on large corium pool behavior based on COPRA facility (2018) (8)
Neutronic/thermal‐hydraulic design features of an improved lead‐bismuth cooled small modular fast reactor (2019) (8)
Experimental investigations on start‐up performance of static nuclear reactor thermal prototype (2020) (8)
Study on the onset of nucleate boiling in narrow annular channel by genetic neural network (2010) (8)
Development of cladding oxidation analysis code [COAC] and application for early stage severe accident simulation of AP1000 (2015) (8)
Primary radiation damage characteristics in displacement cascades of FeCrAl alloys (2021) (8)
Numerical research on the coupling optimization design rule of the CFETR HCSB blanket using the NTCOC code (2018) (8)
Sub‐channel analysis for Pb‐Bi‐cooled direct contact boiling water fast reactor (2018) (8)
Ammonia-water mixture property code (AWProC) development, verification and Kalina cycle design for nuclear power plant (2016) (8)
Study of boron diffusion models and dilution accidents in nuclear reactor: A comprehensive review (2020) (8)
Simulation of the small modular reactor severe accident scenario response to SBO using MELCOR code (2016) (8)
RELAP5 MOD3.2 modification and application to the transient analysis of a fluoride-salt-cooled high-temperature reactor (2017) (8)
Code improvement, separate-effect validation, and benchmark calculation for thermal-hydraulic analysis of helical coil once-through steam generator (2020) (8)
3D fluid-solid coupling simulation for plate-type nuclear fuel assemblies under the irradiation condition (2020) (8)
Development and verification of molten corium–concrete interaction code (2015) (8)
Review on heat transfer and flow characteristics of liquid sodium (2): Two-phase (2018) (8)
Numerical Simulation on Collapse of Vapor Bubble Using Particle Method (2014) (8)
Program development and study on supercritical CO2-cooled reactor sub-channel thermal hydraulic (2021) (8)
Models development of liquid drops entrainment at a T-junction with a large vertical up branch (2017) (8)
Numerical analysis on flow instability of parallel channels in steam generator for sodium‐cooled fast reactor (2020) (8)
Transient thermal-hydraulic analysis of thermionic space reactor TOPAZ-II with modified RELAP5 (2019) (8)
CFD study on onset of liquid entrainment through ADS-4 branch line in AP1000 (2021) (7)
Flow pattern effect on two-phase pressure drops in vertical upward flow across a horizontal tube bundle (2018) (7)
Multi-objective optimization of helical coil steam generator in high temperature gas reactors with genetic algorithm and response surface method (2022) (7)
Numerical study on the purge gas flow and heat transfer characteristics in helium cooled solid breeder blanket of CFETR (2018) (7)
Numerical analysis of segmented thermoelectric generators applied in the heat pipe cooled nuclear reactor (2021) (7)
Experimental research on heat transfer behavior of large scale two-layer salt melt pool based on COPRA facility (2020) (7)
Experimental simulation of liquid entrainment in ADS-4 depressurization line in AP1000 (2016) (7)
Development of CHF models for inner and outer RPV gaps in a meltdown severe accident (2013) (7)
Thermal-electrical coupling characteristic analysis of the heat pipe cooled reactor with static thermoelectric conversion (2021) (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)
A critical heat flux model for unilateral heating rectangular narrow channel (2020) (7)
Development of a Thermal-Hydraulic Analysis Code and Transient Analysis for a FHTR (2014) (7)
Experimental research on flow instability in vertical narrow annuli (2007) (7)
Hybrid medium model for conjugate heat transfer modeling in the core of sodium-cooled fast reactor (2020) (7)
Simulation of the PHEBUS FPT-1 experiment using MELCOR and exploration of the primary core degradation mechanism (2015) (7)
Numerical simulation of zircaloy-water reaction based on the moving particle semi-implicit method and combined analysis with the MIDAC code for the nuclear-reactor core melting process (2020) (7)
Theoretical prediction of single bubble motion in vertically upward two-phase flow across inclined tube bundles (2019) (7)
ECC condensation research in T-junction (2016) (7)
Simulation on mass transfer at immiscible liquid interface entrained by single bubble using particle method (2020) (7)
Development of the analysis tool for the water cooling type passive residual heat removal system of Chinese pressurized reactor (2016) (7)
Study on dryout point by wavelet and GNN (2010) (7)
Isothermal experiments on steam oxidation of magnetron-sputtered chromium-coated zirconium alloy cladding at 1200℃ (2022) (7)
Development of a transient thermal-hydraulic code for analysis of China Demonstration Fast Reactor (2013) (7)
Experimental study of the helium flow characteristics in pebble-bed under the condition of CFETR's blanket module (2017) (7)
A new method on fluid-to-fluid scaling for heat transfer in tubes at supercritical pressures (2018) (7)
Numerical study on cooling characteristics in granular and liquid spallation targets (2017) (7)
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)
Thermoelectric performance study on a heat pipe thermoelectric generator for micro nuclear reactor application (2021) (6)
Numerical simulation of temperature heterogeneity inside the AP1000 upper plenum and hot leg (2020) (6)
A porous medium model for simulating conjugate heat transfer between wire-wrapped fuel bundles under forced and mixed convection (2021) (6)
Heat transfer analysis of heat pipe cooled device with thermoelectric generator for nuclear power application (2022) (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)
Experimental study on flow characteristics of rectangular narrow channel (2020) (6)
Uncertainty analysis of Transportable Fluoride-salt-cooled High-temperature Reactor (TFHR) using coupled DAKOTA with RELAP-3D method (2017) (6)
Design and heat transfer optimization of a 1 kW free-piston stirling engine for space reactor power system (2021) (6)
Licensing Considerations of a Fluoride Salt Cooled High Temperature Test Reactor (2013) (6)
Preliminary study of parameter uncertainty influence on thermal design and analysis for sodium heated once-through steam generator (2020) (6)
Numerical investigation of fluid–solid interaction during debris bed formation based on MPS-DEM (2022) (6)
Numerical analysis of melt migration and solidification behavior in LBR severe accident with MPS method (2021) (6)
Transient analysis of tritium transport characteristics of thorium molten salt reactor with solid fuel (2020) (6)
Numerical Study of Integral Inherently Safe Light Water Reactor in Case of Inadvertent DHR Operation Based on the Multiscale Method (2018) (6)
Operation and safety analysis of space lithium-cooled fast nuclear reactor (2022) (6)
Energy allocation optimization of the gas-cooled space nuclear reactor (2021) (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)
Large eddy simulation on the mixing characteristics of liquid sodium at the core outlet of sodium cooled fast reactors (SFR) (2021) (6)
Development of the FHR advanced natural circulation analysis code and application to FHR safety analysis (2016) (6)
Analysis on the behavior of dispersed plate-type fuel based on fluid-solid coupling method (2020) (6)
Flow and heat transfer analysis of lead–bismuth eutectic flowing in a tube under rolling conditions (2021) (6)
Optimization of vapor anode multi-tube alkali metal thermoelectric converter based on an integrated model (2020) (6)
Experimental Investigation of Air-Water CCFL in the Pressurizer Surge Line of AP1000 (2016) (6)
Experimental study on fragmentation characteristics of molten aluminum/copper jet penetrating in sodium pool (2019) (6)
A fusion–fission hybrid reactor with water-cooled pressure tube blanket for energy production (2013) (6)
Experiment study on thermal behavior of a horizontal high-temperature heat pipe under motion conditions (2022) (6)
Experimental Study on Heat Transfer of Single-Phase Flow and Boiling Two-Phase Flow in Vertical Narrow Annuli (2002) (6)
Development of a thermal hydraulic code for an integral reactor (2013) (5)
Experimental analysis on thermal characteristics of two-phase water in narrow rectangular channels (2021) (5)
Thermal fatigue analysis of structures subjected to liquid metal jets at different temperatures in the Gen-IV nuclear energy system (2022) (5)
Experimental study on critical heat flux in bilaterally heated narrow annuli (2009) (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)
Experimental investigation on narrow gap heat transfer with porous media under downward-facing horizontal heated surface (2009) (5)
Modeling of early stage droplet spreading based on numerical simulations (2020) (5)
Thermal–hydraulic performance analysis of IPWR during full pressure start-up mode (2013) (5)
Operation performance analysis of a liquid metal droplet radiator for space nuclear reactor (2021) (5)
The effects of core zoning on optimization of design analysis of molten salt reactor (2013) (5)
A new unidentified leak detection method based on the EVR ventilation condensate (2017) (5)
Experimental investigations on single-phase convection and critical heat flux in vertical tubes under oscillatory flow condition (2020) (5)
Study on the flow and heat transfer characteristics of liquid sodium in a hexagonal 7-rod bundle (2022) (5)
Investigation on thermo-mechanical performance of fully ceramic microencapsulated fuel (2021) (5)
Study on flow instability in natural circulation loop with parallel channels under moving condition (2021) (5)
Thermal–hydraulic analysis of space nuclear reactor TOPAZ-II with modified RELAP5 (2019) (5)
Experimental study of raining effect on the inner surface of containment roof (2020) (5)
Review of the AFD-type CHF mechanistic model and its application to rod bundle (2020) (5)
3D-2D coupling multi-dimension simulation for the heat pipe micro-reactor by MOOSE&SAM (2021) (5)
Development of a thermal–hydraulic analysis code for the Pebble Bed Water-cooled Reactor (2011) (5)
Study effects of the kinetics of local composition diffusion on the melt pool coolability by developing a DBL-LIVE model (2016) (5)
Thermal‐hydraulic design and analysis of a small modular molten salt reactor (MSR) with solid fuel (2018) (5)
Preliminary numerical investigation of TRISO-matrix interface debonding characteristics in fully ceramic microencapsulated fuel (2021) (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)
Numerical analysis for a molten salt reactor in the presence of localized perturbations (2012) (5)
Analytical model for CHF in narrow gaps with surface orientation effects (2011) (5)
Reactor Core Design and Analysis for a Micronuclear Power Source (2018) (5)
Numerical investigation of natural convection characteristics of a heat pipe-cooled passive residual heat removal system for molten salt reactors (2020) (5)
Parametric investigation of radiation heat transfer and evaporation characteristics of a liquid droplet radiator (2020) (5)
Numerical investigation on heat transfer characteristics of helium‐xenon gas mixture (2020) (5)
Neutronics/Thermal-hydraulics Coupling Analysis for the Liquid-Fuel MOSART Concept (2017) (5)
A modified system analysis code for thermo-hydraulic calculation of hydrogen in a nuclear thermal propulsion (NTP) system (2021) (5)
Analysis of the dynamic pressure from ex-vessel steam explosion for pressurized water reactor (2017) (5)
Development and applicability analyses of ADS-4 entrainment model in large advanced PWR (2020) (4)
Preliminary analysis on the thermal-mechanical behavior of dispersed plate-type fuel under reactivity insertion accident (2021) (4)
Development and application of TaSNAM 2.0 for advanced pressurized water reactor (2022) (4)
Numerical and Experimental Investigation on Core Assembly Thermal-Gradient-Induced Deformation of Sodium-Cooled Fast Reactor (2018) (4)
A 3-D simulation tool for hydrogen detonation during severe accident and its application (2017) (4)
Development and application of MOQUICO code to study molten corium-concrete interaction (2020) (4)
Dynamic simulation of a space gas-cooled reactor power system with a closed Brayton cycle (2021) (4)
RELAP5/MOD3.4 calculation and model evaluation based on upper plenum entrainment experiment in AP1000 (2020) (4)
COUPLE, A Time-Dependent Coupled Neutronics and Thermal-Hydraulics Code, and its Application to MSFR (2014) (4)
Experimental research on dryout point of flow boiling in narrow annular channels (2006) (4)
Experiment research on thermal mixing in horizontal T-junction: In-pipe temperature and flow characteristic research (2017) (4)
Oxygen transport analysis in lead-bismuth eutectic coolant for solid-phase oxygen control (2021) (4)
Reactor core design of UPR-s: A nuclear reactor for silence thermoelectric system NUSTER (2021) (4)
Preliminary design study of a board type radial fuel shuffling sodium cooled breed and burn reactor core (2014) (4)
Experimental investigation of the frictional pressure drop of steam-water two-phase flow in AP1000 surge line (2018) (4)
Research on Enhancement of Natural Circulation Capability in Lead-Bismuth Alloy Cooled Reactor by Using Gas-Lift Pump (2012) (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)
Development of oxidation model for zirconium alloy cladding and application in the analysis of cladding behavior under loss of coolant accident (2022) (4)
Analysis of PWR RPV lower head SBLOCA scenarios with the failure of high-pressure injection system using MAAP5 (2014) (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)
Numerical study of laminar flow and friction characteristics in narrow channels under rolling conditions using MPS method (2019) (4)
Assessment of ECCMIX component in RELAP5 based on ECCS experiment (2020) (4)
Thermal-hydraulic analysis of heat pipe reactor experimental device with thermoelectric generators (2022) (4)
LES study on the turbulent thermal stratification and thermo-mechanical fatigue analysis for NPP surge line (2022) (4)
Numerical Solution on Spherical Vacuum Bubble Collapse Using MPS Method (2010) (4)
Analysis of Westinghouse MB2 test using the Steam-generator Thermohydraulics Analysis code STAF (2015) (4)
Prediction of dryout-type CHF for rod bundle in natural circulation loop under motion condition (2020) (4)
Heart, a Specific Code for Thermal-Electrical Analysis of Heat Pipe Cooled Nuclear Reactor (2022) (4)
Numerical evaluation of non-condensable gas influence on the heat transfer characteristics of high-temperature lithium heat pipe during reactor operation (2022) (4)
The code development and thermo-hydrodynamic analysis of the reflood during severe accident in PWR (2017) (4)
Heat transfer characteristics in super-low finned-tube bundles of moisture separator reheaters (2019) (4)
Evaluation of Static Thermophysical Properties of the Ternary Molten Salt System Li, Na and Be/F Based on the Modified Peng-Robinson Equation (2008) (4)
A study on the dynamic characteristics of the secondary loop in nuclear power plant (2020) (4)
Fragmentation characteristics of molten materials jet dropped into liquid sodium pool (2019) (3)
Calibration of a compact magnetic proton recoil neutron spectrometer (2016) (3)
Accident Process and Core Thermal Response During a Station Blackout Initiated Study for Small Modular Reactor (2018) (3)
Development of safety analysis code for SCWR and its LOCA analysis of CSR1000 (2018) (3)
A dryout mechanism model for rectangular narrow channels at high pressure conditions (2020) (3)
Phenomena identification and ranking table of station blackout accidents for China sodium cooled fast reactor (2021) (3)
Model application research for liquid entrainment through ADS-4 pipe in AP1000 (2017) (3)
Numerical study on the thermal-hydraulic characteristics of the choked flow through micro cracks for various conditions (2020) (3)
Theoretical Research on Flow Instability in Parallel Channels Under Motion Conditions (2013) (3)
Development of fuel rod behavior analysis code and its application to supercritical CO2 cooled nuclear reactor (2021) (3)
Code development and analysis of heat pipe cooled passive residual heat removal system of Molten salt reactor (2020) (3)
Numerical simulation of micro-crack leakage on steam generator heat transfer tube (2021) (3)
Development of TSACO and application to Chinese HCCB TBM cooling system (2013) (3)
Loss-of-Flow-Accidents (LOFA) Study for 100 MW IPWR (2014) (3)
Development of a compact magnetic proton recoil spectrometer for measurement of deuterium-tritium neutrons. (2015) (3)
Numerical study of bubble rising in quiescent liquid under rolling motion conditions using MPS – MAFL method (2019) (3)
Density Wave Instability of Sodium Boiling Two-phase Flow in a Vertical Annulus at Low Pressure (2003) (3)
Analysis of flow instabilities in forced-convection steam generator (2006) (3)
Transient analysis of tritium transport characteristics in fluoride-salt-cooled high-temperature reactor (2019) (3)
Numerical investigation of dynamic characteristics of debris bed formation based on CFD-DEM method (2023) (3)
Development and application of SANPR with coupling numerical methods for analysis of effect of moving condition on natural circulation of nuclear power system (2019) (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)
Convection of internal-heated two-layer fluids with deformable interface under swinging motion conditions (2020) (3)
Research on the nuclear fuel rods melting behaviors by alternative material experiments (2021) (3)
Experimental investigations on leak flow rate characteristics of water through axial artificial microcracks of steam generator tubes under back pressure conditions (2019) (3)
Study on the water seal formation process in advanced PWR pressurizer using CFD method (2020) (3)
Development of VTSAS 1.0 and application to an IPWR (2013) (3)
Conceptual design and comprehensive optimization analysis of a fusion-fission hybrid reactor water-cooled pressure tube blanket (2018) (3)
Numerical investigation for the heat transfer mechanisms between subchannels of bar rod bundles cooled by liquid sodium (2021) (3)
Theoretical investigation on the steady-state natural circulation characteristics of a new type of pressurized water reactor (2006) (3)
Spatial temperature distribution of fuel assembly pre-simulation for a new simple core degradation experiment (2019) (3)
A new method to simulate dispersion plate-type fuel assembly in a multi-physics coupled way (2022) (3)
Study on Flow Boiling Characteristics in Rectangle Channel After Formation of Blisters (2021) (3)
Analysis on natural circulation capacity of the CARR (2007) (3)
Investigation of Pressure Drop for Fluid Flow Through Porous Media: Application to a Pebble-Bed Reactor (2010) (3)
Experimental Study on Dryout Point in Vertical Narrow Annulus Under Low Flow Conditions (2004) (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)
An analysis of incipient boiling superheat in alkali liquid metals (2014) (3)
Development of a transient module based on FROBA-ROD code and assessment for fuel rod performance under reactivity-initiated accident (2021) (3)
PIV measurement and numerical investigation on flow characteristics of simulated fast reactor fuel subassembly (2020) (3)
Research of two‐phase density wave instability in reactor core channels with rolling motion (2020) (3)
Experimental study on the influence of heating surface inclination angle on heat transfer and CHF performance for pool boiling (2021) (3)
Generating Hexahedral Mesh for Wire-wrapped Fuel Assembly With RBF Mesh Deformation Method (2021) (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)
Experimental and numerical investigation on flow characteristics of inter-wrapper channel in LMFBR (2021) (3)
MELCOR simulation of the SBLOCA induced severe accident for the SMR in a floating nuclear power plant (2020) (3)
Neutronics influence of poloidal nonuniform neutron wall loading on helium-cooled ceramic breeder blanket for CFETR (2020) (3)
Transient safety analysis for simplified accelerator driven system with gas-lift pump (2018) (3)
Preliminary design and assessment of a heat pipe residual heat removal system for the reactor driven subcritical facility (2021) (3)
A practical methodology devoted to pool‐type phenomena simulation in safety analysis for sodium‐cooled fast reactor (2020) (3)
Parametric sensitivity analysis of liquid metal helical coil once-through tube steam generator (2021) (3)
Experimental Study of Air-Steam–Mixture Condensation Underneath Containment Vessel Surface (2021) (3)
The Research on Core Melting Process: Oxidation (2013) (3)
Transient behavior and maximum heat flux ratios of two-layer corium pool (2022) (3)
Molecular dynamics simulation of the evaporation of liquid sodium film in the presence of non-condensable gas (2022) (3)
Study on startup characteristics of prototype once-through steam generator for China fast reactor (2022) (3)
Numerical research on local heat transfer distribution of liquid sodium turbulent flow in an annulus (2013) (3)
Flow blockage analysis for fuel assembly in a lead-based fast reactor (2021) (3)
Analysis of the Particulate Debris Bed Quenching During Top and Bottom Flood (2014) (3)
CFD/RELAP5 coupling analysis of the ISP No. 43 boron dilution experiment (2021) (3)
Modification and application of Relap5 Mod3 code to several types of nonwater‐cooled advanced nuclear reactors (2018) (3)
Numerical study on improved design of passive residual heat removal system for China pressurizer reactor (2021) (2)
Investigation of fission products distribution effected by spray system in PWR containment during severe accidents (2022) (2)
Numerical method development for oxidation particle formation during sodium spray fires in SFR containment (2020) (2)
Research on pressure drop characteristics in inverted half U-tube bundle under two-phase cross-flow condition (2018) (2)
Experimental investigation on hot water seal over an analogous U-shaped device (2018) (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)
Program development and preliminary CHF characteristics analysis for natural circulation loop under moving condition (2020) (2)
Start-up characteristics for the test facility of a prototype sodium heated OTSG (2021) (2)
Flow characteristics of single-phase flow in narrow annular channels (2008) (2)
Performance of radial fuel shuffling sodium cooled Breed and Burn reactor core (2016) (2)
Experimental study on helium pressure drop across randomly packed bed for fusion blanket (2017) (2)
Analysis for Fuel Rod Performance under LOCA Based on the FROBA-ROD 2.0 Code (2021) (2)
Performance analysis of PRHRS in primary and secondary circuit for offshore floating nuclear plant (2021) (2)
Performance analysis of automatic depressurization system in advanced PWR during a typical SBLOCA transient using MIDAC (2020) (2)
NUMERICAL SIMULATION OF NATURAL CONVECTION HEAT TRANSFER FROM A DOWNWARD-FACING HORIZONTAL ROUND PLATE IN CONFINED SPACE (2007) (2)
Preliminary development and validation of ACENA code for heavy liquid metal-gas two phase flow simulation (2021) (2)
Analysis of AP1000 ex-vessel steam explosion behavior using TEXAS-V code (2015) (2)
CFD simulation of thermal hydraulic phenomena in enclosed cavity of nuclear power plants (2021) (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)
Sub-Channel Analysis of Pb-Bi-Cooled Reactor With Modified COBRA-EN (2014) (2)
Development of thermal hydraulic analysis code of annular fuel under flow blockage condition (2021) (2)
Study on high-temperature hydrogen dissociation for nuclear thermal propulsion reactor (2022) (2)
Numerical studies of stepwise radial fuel shuffling in a traveling wave reactor (2014) (2)
Molecular dynamics study of liquid sodium film evaporation and condensation by Lennard-Jones potential (2022) (2)
Flow and heat transfer evaluation of lead-bismuth eutectic coolant for nuclear power application (2021) (2)
3D Flow Field Analysis for a Traditional II+ PWR Containment Under Normal Condition (2014) (2)
Numerical Study of Bubble Rising and Coalescence Characteristics under Flow Pulsation Based on Particle Method (2019) (2)
Analysis of the natural circulation test of PHENIX reactor by the THACS code (2020) (2)
Thermal-hydraulic performance evaluation of annular fuel based on modified FROBA-ANNULAR (2021) (2)
Experimental Study on Thermal-Hydraulic Performance of Single-Phase Water Flow in Narrow Rectangular Channel (2009) (2)
Thermo-Hydraulic Analysis of the Optimized Helium Cooled Solid Breeder Blanket for CFETR (2016) (2)
Validation of TRACE capability to simulate unprotected transients in Sodium Fast Reactor using FFTF LOFWST Test #13 (2021) (2)
Study on the Coupled Neutronic and Thermal-Hydraulic Characteristics of the New Concept Molten Salt Reactor (2010) (2)
Numerical simulation on thermal‐hydraulic and thermoelectric characteristics of the TOPAZ‐II reactor core (2020) (2)
Theoretical analysis of the characteristics of critical heat flux in vertical narrow rectangular channels under motion conditions (2015) (2)
Parameter sensitivity study on startup characteristics of high temperature potassium heat pipe (2022) (2)
Heat transfer of air turbulent mixed convection in the passive containment air-cooling system of a modular small nuclear reactor (2022) (2)
Natural Convection With Non-Uniform Heat Generation in Molten Salt Reactor (2009) (2)
CFD Simulation of thermal hydraulic characteristics in a typical upper plenum of RPV (2021) (2)
Experimental investigation on heat transfer characteristics of high temperature air in round tube (2021) (2)
CFD simulation based on film model of high temperature potassium heat pipe at different positions: Horizontal, vertical, and 45° inclined (2022) (2)
Numerical study of oxygen transport characteristics in lead-bismuth eutectic for gas-phase oxygen control (2021) (2)
Transient Safety Analysis of a Transportable Fluoride-Salt-Cooled High-Temperature Reactor Using RELAP5-3D (2017) (2)
Numerical approaches and analysis of spray characteristics for pressuriser nozzles (2014) (2)
Development of TSAC1.0 and application to reactivity insertion accident of CARR (2011) (2)
Experimental investigation of entrainment effect on the countercurrent flow in the Hot Leg and Pressurizer Surge Line assembly of third-generation passive nuclear reactors (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)
Mechanism Study and Numerical Simulation on Blistering of Plate-Type Fuel (2016) (2)
SEINA: A two-dimensional steam explosion integrated analysis code (2022) (2)
Numerical simulation of bubble transport during steam generator tube rupture accident of Lead-cooled Fast Reactor (2021) (2)
Experimental research on the influence of rolling motions on the convection behaviors inside two-layer corium pools (2020) (2)
Estimation of thermodynamic properties of the ternary molten salt system, LiF-NaF-BeF2, by the modified Peng-Robinson equation (2007) (2)
Numerical simulation study on the fluid excitation force on a nuclear fuel rod with a spacer grid (2)
Numerical Research on Steady Coupling of Neutronics and Thermal-Hydraulics for a Molten Salt Reactor (2008) (2)
Analysis code development for the direct reactor auxiliary cooling system of the pool-type sodium-cooled fast reactor (2018) (2)
Numerical study on the enhanced heat transfer characteristics of steam generator with axial economizer (2022) (2)
Numerical investigation on radiative and evaporative characteristics of a liquid droplet radiator through Monte-Carlo method (2022) (1)
Experimental investigation of pressure fluctuation and steam transport under SGTR accident in Lead-cooled Fast Reactors (2023) (1)
Numerical investigation on thermohydraulic performance of high temperature hydrogen in twisted rod channels (2021) (1)
Experimental Study on Flow Patterns in Narrow Rectangular Channels (2023) (1)
Thermal-hydraulic analysis of a lead–bismuth small modular reactor under moving conditions (2021) (1)
Analysis of CHF characteristics with fuel rods in the natural circulation system under motion conditions (2022) (1)
An effective method for modeling 1D two-phase two-fluid six-equation model with automatic differentiation approach (2022) (1)
Development of Boron Dilution Model in COBRA-EN (2018) (1)
FISSION REACTORS 221 Analysis of the Limiting Safety System Settings of a Fluoride Salt-Cooled (2014) (1)
Experimental study on fuel rod melting based on alternative materials (2022) (1)
Three-Dimensional Steady Simulation on Two-Phase Flow in Secondary Side of Steam Generator (2013) (1)
Heat transfer characteristics of single-layer and two-layer corium pool in elliptical lower head (2022) (1)
Finite element based fuel performance investigation of U3Si2–FeCrAl design under normal and RIA conditions (2022) (1)
Numerical Investigation on Heat Removal Capacity of Passive Residual Heat Removal Heat Exchanger (2014) (1)
THREE-DIMENSIONAL THERMAL HYDRAULIC ANALYSIS OF A TRANSPORTABLE FLUORIDE-SALT-COOLED HIGH-TEMPERATURE REACTOR (2015) (1)
Study on the Prediction of DNB-Type Critical Heat Flux in Rod Bundle Under Motion Conditions (2018) (1)
Development and validation of thermo-mechanical analysis code of metallic fuel under steady-state conditions in LMFR (2020) (1)
Investigation of single bubble behavior under rolling motions using multiphase MPS method on GPU (2020) (1)
Numerical Study on External Environmental Radiation of Nuclear Ramjet Reactor Tory-Ii C (2022) (1)
COPRA and LIVE tests on transient and steady-state heat transfer in a melt pool (2016) (1)
Preliminary development of a multi-physics coupled fuel performance code for annular fuel analysis under normal conditions (2022) (1)
Experimental and theoretical study on fluid-structure interaction and non-equilibrium of the flow through micro cracks (2020) (1)
Experimental research and theoretical analysis of flow instability in advanced secondary passive residual heat removal system (2023) (1)
Research on Two-Phase Flow Instability in Parallel Multi-Channel Under Rolling Motion Condition (2008) (1)
Analysis on the results of CAP1400 passive containment cooling system during LOCA scenario via integral test (2022) (1)
Modification of FROBA code and its application in Thermal-Mechanical analysis of the Single-Cell thermionic fuel element (2022) (1)
Analysis of CHF characteristics of concentric-tube open thermosyphon by using artificial neural network (2010) (1)
Analysis of heat flux and velocity effects on nucleation superheat in liquid metals based on dynamic effects (2014) (1)
Numerical Investigation on Heat Transfer Characteristics of Helium-Xenon Gas Mixture (2019) (1)
Design and Optimal Thermal Efficiency Contrastive Analysis on Closed Brayton Cycle Systems with Different Fluids of Fluoride-Salt-Cooled High-Temperature Advanced Reactor (2023) (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)
Pressure Drop Experiments of Liquid Sodium Flowing in a 7-Rod Bundle (2018) (1)
Single/multi‐objective optimization and comparative analysis of liquid‐metal heat pipe (2022) (1)
Numerical simulation on the thermal stratification in the lead pool of lead-cooled fast reactor (LFR) (2022) (1)
Neutronics and Thermo-Hydraulic Analysis of Water-Cooled Blanket Based on PWR and SCWR Water Conditions for CFETR (2016) (1)
A best-estimated correlation for prediction of nucleation radius in sodium boiling (2019) (1)
Vapor condensation with low air mass fraction inside water seal branch tube under free convection (2021) (1)
Preliminary conceptual design and analysis of a 100 kWe level Nuclear Silent Thermal‐Electrical Reactor (NUSTER‐100) (2022) (1)
Implementation of Liquid Metal Properties in RELAP5 MOD3.2 for Safety Analysis of Sodium-Cooled Fast Reactors (2017) (1)
Development of a steady thermal-hydraulic analysis code for the China Advanced Research Reactor (2007) (1)
Water film covering characteristic on horizontal fuel rod under impinging cooling condition (2022) (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)
Development of an Ammonia-Water mixture Property Code (AWProC) for Kalina cycle (2014) (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)
Numerical analysis of liquid fall type gas entrainment in pool-type fast reactor (2021) (1)
Theoretical study of steady-state characteristics of natural circulation system (2020) (1)
Numerical Analysis of the Corium Behavior Within the Fuel Support Piece by MPS (2016) (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)
Investigations of near-wall bubble behavior in wire heaters pool boiling (2020) (1)
Numerical investigation of oxidation and dissolution behavior in the fuel cladding using MPS-CV method (2021) (1)
Simulation on Pellet-Cladding Mechanical Interaction (PCMI) of Accident Tolerant Fuel (ATF) With Coated Cladding (2017) (1)
THE EXPERIMENTAL STUDY ON DENSITY WAVE INSTABILITY OF LIQUID SODIUM BOILING IN AN ANNULAR CHANNEL (1998) (1)
Application of Film Dryout Model in Liquid Metal CHF Prediction (2014) (1)
Thermal hydraulic investigations and optimization on the EVC system of a PWR by CFD simulation (2015) (1)
An Investigation of Flow, Heat Transfer Characteristic of Annular Flow and Critical Heat Flux in Vertical Upward Round Tube (2006) (1)
Development of the FHR advanced natural circulation analysis (Fancy) code (2015) (1)
Numerical Investigation of Dissolution Reaction between UO 2 and Molten Zry-4 using MPS method (2018) (1)
A deep-learning reduced-order model for thermal hydraulic characteristics rapid estimation of steam generators (2022) (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 turbulent natural convection of air between the open-ended parallel plates with one-side heating (2023) (1)
EXPERIMENTAL AND NUMERICAL INVESTIGATION OF HEAT TRANSFER AND PRESSURE DROP IN STAGGERED ARRANGEMENT HELICALLY FINNED-TUBE BUNDLE (2015) (1)
COPRA Experiments on Melt Pool Behavior With Eutectic NaNO3-KNO3 Simulant (2018) (0)
ICONE23-1792 DEVELOPMENT OF TRANSIENT THERMAL-HYDRAULIC ANALYSIS CODE FOR THE SPACE THERMIONIC REACTOR (2015) (0)
Thermal–hydraulic analysis of space nuclear reactor TOPAZ-II with modified RELAP5 (2019) (0)
Study on criteria and prediction method of liquid fall type gas entrainment in pool-type sodium-cooled fast reactors (2022) (0)
Development and Application of a UTSG Thermal-Hydraulic Analysis Code (2014) (0)
Numerical simulation of natural convection around the dome in the passive containment air-cooling system (2023) (0)
Coupled Analysis of Thermal Hydraulics and Neutronics for a Molten Salt Reactor (2017) (0)
tudy on the characteristic points of boiling curve by using avelet analysis and genetic neural network (2009) (0)
Numerical Analysis for a Molten Salt Reactor in the Presence of Fissile Lump (2012) (0)
Effect of Rolling Motion on Flow Instability of Parallel Rectangular Channels of Natural Circulation (2018) (0)
Numerical Simulation of the Fluid-Solid Mixture Flow Based on the MPS method (2017) (0)
Numerical simulation of corrosion phenomena in oxygen-controlled environment for a horizontal Lead-bismuth reactor core (2022) (0)
Heat transfer of hydrogen with variable properties in a heated tube (2023) (0)
Flow Fluctuations and Flow Friction Characteristics of Lead-Bismuth Eutectic in a Vertical Tube Under Rolling Conditions (2023) (0)
Preliminary Development of a Coupling Environment Based on MOOSE and OpenFOAM and Its Application on Plate Fuel Modeling (2022) (0)
The fouling and thermal hydraulic coupling study on the typical 5 × 5 rod bundle in PWRs (2022) (0)
Numerical simulation on bubble growth and departure by MPS (2011) (0)
An improved MPS-DEM numerical model for fluid–solid coupling problem in nuclear reactor (2022) (0)
Steady-State Multi-Physics Coupling Analysis of Heat Pipe Cooled Reactor Core (2022) (0)
Numerical simulation of Taylor bubble rising in liquid lead-bismuth eutectic based on MPS method (2013) (0)
Transient Thermoelectric Characteristics of the Principle Prototype for the Heat Pipe Cooled Nuclear Silent Themoelectirc Reactor (Nuster) (2023) (0)
Thermal-Hydraulics Design of Water-Cooled Pressure Tube Blanket for a Fusion Driven Subcritical Reactor (2012) (0)
An investigation of characteristics of flow and heat transfer in the two-layer molten pool under swing motion condition (2022) (0)
Performance analysis of the SPRHRS for the 1000 MWe class PWR in coping with station black out (2020) (0)
APPLICATION OF RPI MODEL : PREDICTION OF SUBCOOLED BOILING AND DNB IN VERTICAL PIPES (2015) (0)
Boiling incipience of liquid sodium flow in an annular channel based on wavelet analysis (2020) (0)
Simulation of Molten Corium Concrete Interaction With the MOCO Code (2014) (0)
Research on Natural Convection of Two-Layer Corium Pools (2020) (0)
Melting and relocation behavior of metal and force balance analysis of metallic droplet (2023) (0)
PRELIMINARY NEUTRONIC ANDTRANSIENT ANALYSIS OF A 20 MW THORIUM-BASED MOLTEN SALT REACTOR WITH SOLID FUEL (2015) (0)
Steady-State Thermal-Hydraulic Analysis of a Plate Type Reactor (2008) (0)
Upwinding Meshfree Point Collocation Method for Steady MHD Flow (2010) (0)
Transient and Safety Analysis Code for TP-1 Sodium Cooled TWR (2013) (0)
Numerical Simulation of Concrete Ablation and Corium Cooling for Molten Corium-Concrete Interaction (MCCI) (2020) (0)
DEVELOPMENT OF AN IN-VESSEL SEVERE ACCIDENT ANALYSIS CODE MIDAC (2015) (0)
CorTAF: A nuclear reactor core three-dimensional thermal-hydraulic characteristics analysis code based on OpenFOAM (2023) (0)
1-s2.0-S0149197015300779-main (2015) (0)
Numerical Research on Melt Pool Flow Characteristics Under Rolling Condition (2018) (0)
Droplets Behavior of Hollow-Cone Spray in a Non-Condensable Environment (2002) (0)
Experimental Investigation on Analogous U-Shaped Tube Water Seal in Front of Pressurizer Safety Valve (2016) (0)
Experimental Study on Boiling Two-Phase of Liquid Sodium Along a 7-Rod Bundle – Part I:Pressure Drop Characteristics (2023) (0)
Numerical Simulation on Single Bubble Rising Behavior in Liquid Metal Using Moving Particle Semi-implicit Method (2011) (0)
Study on pool boiling and flow boiling with artificial neural networks (2010) (0)
Optimization Analysis of Nuclear Thermal Coupling for a Small Nuclear Thermal Propulsion (Sntp) Reactor (2023) (0)
Analysis of flow-induced vibration of wire-wrapped fuel assemblies under the liquid metal axial flow in the Gen-IV nuclear reactor (2023) (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)
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)
Experimental Study on Density Wave Instability of Sodium Boiling Two-Phase Flow in an Annulus (2002) (0)
Meshless Local Petrov-Galerkin Method for the Steady Magnetohydrodynamic (MHD) Flow in Rectangular Ducts With Arbitrary Wall Conductivity (2010) (0)
Experimental and Simulative Investigation of ADS-4 Depressurization Process in AP1000 (2016) (0)
SIMULATIONS ON NATURAL CONVECTION OF STRATIFIED MELT POOLS WITH VOLUMETRIC HEAT GENERATION (2019) (0)
NUCLEAR ENGINEERING AND TECHNOLOGY (2019) (0)
Study on the thermal and geometrical parameters of helical coil once-through steam generator system (2021) (0)
ICONE19-43196 Prediction of Periodic Dryout Critical Heat Flux under Flow Oscillation Condition (2011) (0)
Preliminary Analysis of Three ULOFAs Based on the Dual-Functional Lithium Lead Test Blanket Module Configuration in ITER (2010) (0)
Experimental Study on Heat Transfer Characteristics of Leb Flow in a Vertical Tube Under Static and Rolling Conditions (2023) (0)
SIMULATION AND VALIDATION OF TURBULENT MIXING IN CHANNEL WITH NEK5000 (2019) (0)
Validation of THACS for Sodium Cooled Fast Reactor Based on Benchmark Analysis of EBR-II (2014) (0)
Experimental investigation of nano-particle deposited wick Structure's heat transfer characteristics (2022) (0)
A Prediction of the Leakage Through Cracks for Leak Before Break (2014) (0)
Three-dimensional thermal-hydraulic characteristics analysis of plate-type fuel reactor core based on OpenFOAM (2023) (0)
Development of a Thermal-Hydraulic Code for Chinese Helium-Cooled Ceramic Breeder TBM Cooling System (2013) (0)
Development of a hybrid model for fuel performance analysis of spherical fuel elements under normal conditions (2023) (0)
Validation of the ATHROC Code With NUPEC Tests (2016) (0)
Thermionic Conversion Performance Analysis of the Single-Cell Thermionic Fuel Element Based on Froba-Thermion Code (2023) (0)
CFD Analysis of Subcooled Wall Boiling at Shell Side of Steam Generator With TSP (2014) (0)
Numerical Study on Thermal-Hydraulic Characteristics of Lead-Bismuth Loop System Under Moving Conditions (2022) (0)
CFD Simulation of Thermal-Hydraulic Characteristics of Water Seal Structure in PWR Pressurizer (2017) (0)
Validation of Lead-Bismuth Thermal Hydraulic Facilities Based on Modified Relap5 (2022) (0)
The Influence of Non-Uniform Heating on Two-Phase Flow Instability in Parallel Channels (2013) (0)
Thermal Hydraulic Studies of a Fluoride Salt Cooled High Temperature Test Reactor With Different CFD Methods (2014) (0)
Investigation of the Modified RELAP5 MOD 3.2 Capability to Simulate the Transients of the Fluoride-Salt High-Temperature Reactors (2016) (0)
Development of drift-flux correlations for vertical forward bubble column-type gas-liquid lead-bismuth two-phase flow (2022) (0)
The evaporation of nanoscale sodium liquid film on the non-ideal nanostructure surface: A molecular dynamics study (2023) (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)
Development and Verification of Thermal Hydraulic Subchannel Analysis Code for Motion Conditions (2016) (0)
Experimental Investigation on Density Wave Instability of Sodium Boiling Two-Phase Flow in an Annulus (2002) (0)
Experimental Investigation on Critical Heat Flux From Downward-Facing Flat Plate for Different Orientation Angles (2018) (0)
Nuclear Thermal Coupling Optimization of Baffled Ntp Reactor (2023) (0)
Start-Up Simulation of the Improved TOPAZ-II Space Power System (2016) (0)
Numerical studies of stepwise radial fuel shuffling in a traveling wave reactor (2014) (0)
Preliminary study on FROBA-SCO2 with transient models and its application for Reactivity Initiated Accident and loss of flow accident (2022) (0)
K-2206 Experimental Study on Heat Transfer of Boiling Two-Phase Flow in Narrow Annular Channel (2001) (0)
ICONE23-1570 THE FLOW AND HEAT TRANSFER CHARACTERISTICS OF A PASSIVE RESIDUAL HEAT REMOVAL SYSTEM UNDER OCEAN CONDITIONS (2015) (0)
A Subchannel Analysis Code Star for Sodium-Cooled Fast Reactor (2022) (0)
Transient Safety Analysis of 125mwth Fluoride-Salt-Cooled High-Temperature Advanced Reactor (2023) (0)
Water Hammer Characteristics for Parallel Pumps Water Supply Systems (2008) (0)
Numerical investigation on the dryout point of annular flow in the upward narrow annuli with bilateral heating (2007) (0)
A framework of the transport model for high-order eddy viscosity tensor in two-dimensional turbulent flow (2023) (0)
The Code Development for the Thermo-Hydrodynamic Characteristics Study of Reflood Phase (2014) (0)
Steady-State Thermal-Hydraulic Analysis of a Particle-Bedded Boiling Water Reactor (2009) (0)
An Innovative Method for the Theoretical Investigation on the Critical Heat Flux of Nanofluid Flow Boiling With Nanoparticle Deposition (2021) (0)
Numerical Study on the Thermal Stratification Phenomenon in the Sodium-Cooled Fast Reactor (2019) (0)
Experimental and numerical investigation on characteristics of MCCI with exothermic thermite (2021) (0)
The Severe Accident Analysis of CPR1000 Based on MELCOR Code (2013) (0)
Study on the Improvement of TOPAZ-II system by Using a Heat Pipe Radiator (2015) (0)
Probability analysis of ex-vessel steam explosion induced pressure load based on analysis code SEINA (2022) (0)
Investigation on the Accident of Loss of Offsite Power of CARR (2010) (0)
Hydraulic Characteristics Research on SG Under Tube Plugging Operations Using FLUENT (2018) (0)
Neutronic/Thermal-Hydraulic Coupling Analysis of Heat Pipe Reactor Nuster-100 Based on Comsol (2022) (0)
Thermoelectric Characteristics Analysis of TOPAZ-II (2019) (0)
Numerical Research on Fuel Rod Progression During Core Degradation Process Using MELCOR (2018) (0)
Thermal hydraulic design and analysis of Thorium-based Advanced CANDU Reactor (TACR) (2017) (0)
Data for: A best-estimated correlation for prediction of nucleation superheat in sodium-cooled fast reactor (2019) (0)
Thermal-Hydraulic Analysis of Design Basis Accidents for Chinese Helium-Cooled Solid Breeder TBM (2012) (0)
Experimental Study on the Thermal Hydraulic Characteristics of Liquid Sodium Flowing in an Annulus (2014) (0)
Development and Basic Verification of Decay Heat Removal Analysis Code of Sodium-Cooled Fast Reactor (2018) (0)
Experimental study on boiling two-phase of liquid sodium along a 7-rod bundle – Part Ⅱ: Heat transfer characteristics (2023) (0)
CFD Simulation of a 61-pin Wire-wrapped Fuel Subassembly for Sodium Cooled Fast Reactor (2017) (0)
Program development for mass flowrate distribution optimization in the nuclear power plant (2023) (0)
THREE DIMENSIONAL THERMAL HYDRAULIC COUPLING METHOD ON PWR STEAM GENERATOR USING CFD METHOD (2019) (0)
Experimental Study on Natural Circulation in a Lead Bismuth Eutectic Loop (2017) (0)
Safety Analyses for Pb-Bi-Cooled Direct Contact Boiling Water Fast Reactor (PBWFR) (2014) (0)
CONCEPTUAL DESIGN OF A MICRO NUCLEAR REACTOR POWER SOURCE FOR MULTI-APPLICAITON (2019) (0)
ICONE19-43372 Numerical Simulation of Opposing Mixed Convection Heat Transfer of Lithium-Lead in a Vertical Square Channel with Heat Source (2011) (0)
Numerical Study on the Heat Transfer Characteristics of COPRA-L1 Melt Pool Based on the LES Method (2016) (0)
Experimental Investigation and Model Analysis on Upper Plenum Entrainment in AP1000 (2018) (0)
Prediction of Post-Dryout Heat Transfer in Vertical Annular Channels Using Artificial Neural Network Method (2008) (0)
Design and Optimization of the Heat Transport and Passive Residual Heat Removal System for Fluoride-Salt-Cooled High-Temperature Advanced Reactor (FuSTAR) (2022) (0)
Numerical Analysis on the Thermal-Hydraulic Characteristics for the Reactor Main Vessel Cooling System of Chinese Sodium Cooled Fast Reactor (2021) (0)
Impact of axial power distribution on thermal-hydraulic characteristics for thermionic reactor (2021) (0)
An experimental review of steam generator tube rupture accident in lead-cooled fast reactors: Thermal-hydraulic experiments classification and methods introduction (2023) (0)
Thermohydraulic and Safety Analysis for CARR Under Station Blackout Accident (2006) (0)
MULTIPLE SOLVERS FOR IMPLICIT TEMPERATURE CALCULATION OF HEAT CONDUCTION WITH THE MPS METHOD (2022) (0)
Experimental Research on Dryout Point of Flow Boiling in Narrow Annuli (2006) (0)
Transient Analysis of CP300 Based on RELAP5/MOD3.4 (2014) (0)
Transient Thermal Behaviors of SBO Accident for a 200MW OFNP Under Heaving Motion Conditions (2018) (0)
DETONATION CHARACTERISTICS OF H2-AIR DILUTED WITH N2 IN SMOOTH TUBE (2019) (0)
EFFECTS OF HEAVING CONDITION ON CHARACTERISTICS OF SYSTEM UNDER FORCED CIRCULATION AND NATURAL CIRCULATION (2019) (0)
Experimental Investigation of Liquid Entrainment in ADS-4 Branch Line (2014) (0)
Numerical Research on Oscillation of Two-Phase Flow Under Rolling Motion (2010) (0)
FLUENT-based computationfor a time-space-dependent neutron kinetics model (2015) (0)
THREE-DIMENSIONAL THERMAL HYDRAULIC ANALYSIS OFA TRANSPORTABLE FLUORIDE-SALT-COOLED HIGH-TEMPERATURE REACTOR (2015) (0)
Experimental Studies on the Thermal-Hydraulics of Dowtherm A Through the Pebble Bed With Internal Heat Generation (2018) (0)
Design and Optimal Thermal Efficiency Analysis on Closed Brayton Cycle System of Fluoride-Salt-Cooled High-Temperature Advanced Reactor (Fustar) (2022) (0)
ICONE23-1537 EFFECTIVENESS ANALYSIS OF SEVERE ACCIDENT MANAGEMENT STRATEGIES IN LOCA SCENARIOS FOR AP1000 (2015) (0)
Molecular dynamics simulation of tensile deformation behavior of single-crystal Fe–Cr–Al before and after irradiation (2022) (0)
Numerical and experimental analysis of LBE flow and heat transfer characteristics in hexagonal rod bundles (2023) (0)
Data for: Radiative and evaporative analysis of a liquid droplet layer for space applications (2019) (0)
Extension of GeN-Foam to modeling of boiling water and validation against the OECD/NRC PSBT benchmark (2023) (0)
Characterization and Experimental Investigation for the Dynamic Performance of the Hydraulically Suspended Passive Shutdown System in China Sodium-Cooled Fast Reactor (2018) (0)
Sacos-Plate: A New Thermal-Hydraulic Subchannel Analysis Code for Plate Type Fuel Assemblies (2023) (0)
Retraction notice to “Core design and analysis of a lead-bismuth cooled small modular reactor” [Ann. Nucl. Energy 133 (2019) 511–518/6850] (2022) (0)
Corrigendum to “Entrainment at T-junction: A review work” [Prog. Nucl. Energy 70 (January 2014) 221–241] (2014) (0)
Study of the Behaviors of an Open-Loop Heat-Removal System (2018) (0)
Theoretical and Experimental Research on the Single-Phase and Incipient Boiling Heat Transfer of Liquid Metal Sodium (2017) (0)
Fast Neutron Multiplicity Simulation of Nuclear Material Based on Geant4 (2016) (0)
Simulation on Pellet–Cladding Mechanical Interaction of Accident Tolerant Fuel With Coated Cladding (2019) (0)
BEPU Analysis in LBLOCA Safety Review Calculation (2021) (0)
Experimental Study on Post-Dryout Heat Transfer of Dispersed Flow in Vertical Narrow Annuli (2004) (0)
Development of Drift Flux-Type Correlations Considering Bubble Induced Turbulence in Vertical Gas-Liquid Metal Two-Phase Flow (2022) (0)
NUMERICAL INVESTIGATION ON THE MELTING BEHAVIOR MECHANISM OF FUEL ROD USING MPS-CV METHOD (2019) (0)
CFD Analysis of Cross Flow in Rod Bundles Under Rolling Motion (2016) (0)
THE MECHANISM OF ENHANCEMENT OR DETERIORATION FOR NANOFLUID FLOW BOILING BASED ON THE EXPERIMENTAL RESULTS (2019) (0)
Simulation on the Thermal Hydraulics of the Coolant in a Pebble Bed Reactor Core by CFD (2009) (0)
Study on the safety characteristics of molten corium in-vessel retention of annular fuel core (2023) (0)
Development of a PCCS module in the ATHROC for simulation of passive containment cooling system (2022) (0)
Development of Safety Analysis Code TACOS and Application to Fuel Qualification Test Loop (2017) (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)
ICONE19-43215 NUMERICAL RESEARCH ON THE THERMAL HYDRAULICS OF THE COOLANT IN A PEBBLE BED REACTOR CORE BY CFD (2011) (0)
Numerical investigation on heat transfer and pressure drop characteristics of moisture separator reheater with porous media method (2022) (0)
Steady Thermal Hydraulics Analysis for a Graphite-Moderated Channel Type Molten Salt Reactor (2008) (0)
Tritium Transport Characteristics Analysis in Molten Salt Reactor Under Transient Conditions (2018) (0)
Experimental Study on Spray Pattern of Pressure-Swirl Nozzle in Reactor Containment (2018) (0)
EXPERIMENTAL STUDY ON VOID FRACTION OF ECCS TWO-PHASE FLOW (2017) (0)
ICONE23-1996 CFD SIMULATIONS OF THERMAL MIXING AT ECC SAFETY INJECTION FOR SINGLE PHASE AND AIR-WATER BUBBLY PHASE FLOW (2015) (0)
Experimental study on thermoelectric characteristics of heat pipe reactor (NUSTER-100) Single Assembly (2022) (0)
Study on three-dimensional numerical simulation of shell and tube heat exchanger of the surface ship under marine conditions (2022) (0)
Experimental Study on the Steam-Water Co-Current Flow Friction Multiplier of the AP1000 Surge Line (2017) (0)
Investigations on thermoelectric characteristic of heat pipe thermoelectric generator waste heat utilization device in nuclear power system (2023) (0)
Transient Study on Sodium Heat Pipe in Passive Heat Removal System of Molten Salt Reactor (2013) (0)
Transient thermal‐hydraulic analysis of heat pipe cooled passive residual heat removal system of molten salt reactor (2020) (0)
Validation of a Code and Effect of Turbulence Model on Predicting Thermal Stratification Phenomena in the Upper Plenum of SFR (2018) (0)
ICONE23-2163 SEVERE ACCIDENT ANALYSIS OF A PWR SPENT FUEL POOL IN CASE OF LOSS OF POOL COOLANT (2015) (0)
Low temperature overpressurization analysis for CPR1000 (2021) (0)
The stability criterion based on the spurious pressure oscillation analysis of MPS method (2022) (0)
The Choose of Decay Heat Removal Systems of SFR (2018) (0)
The Optimization Design of Lower Plenum and Distribution Plates in MSR (2013) (0)
ICONE23-1345 DEVELOPMENT AND VALIDATION OF STAF : A STEAM GENERATOR 3D THERMOHYDRAULICS ANALYSIS CODE BASED ON FLUENT (2015) (0)
Experimental Study on the Critical Heat Flux of Nanofluid Flow Boiling Under Different Conditions (2018) (0)
Natural Circulation Characteristics of an Integral Pressurized Water Reactor (2006) (0)
SIMULATIONS OF ECC SAFETY INJECTION FOR SINGLE PHASE AND STRATIFIED PHASE FLOW (2015) (0)
Experimental Research on Energy Release and Fragments Characteristics Under Molten Materials Discharged Into Liquid Sodium (2018) (0)
Cover Image, Volume 43, Issue 9 (2019) (0)
Molecular dynamics study of the wettability effect on the evaporation of thin liquid sodium film (2023) (0)
An enhanced implicit viscosity ISPH method for simulating free-surface flow coupled with solid-liquid phase change (2022) (0)
High-Fidelity Neutronics and Thermal-Hydraulics Analysis of Helical Cruciform Fuel Based on Small Modular Fhr (2023) (0)
Oxidation behavior and kinetics of magnetron-sputtered Cr-coated Zr alloy cladding in 1000–1300 ℃ steam environment (2023) (0)
A Novel Point Estimate Procedure for IVR Calculations in Core-Molten Severe Accident (2010) (0)
Experimental investigation and modeling of falling film heat transfer on partial dry-out condition (2023) (0)
Analysis of a Loss of Heat Removal Accident in a PWR Spent Fuel Pool (2014) (0)
Development of a Thermal-Hydraulic Analysis Code and Transient Analysis for a Fluoride-Salt-Cooled High-Temperature Test Reactor (2015) (0)
Comparison of Transient Responses for SCWRs With Different Flow Path Designs Under Loss of Flow Accident (2012) (0)
Numerical investigation of natural convection characteristics of a heat pipe-cooled passive residual heat removal system for molten salt reactors (2020) (0)
Development and validation of transient thermal‐hydraulic evaluation code for a lead‐based fast reactor (2021) (0)
ICONE19-43763 DESIGN AND TRANSIENT ANALYSES OF PASSIVE EMERGENCY FEEDWATER SYSTEM OF CPR1000 : PART I: AIR COOLING CONDITION (2011) (0)
Development of a New Method for Simulating Gas-to-Particle Conversion During Sodium Pool Fires in SFR Containment (2020) (0)
Numerical Study on Transverse Mixing Characteristics of Flow Sweeping in Helical Cruciform Rod Bundle (2022) (0)
COPRA EXPERIMENTS ON NATURAL CONVECTION HEAT TRANSFER WITH HIGH RAYLEIGH NUMBERS (2015) (0)
Thermal-Hydraulic Analysis of TOPAZ-II With Modified RELAP5 (2018) (0)
Design, optimization and thermodynamic analysis of SCO2 Brayton cycle system for FHR (2023) (0)
Thermal Hydraulic Analysis of a Passive Residual Heat Removal System for an Integral PressurizedWater Reactor (2015) (0)
Multi-Objective Optimization Design of Plate-type Fuel via Co-simulation Method (2021) (0)
Study on Thermal-Hydraulic Characteristics of Vertical Narrow Rectangular Channel With Large Aspect Ratio Under Transverse Uneven Heating (2018) (0)
Heat Transfer Mechanism Investigation of Bubble Growth on the Superhydrophilic Nano-Structured Surface Using Moving Particle Semi-Implicit Method (2023) (0)
Numerical simulation of pressure force for control rod guide tube in PWR (2022) (0)
Experimental study on critical heat flux in bilaterally heated narrow annuli (2009) (0)
Development of Simulation Codes for Some Accidents in Pressurized Water Reactors (2008) (0)

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Xi'an Jiaotong University

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