Wen-xi Tian
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Wen-xi Tianengineering Degrees
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Mechanical Engineering
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Applied Physics
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Engineering
Wen-xi Tian's Degrees
- PhD Mechanical Engineering University of California, Santa Barbara
- Masters Mechanical Engineering University of California, Santa Barbara
- Bachelors Mechanical Engineering Tsinghua University
Why Is Wen-xi Tian Influential?
(Suggest an Edit or Addition)Wen-xi Tian'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
- 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)
- 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)
- Numerical computation of thermally controlled steam bubble condensation using Moving Particle Semi-implicit (MPS) method (2010) (67)
- Numerical computation of thermally controlled steam bubble condensation using Moving Particle Semi-implicit (MPS) method (2010) (67)
- Study on the characteristics of the sodium heat pipe in passive residual heat removal system of molten salt reactor (2013) (63)
- Two-phase bubbly flow simulation using CFD method: A review of models for interfacial forces (2020) (62)
- Thermal hydraulic phenomena related to small break LOCAs in AP1000 (2011) (62)
- Research on the designed emergency passive residual heat removal system during the station blackout scenario for CPR1000 (2012) (57)
- Natural convection heat transfer in corium pools: A review work of experimental studies (2015) (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)
- 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)
- Simulation and analysis on 10-in. cold leg small break LOCA for AP1000 (2012) (46)
- Preliminary evaluation of U3Si2-FeCrAl fuel performance in light water reactors through a multi-physics coupled way (2018) (45)
- Experimental study on heat pipe thermoelectric generator for industrial high temperature waste heat recovery (2020) (45)
- Experimental investigations on single-phase convection and steam-water two-phase flow boiling in a vertical rod bundle (2017) (43)
- Performance analysis of heat pipe radiator unit for space nuclear power reactor (2017) (43)
- Theoretical Study on the Flow Instability of Supercritical Water in the Parallel Channels (2012) (42)
- Transient behavior of the sodium–potassium alloy heat pipe in passive residual heat removal system of molten salt reactor (2013) (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)
- 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)
- Severe accident analysis for a typical PWR using the MELCOR code (2014) (38)
- Review of Thermal-Hydraulic Issues and Studies of Lead-based fast reactors (2020) (37)
- Preliminary safety analysis of the PWR with accident-tolerant fuels during severe accident conditions (2015) (37)
- Conceptual design and analysis of a multipurpose micro nuclear reactor power source (2018) (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)
- Numerical simulation on void bubble dynamics using moving particle semi-implicit method (2009) (35)
- The development of Module In-vessel degraded severe accident Analysis Code MIDAC and the relevant research for CPR1000 during the station blackout scenario (2014) (34)
- Development of a new Pellet-Clad Mechanical Interaction (PCMI) model and its application in ATFs (2017) (34)
- Experimental research of liquid entrainment through ADS-4 in AP1000 (2014) (33)
- COPRA: A large scale experiment on natural convection heat transfer in corium pools with internal heating (2016) (33)
- Natural convection heat transfer test for in-vessel retention at prototypic Rayleigh numbers – Results of COPRA experiments (2016) (32)
- Analysis of the loss of pool cooling accident in a PWR spent fuel pool with MAAP5 (2014) (32)
- Experimental study on the flow and thermal characteristics of two-phase leakage through micro crack (2019) (31)
- Design and transient analyses of emergency passive residual heat removal system of CPR1000. Part I: Air cooling condition (2011) (31)
- Development of Fuel ROd Behavior Analysis code (FROBA) and its application to AP1000 (2012) (31)
- Core thermal-hydraulic evaluation of a heat pipe cooled nuclear reactor (2020) (31)
- Numerical study on annular tube once-through steam generator using compressible flow model (2012) (30)
- Study on the coolant mixing phenomenon in a 45° T junction based on the thermal-mechanical coupling method (2018) (30)
- A sub-channel analysis code for advanced lead bismuth fast reactor (2013) (30)
- Experimental study on spray characteristics of pressure-swirl nozzles in pressurizer (2014) (30)
- MELCOR simulation of core thermal response during a station blackout initiated severe accident in China pressurized reactor (CPR1000) (2015) (29)
- COPRA experiments on natural convection heat transfer in a volumetrically heated slice pool with high Rayleigh numbers (2016) (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)
- Optimization study for thermal efficiency of supercritical water reactor nuclear power plant (2014) (29)
- An evaluation of designed passive Core Makeup Tank (CMT) for China pressurized reactor (CPR1000) (2013) (29)
- Thermal hydraulic investigations with different fuel diameters of pebble bed water cooled reactor in CFD simulation (2012) (28)
- Development of a thermal–mechanical behavior coupling analysis code for a dual-cooled annular fuel element in PWRs (2016) (27)
- Three-dimensional study on the hydraulic characteristics under the steam generator (SG) tube plugging operations for AP1000 (2019) (26)
- Numerical research on the neutronic/thermal-hydraulic/mechanical coupling characteristics of the optimized helium cooled solid breeder blanket for CFETR (2017) (26)
- Evaluation and optimization of tritium breeding, shielding and nuclear heating performances of the helium cooled solid breeder blanket for CFETR (2017) (25)
- Preliminary design and thermal analysis of a liquid metal heat pipe radiator for TOPAZ-II power system (2016) (25)
- Flow and heat transfer characteristics in plate-type fuel channels after formation of blisters on fuel elements (2019) (25)
- Large eddy simulation on turbulent heat transfer in reactor vessel lower head corium pools (2018) (25)
- Two-dimensional numerical simulation of single bubble rising behavior in liquid metal using moving particle semi-implicit method (2013) (24)
- CFD investigation on thermal hydraulics of the passive residual heat removal heat exchanger (PRHR HX) (2018) (24)
- Development of a MCNP–ORIGEN burn-up calculation code system and its accuracy assessment (2014) (24)
- 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)
- A simple novel analysis procedure for IVR calculation in core-molten severe accident (2011) (23)
- Numerical analysis of the granular flow and heat transfer in the ADS granular spallation target (2018) (23)
- Thermal-hydraulic analysis of the improved TOPAZ-II power system using a heat pipe radiator (2016) (23)
- The development of a zirconium oxidation calculating program module for Module In-vessel Degraded Analysis Code MIDAC (2014) (23)
- Hydrodynamics of two-phase flow in a rod bundle under cross-flow condition (2016) (23)
- Experimental investigation of a novel heat pipe thermoelectric generator for waste heat recovery and electricity generation (2020) (23)
- Simulations of unprotected loss of heat sink and combination of events accidents for a molten salt reactor (2013) (22)
- Mechanism study and theoretical simulation on heat split phenomenon in dual-cooled annular fuel element (2016) (22)
- Pressure drop characteristics of vertically upward flow in inclined rod bundles (2016) (22)
- Numerical study on the turbulent mixing in channel with Large Eddy Simulation (LES) using spectral element method (2019) (22)
- Numerical analysis of the melt behavior in a fuel support piece of the BWR by MPS (2017) (22)
- Development of sub-channel code SACoS and its application in coupled neutronics/thermal hydraulics system for SCWR (2012) (22)
- Accident analyses for china pressurizer reactor with an innovative conceptual design of passive residual heat removal system (2014) (22)
- Steady and transient solutions of neutronics problems based on finite volume method (FVM) with a CFD code (2015) (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)
- Experimental and theoretical investigation of liquid entrainment through small-scaled ADS-4 in AP1000 (2014) (21)
- CFD simulation of flow and heat transfer characteristics in a 5×5 fuel rod bundles with spacer grids of advanced PWR (2020) (21)
- The influence of ocean conditions on thermal-hydraulic characteristics of a passive residual heat removal system (2015) (21)
- Research on thermal hydraulic behavior of small-break LOCAs in AP1000 (2013) (21)
- Three dimensional thermal hydraulic characteristic analysis of reactor core based on porous media method (2017) (21)
- An improved Multiphase Moving Particle Semi-implicit method in bubble rising simulations with large density ratios (2018) (21)
- CFD analysis on subcooled boiling phenomena in PWR coolant channel (2015) (21)
- Numerical research on water hammer phenomenon of parallel pump-valve system by coupling FLUENT with RELAP5 (2017) (21)
- Experimental research on transient critical heat flux in vertical tube under oscillatory flow condition (2011) (20)
- Transient thermal–hydraulic analysis of a space thermionic reactor (2016) (20)
- Numerical investigation on thermal-hydraulic characteristics of NaK in a helical wire wrapped annulus (2019) (20)
- Experimental investigations on single-phase convection and two-phase flow boiling heat transfer in an inclined rod bundle (2019) (20)
- Numerical research on oscillation of two-phase flow in multichannels under rolling motion (2011) (20)
- Experimental study of liquid sodium flow and heat transfer characteristics along a hexagonal 7-rod bundle (2019) (20)
- COPRA experiment and numerical research on the behavior of internally-heated melt pool with eutectic salt (2018) (20)
- Numerical investigation of flow and heat transfer characteristics in plate-type fuel channels of IAEA MTR based on OpenFOAM (2021) (19)
- Investigation of severe accident scenario of PWR response to LOCA along with SBO (2015) (19)
- Experimental study on heat transfer limit of high temperature potassium heat pipe for advanced reactors (2021) (19)
- Theoretical investigations on two-phase flow instability in parallel channels under axial non-uniform heating (2014) (19)
- Current achievements on bubble dynamics analysis using MPS method (2020) (19)
- Coupled analysis for new fuel design using UN and UC for SCWR (2013) (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)
- Preliminary design of the I2S-LWR containment system (2020) (19)
- Three-dimensional numerical simulation of the HECLA-4 transient MCCI experiment by improved MPS method (2019) (18)
- MELCOR severe accident analysis for a natural circulation small modular reactor (2017) (18)
- A comparative study on preliminary performance evaluation of ATFs under normal and accident conditions with FRAP-ATF code (2018) (18)
- Entrainment at T-junction: A review work (2014) (18)
- 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)
- Experimental investigation on the heat transfer performance of high-temperature potassium heat pipe for nuclear reactor (2021) (18)
- Experimental investigation of gas lift pump in a lead-bismuth eutectic loop (2018) (17)
- The characteristics and correlation of saturated pool boiling critical heat flux for downward-facing plain heating surface (2020) (17)
- Numerical simulation of Rayleigh-Taylor Instability with periodic boundary condition using MPS method (2018) (17)
- An experiment study of pressure drop and flow distribution in subchannels of a 37-pin wire-wrapped rod bundle (2020) (17)
- Numerical simulation of three-dimensional flow and heat transfer characteristics of liquid lead–bismuth (2021) (17)
- Development of TACOS code for loss of flow accident analysis of SCWR with mixed spectrum core (2012) (16)
- Subchannel thermal-hydraulic analysis of the fuel assembly for liquid sodium cooled fast reactor (2013) (16)
- Preliminary study of parameter uncertainty influence on Pressurized Water Reactor core design (2013) (16)
- Thermal-hydraulic analysis of a fluoride-salt-cooled pebble-bed reactor with CFD methodology (2016) (16)
- Comparison of CORA & MELCOR core degradation simulation and the MELCOR oxidation model (2014) (16)
- Experimental investigation on steam-water two-phase flow boiling heat transfer in a staggered horizontal rod bundle under cross-flow condition (2018) (16)
- CFD simulation of secondary side fluid flow and heat transfer of the passive residual heat removal heat exchanger (2018) (16)
- Thermal‐hydraulic design features of a micronuclear reactor power source applied for multipurpose (2019) (16)
- Research on the leak-rate characteristics of leak-before-break (LBB) in pressurized water reactor (PWR) (2014) (16)
- Thermal-mechanical coupling behavior analysis on metal-matrix dispersed plate-type fuel (2017) (16)
- Depressurization study of supercritical fluid blowdown from simple vessel (2014) (16)
- Numerical investigation on startup characteristics of high temperature heat pipe for nuclear reactor (2021) (16)
- Preliminary accident analysis of Loss of Off-Site Power and In-Box LOCA for the CFETR helium cooled solid breeder blanket (2017) (16)
- Code development and safety analyses for Pb–Bi-cooled direct contact boiling water fast reactor (PBWFR) (2013) (16)
- Pressure drop characteristics of two-phase flow in a vertical rod bundle with support plates (2016) (16)
- 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)
- Numerical study on the thermal stratification characteristics in the upper plenum of sodium-cooled fast reactor (SFR) (2020) (15)
- Thermal‐hydraulic analysis of an open‐grid megawatt gas‐cooled space nuclear reactor core (2020) (15)
- Development and validation of boron diffusion model in nuclear reactor core subchannel analysis (2019) (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)
- Upgrade of FROBA code and its application in thermal-mechanical analysis of space reactor fuel (2018) (15)
- Experimental investigation on saturated pool boiling CHF for downward facing heating surface with different sizes and aspect ratio (2019) (15)
- A theoretical CHF model for downward facing surfaces and gaps under saturated boiling (2012) (15)
- Scaling analysis of AP1000 ADS-4 entrainment and depressurization (2014) (14)
- Numerical prediction of CHF based on CFD methodology under atmospheric pressure and low flow rate (2019) (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)
- Conceptual design and analysis of a megawatt power level heat pipe cooled space reactor power system (2020) (14)
- Development and preliminary validation of a steam generator 3D thermohydraulics analysis code STAF (2016) (14)
- From melt jet break-up to debris bed formation: A review of melt evolution model during fuel-coolant interaction (2022) (14)
- Experimental investigation of steam-air condensation on containment vessel (2020) (14)
- Development of a multi-compartment containment code for advanced PWR plant (2018) (14)
- Thermal–hydraulic and safety analysis for Chinese helium-cooled solid breeder TBM cooling system (2013) (14)
- Steam condensation on a downward-facing plate in presence of air (2019) (14)
- Analyses of liquid entrainment through ADS-4 in AP1000 during a typical small break LOCA transient (2013) (14)
- A code development for leak before break (LBB) leakage from supercritical to subcritical conditions (2018) (14)
- Water hammer characteristics of integral pressurized water reactor primary loop (2013) (14)
- Review on heat transfer and flow characteristics of liquid sodium (1): Single-phase (2017) (13)
- Experimental study of single-phase flow and heat transfer in rectangular channels under uniform and non-uniform heating (2020) (13)
- Comparative study on effect of air–water and steam–water mediums on liquid entrainment through ADS-4 in AP1000 (2015) (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)
- Numerical simulation on single Taylor bubble rising in LBE using moving particle method (2013) (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 sodium boiling in an annulus (2015) (13)
- Development of a subchannel analysis code for SFR wire-wrapped fuel assemblies (2018) (13)
- Effects of power level on thermal-hydraulic characteristics of steam generator (2015) (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)
- Study of tritium transport characteristics in a transportable fluoride‐salt‐cooled high‐temperature reactor (2018) (13)
- Effect of stratified interface instability on thermal focusing effect in two-layer corium pool (2019) (13)
- Experimental investigation on flow and heat transfer characteristics of lead–bismuth eutectic in circular tubes (2020) (12)
- Prediction of flow boiling heat transfer coefficient in horizontal channels varying from conventional to small-diameter scales by genetic neural network (2019) (12)
- Design and analysis of a free-piston stirling engine for space nuclear power reactor (2020) (12)
- Comparison of Hydrogen Generation Rate between CORA-13 Test and MELCOR Simulation: Clad Solid-Phase Oxidation Models Using Self-Developed Code MYCOAC (2015) (12)
- Development and validation of a new module in the ATHROC for simulation of aerosol particles removal by spray in containment (2020) (12)
- Numerical research on natural convection in molten salt reactor with non-uniformly distributed volumetric heat generation (2010) (12)
- Numerical study on the thermal stratification characteristics of AP1000 pressurizer surge line (2019) (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)
- Three-dimensional numerical study on the effect of sidewall crust thermal resistance on transient MCCI by improved MPS method (2020) (12)
- Multiscale Thermal Hydraulic Study under the Inadvertent Safety Injection System Operation Scenario of Typical Pressurized Water Reactor (2017) (12)
- Numerical study on the heat transfer characteristics of LIVE-L4 melt pool with a partial solidification process (2014) (12)
- Study on the hydrogen risk in venturi scrubber filter of filtered containment venting system under PWR severe accident (2018) (12)
- Experimental study on natural convection heat transfer in a two-layer corium pool based on COPRA facility (2019) (12)
- Experimental study on transient performance of heat pipe-cooled passive residual heat removal system of a molten salt reactor (2020) (11)
- CFD simulation on the flow characteristics in the PWR lower plenum with different internal structures (2020) (11)
- Experimental study and optimized design on electromagnetic pump for liquid sodium (2019) (11)
- Analysis of accidental loss of pool coolant due to leakage in a PWR SFP (2015) (11)
- Study on the characteristic points of boiling curve by using wavelet analysis and genetic neural network (2009) (11)
- Conceptual design and analysis of heat pipe cooled silo cooling system for the transportable fluoride-salt-cooled high-temperature reactor (2017) (11)
- Thermal-hydraulic analysis of the thermoelectric space reactor power system with a potassium heat pipe radiator (2020) (11)
- Experimental research on the incipient boiling wall superheat of sodium (2013) (11)
- Radiative and evaporative characteristics analysis of a liquid droplet layer for space applications (2019) (11)
- Development of subcooled wall boiling model considering bubble sliding in narrow rectangular channel (2022) (11)
- Experimental study on spray characteristics of pressure-swirl nozzle in China advanced PWR containment (2019) (11)
- Thermal-hydraulic analysis code development for sodium heated once-through steam generator (2019) (11)
- Quantification of the effect of Cr-coated-Zircaloy cladding during a short term station black out (2020) (11)
- Numerical study on flow and heat transfer characteristics in the rod bundle channels under super critical pressure condition (2010) (11)
- Study on CHF characteristics in narrow rectangular channel under complex motion condition (2020) (11)
- Development of a thermal–hydraulic analysis software for a passive residual heat removal system (2012) (11)
- Study of traveling wave reactor (TWR) and CANDLE strategy: A review work (2014) (11)
- 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)
- Minor actinide transmutation in a board type sodium cooled breed and burn reactor core (2015) (10)
- Development of a thermal-hydraulic subchannel analysis code for motion conditions (2016) (10)
- Large eddy simulation on the turbulent mixing phenomena in 3×3 bare tight lattice rod bundle using spectral element method (2020) (10)
- Experimental study of the steam condensate dripping behavior on the containment dome (2019) (10)
- Numerical investigation of buoyant effect on flow and heat transfer of Lithium–Lead Eutectic in DFLL–TBM (2012) (10)
- Comparative analysis of auxiliary feedwater system and passive safety system under typical accident scenarios for integrated pressurized water reactor (IPWR) (2019) (10)
- Development of a three-field mechanistic model for dryout prediction in annular flow (2020) (10)
- Thermal‐hydraulic analysis of gas‐cooled space nuclear reactor power system with closed Brayton cycle (2020) (10)
- Local effect model development for the steam generator three dimensional thermal hydraulics analysis code (2020) (10)
- A comprehensive review of the leak flow through micro-cracks (in LBB) for nuclear system: Morphologies and thermal-hydraulic characteristics (2020) (10)
- Experimental and theoretical study on transition boiling concerning downward-facing horizontal surface in confined space (2008) (10)
- Experimental investigation of upper plenum entrainment in AP1000 (2015) (10)
- Theoretical investigation of two-phase flow instability between parallel channels of natural circulation in rolling motion (2019) (10)
- Transient thermal-hydraulic evaluation of lead-bismuth fast reactor by coupling sub-channel and system analysis codes (2018) (10)
- Development of an OpenFOAM solver for numerical simulations of shell-and-tube heat exchangers based on porous media model (2022) (10)
- Numerical investigation on the dissolution kinetics of ZrO2 by molten zircaloy using MPS method (2017) (10)
- Development and application of a neutronics/thermal-hydraulics coupling optimization code for the CFETR helium cooled solid breeder blanket with mixed pebble beds (2017) (9)
- Experimental investigation of liquid entrainment in ADS-4 depressurization line with steam–water (2015) (9)
- Study on the reactor core barrel instantaneous characteristics in case of Loss of Coolant Accident (LOCA) scenarios for loop-type PWR (2017) (9)
- Experimental investigation 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)
- Three dimensional neutronic/thermal-hydraulic coupled simulation of MSR in transient state condition (2014) (9)
- Neutronics and thermo-hydraulic design of supercritical-water cooled solid breeder TBM (2015) (9)
- Thermal hydraulic characteristics analysis of direct residual heat removal system for China pressurized reactor (2016) (9)
- PHEBUS FPT-1 simulation by using MELCOR and primary blockage model exploration (2016) (9)
- Study on the systematic thermal-hydraulic characteristics of helical coil once-through steam generator (2021) (9)
- Numerical study of tritium transport characteristics in Thorium Molten Salt Reactor with Solid Fuel (TMSR-SF) (2018) (9)
- CFD modeling of liquid entrainment through vertical T-junction of fourth stage automatic depressurization system (ADS-4) (2021) (9)
- Experimental and numerical study on helium flow characteristics in randomly packed pebble bed (2019) (9)
- Migration–deposition coupling characteristics and influence of corrosion products on heat transfer in steam generators (2022) (9)
- Numerical Study on the Thermal Hydraulic Characteristics in a Wire-Wrapped Assembly of LFRs (2020) (9)
- Thermoelectric characteristics analysis of thermionic space nuclear power reactor (2019) (9)
- Research on enhancement of natural circulation capability in lead–bismuth alloy cooled reactor by using gas-lift pump (2013) (9)
- Preliminary safety assessment on two LOCAs under ITER-like condition for the optimized CFETR helium cooled solid breeder blanket (2017) (9)
- Experimental investigation on flow regimes and transitions of steam-water two-phase flow in narrow rectangular horizontal channels (2021) (9)
- Automatic differentiation approach for solving one-dimensional flow and heat transfer problems (2021) (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)
- MAAP5 Simulation of the PWR Severe Accident Induced by Pressurizer Safety Valve Stuck-Open Accident (2014) (9)
- Comparative study of transient thermal–hydraulic characteristics of SCWRs with different core design (2013) (9)
- Experimental Evaluation on Heat Transfer Limits of Sodium Heat Pipe with Screen Mesh for Nuclear Reactor System (2022) (9)
- Assessment of the severe accident code MIDAC based on FROMA, QUENCH-06&16 experiments (2021) (9)
- Core design and analysis of a lead-bismuth cooled small modular reactor (2019) (9)
- Experimental study on vertically upward steam-water two-phase flow patterns in narrow rectangular channel (2020) (9)
- Development and verification of molten corium–concrete interaction code (2015) (8)
- CFD simulation on the transient process of coolant mixing phenomenon in reactor pressure vessel (2021) (8)
- Experimental study on thermal hydraulic characteristics of natural circulation loop under motion condition (2022) (8)
- A new method for improving the tritium breeding and releasing performance of China Fusion Engineering Test Reactor phase II helium‐cooled ceramic breeder blanket (2020) (8)
- Review on heat transfer and flow characteristics of liquid sodium (2): Two-phase (2018) (8)
- Simulation of the small modular reactor severe accident scenario response to SBO using MELCOR code (2016) (8)
- Experimental investigations on start‐up performance of static nuclear reactor thermal prototype (2020) (8)
- Thermal Hydraulic and Neutronics Coupling Analysis for Plate Type Fuel in Nuclear Reactor Core (2020) (8)
- Numerical research on the coupling optimization design rule of the CFETR HCSB blanket using the NTCOC code (2018) (8)
- Code development and analysis on the operation of liquid metal high temperature heat pipes under full condition (2021) (8)
- Experimental investigation of liquid entrainment in vertical up tee branch with double-end gas inlets (2015) (8)
- Primary radiation damage characteristics in displacement cascades of FeCrAl alloys (2021) (8)
- Study on the onset of nucleate boiling in narrow annular channel by genetic neural network (2010) (8)
- Numerical analysis on flow instability of parallel channels in steam generator for sodium‐cooled fast reactor (2020) (8)
- Development of thermal hydraulic design code for SFR steam generators (2019) (8)
- Study of flow instability in parallel channel system for water cooled blanket (2019) (8)
- Study of boron diffusion models and dilution accidents in nuclear reactor: A comprehensive review (2020) (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)
- Neutronic/thermal‐hydraulic design features of an improved lead‐bismuth cooled small modular fast reactor (2019) (8)
- Transient thermal-hydraulic analysis of thermionic space reactor TOPAZ-II with modified RELAP5 (2019) (8)
- Sub‐channel analysis for Pb‐Bi‐cooled direct contact boiling water fast reactor (2018) (8)
- Improving the optimization algorithm of NTCOC for application in the HCSB blanket for CFETR Phase II (2018) (8)
- Improvement of RELAP5 code for density wave instability analysis in parallel narrow rectangular channels (2018) (8)
- Code improvement, separate-effect validation, and benchmark calculation for thermal-hydraulic analysis of helical coil once-through steam generator (2020) (8)
- Investigations on post-dryout heat transfer in bilaterally heated annular channels (2006) (8)
- Development of cladding oxidation analysis code [COAC] and application for early stage severe accident simulation of AP1000 (2015) (8)
- Results of simulant effect on large corium pool behavior based on COPRA facility (2018) (8)
- Thermal-electrical coupling characteristic analysis of the heat pipe cooled reactor with static thermoelectric conversion (2021) (7)
- Experimental research on heat transfer behavior of large scale two-layer salt melt pool based on COPRA facility (2020) (7)
- Numerical study on the purge gas flow and heat transfer characteristics in helium cooled solid breeder blanket of CFETR (2018) (7)
- Experimental study of the helium flow characteristics in pebble-bed under the condition of CFETR's blanket module (2017) (7)
- Simulation on mass transfer at immiscible liquid interface entrained by single bubble using particle method (2020) (7)
- Isothermal experiments on steam oxidation of magnetron-sputtered chromium-coated zirconium alloy cladding at 1200℃ (2022) (7)
- Simulation of the PHEBUS FPT-1 experiment using MELCOR and exploration of the primary core degradation mechanism (2015) (7)
- Experimental simulation of liquid entrainment in ADS-4 depressurization line in AP1000 (2016) (7)
- Study on dryout point by wavelet and GNN (2010) (7)
- Numerical study on cooling characteristics in granular and liquid spallation targets (2017) (7)
- ECC condensation research in T-junction (2016) (7)
- Experimental study on heat transfer performance between fluoride salt and heat pipes in the new conceptual passive residual heat removal system of molten salt reactor (2018) (7)
- 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)
- Development of the analysis tool for the water cooling type passive residual heat removal system of Chinese pressurized reactor (2016) (7)
- Numerical analysis of segmented thermoelectric generators applied in the heat pipe cooled nuclear reactor (2021) (7)
- Theoretical prediction of single bubble motion in vertically upward two-phase flow across inclined tube bundles (2019) (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)
- CFD study on onset of liquid entrainment through ADS-4 branch line in AP1000 (2021) (7)
- Development of a transient thermal-hydraulic code for analysis of China Demonstration Fast Reactor (2013) (7)
- Hybrid medium model for conjugate heat transfer modeling in the core of sodium-cooled fast reactor (2020) (7)
- Development of CHF models for inner and outer RPV gaps in a meltdown severe accident (2013) (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 analysis of melt migration and solidification behavior in LBR severe accident with MPS method (2021) (6)
- Thermoelectric performance study on a heat pipe thermoelectric generator for micro nuclear reactor application (2021) (6)
- Development of a subchannel analysis code and its application to annular fuel assemblies (2019) (6)
- Experimental study on flow characteristics of rectangular narrow channel (2020) (6)
- Energy allocation optimization of the gas-cooled space nuclear reactor (2021) (6)
- Design and heat transfer optimization of a 1 kW free-piston stirling engine for space reactor power system (2021) (6)
- Numerical investigation of fluid–solid interaction during debris bed formation based on MPS-DEM (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)
- Operation and safety analysis of space lithium-cooled fast nuclear reactor (2022) (6)
- Effects of nitrogen and carbon monoxide on the detonation of hydrogen-air gaseous mixtures (2019) (6)
- Flow and heat transfer analysis of lead–bismuth eutectic flowing in a tube under rolling conditions (2021) (6)
- Transient analysis of tritium transport characteristics of thorium molten salt reactor with solid fuel (2020) (6)
- Neutronics and Thermal Hydraulics Analysis of a Conceptual Ultra-High Temperature MHD Cermet Fuel Core for Nuclear Electric Propulsion (2018) (6)
- Experiment study on thermal behavior of a horizontal high-temperature heat pipe under motion conditions (2022) (6)
- Numerical simulation of temperature heterogeneity inside the AP1000 upper plenum and hot leg (2020) (6)
- Heat transfer analysis of heat pipe cooled device with thermoelectric generator for nuclear power application (2022) (6)
- Experimental Investigation of Air-Water CCFL in the Pressurizer Surge Line of AP1000 (2016) (6)
- Thermal-hydraulic design of water-cooled pressure tube blanket for a fusion driven subcritical reactor (2013) (6)
- Numerical Study of Integral Inherently Safe Light Water Reactor in Case of Inadvertent DHR Operation Based on the Multiscale Method (2018) (6)
- Analysis on the behavior of dispersed plate-type fuel based on fluid-solid coupling method (2020) (6)
- Uncertainty analysis of Transportable Fluoride-salt-cooled High-temperature Reactor (TFHR) using coupled DAKOTA with RELAP-3D method (2017) (6)
- Development of DETAC and its application to the hydrogen detonation analysis (2015) (6)
- Preliminary study of parameter uncertainty influence on thermal design and analysis for sodium heated once-through steam generator (2020) (6)
- A porous medium model for simulating conjugate heat transfer between wire-wrapped fuel bundles under forced and mixed convection (2021) (6)
- A fusion–fission hybrid reactor with water-cooled pressure tube blanket for energy production (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 a thermal–hydraulic analysis code for the Pebble Bed Water-cooled Reactor (2011) (5)
- Flow Boiling Pressure Drop Characteristics in Rectangular Channels under Uniform and Non-Uniform Heating (2020) (5)
- Study on flow instability in natural circulation loop with parallel channels under moving condition (2021) (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)
- Analytical model for CHF in narrow gaps with surface orientation effects (2011) (5)
- Parametric investigation of radiation heat transfer and evaporation characteristics of a liquid droplet radiator (2020) (5)
- Preliminary numerical investigation of TRISO-matrix interface debonding characteristics in fully ceramic microencapsulated fuel (2021) (5)
- Investigation on thermo-mechanical performance of fully ceramic microencapsulated fuel (2021) (5)
- Thermal‐hydraulic design and analysis of a small modular molten salt reactor (MSR) with solid fuel (2018) (5)
- Thermal fatigue analysis of structures subjected to liquid metal jets at different temperatures in the Gen-IV nuclear energy system (2022) (5)
- Reactor Core Design and Analysis for a Micronuclear Power Source (2018) (5)
- Experimental study of raining effect on the inner surface of containment roof (2020) (5)
- Numerical analysis for a molten salt reactor in the presence of localized perturbations (2012) (5)
- Experimental investigations on single-phase convection and critical heat flux in vertical tubes under oscillatory flow condition (2020) (5)
- Experimental research on the characteristics of steam-water counter-current flow in the Pressurizer Surge Line assembly (2018) (5)
- Study on the flow and heat transfer characteristics of liquid sodium in a hexagonal 7-rod bundle (2022) (5)
- Study effects of the kinetics of local composition diffusion on the melt pool coolability by developing a DBL-LIVE model (2016) (5)
- Operation performance analysis of a liquid metal droplet radiator for space nuclear reactor (2021) (5)
- Review of the AFD-type CHF mechanistic model and its application to rod bundle (2020) (5)
- The effects of core zoning on optimization of design analysis of molten salt reactor (2013) (5)
- Numerical investigation on heat transfer characteristics of helium‐xenon gas mixture (2020) (5)
- A modified system analysis code for thermo-hydraulic calculation of hydrogen in a nuclear thermal propulsion (NTP) system (2021) (5)
- Thermal–hydraulic analysis of space nuclear reactor TOPAZ-II with modified RELAP5 (2019) (5)
- Development of a thermal hydraulic code for an integral reactor (2013) (5)
- Numerical investigation of natural convection characteristics of a heat pipe-cooled passive residual heat removal system for molten salt reactors (2020) (5)
- Experimental research on fragmentation characteristics of molten stainless steel discharged into sodium pool and comparison with molten copper (2020) (5)
- Modeling of early stage droplet spreading based on numerical simulations (2020) (5)
- A new unidentified leak detection method based on the EVR ventilation condensate (2017) (5)
- Research on Enhancement of Natural Circulation Capability in Lead-Bismuth Alloy Cooled Reactor by Using Gas-Lift Pump (2012) (4)
- Numerical evaluation of non-condensable gas influence on the heat transfer characteristics of high-temperature lithium heat pipe during reactor operation (2022) (4)
- LES study on the turbulent thermal stratification and thermo-mechanical fatigue analysis for NPP surge line (2022) (4)
- Analysis of PWR RPV lower head SBLOCA scenarios with the failure of high-pressure injection system using MAAP5 (2014) (4)
- Development of oxidation model for zirconium alloy cladding and application in the analysis of cladding behavior under loss of coolant accident (2022) (4)
- Dynamic simulation of a space gas-cooled reactor power system with a closed Brayton cycle (2021) (4)
- Numerical investigation on bubble condensation and coalescence of bubble pairs using moving particle semi-implicit method (2011) (4)
- Assessment of ECCMIX component in RELAP5 based on ECCS experiment (2020) (4)
- The code development and thermo-hydrodynamic analysis of the reflood during severe accident in PWR (2017) (4)
- Heart, a Specific Code for Thermal-Electrical Analysis of Heat Pipe Cooled Nuclear Reactor (2022) (4)
- Numerical study of laminar flow and friction characteristics in narrow channels under rolling conditions using MPS method (2019) (4)
- Experimental investigation of the frictional pressure drop of steam-water two-phase flow in AP1000 surge line (2018) (4)
- A study on the dynamic characteristics of the secondary loop in nuclear power plant (2020) (4)
- Numerical and Experimental Investigation on Core Assembly Thermal-Gradient-Induced Deformation of Sodium-Cooled Fast Reactor (2018) (4)
- Preliminary design study of a board type radial fuel shuffling sodium cooled breed and burn reactor core (2014) (4)
- A 3-D simulation tool for hydrogen detonation during severe accident and its application (2017) (4)
- Development of a two-fluid based thermal-hydraulic subchannel analysis code with high-resolution numerical method (2021) (4)
- Thermal-hydraulic analysis of heat pipe reactor experimental device with thermoelectric generators (2022) (4)
- Preliminary design and analyses of the helium cooled ceramic breeder blanket for CFETR phase II (2020) (4)
- Development and application of TaSNAM 2.0 for advanced pressurized water reactor (2022) (4)
- Heat transfer characteristics in super-low finned-tube bundles of moisture separator reheaters (2019) (4)
- RELAP5/MOD3.4 calculation and model evaluation based on upper plenum entrainment experiment in AP1000 (2020) (4)
- Development and application of MOQUICO code to study molten corium-concrete interaction (2020) (4)
- Prediction of dryout-type CHF for rod bundle in natural circulation loop under motion condition (2020) (4)
- Experiment research on thermal mixing in horizontal T-junction: In-pipe temperature and flow characteristic research (2017) (4)
- Preliminary analysis on the thermal-mechanical behavior of dispersed plate-type fuel under reactivity insertion accident (2021) (4)
- Development and applicability analyses of ADS-4 entrainment model in large advanced PWR (2020) (4)
- Experimental study on the natural circulation capability and heat transfer characteristic of liquid lead bismuth eutectic (2019) (4)
- Numerical Solution on Spherical Vacuum Bubble Collapse Using MPS Method (2010) (4)
- Oxygen transport analysis in lead-bismuth eutectic coolant for solid-phase oxygen control (2021) (4)
- Analysis of Westinghouse MB2 test using the Steam-generator Thermohydraulics Analysis code STAF (2015) (4)
- Improvement and validation of a sub‐channel analysis code for a lead‐cooled reactor with wire spacers (2020) (4)
- A practical methodology devoted to pool‐type phenomena simulation in safety analysis for sodium‐cooled fast reactor (2020) (3)
- Reactivity feedback evaluation during the start-up of the heat pipe cooled nuclear reactors (2020) (3)
- Parametric sensitivity analysis of liquid metal helical coil once-through tube steam generator (2021) (3)
- Development of TSACO and application to Chinese HCCB TBM cooling system (2013) (3)
- A new method to simulate dispersion plate-type fuel assembly in a multi-physics coupled way (2022) (3)
- Experimental investigations on leak flow rate characteristics of water through axial artificial microcracks of steam generator tubes under back pressure conditions (2019) (3)
- Theoretical Research on Flow Instability in Parallel Channels Under Motion Conditions (2013) (3)
- Development of a three-dimensional method for thermal-hydraulics/neutronics coupling analysis and its application on CFETR helium-cooled solid breeder blanket (2021) (3)
- Experimental Study on Dryout Point in Vertical Narrow Annulus Under Low Flow Conditions (2004) (3)
- Numerical simulation of micro-crack leakage on steam generator heat transfer tube (2021) (3)
- Development of VTSAS 1.0 and application to an IPWR (2013) (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)
- Analysis of the Particulate Debris Bed Quenching During Top and Bottom Flood (2014) (3)
- Development of safety analysis code for SCWR and its LOCA analysis of CSR1000 (2018) (3)
- Analysis on natural circulation capacity of the CARR (2007) (3)
- Numerical study of bubble rising in quiescent liquid under rolling motion conditions using MPS – MAFL method (2019) (3)
- Numerical investigation for the heat transfer mechanisms between subchannels of bar rod bundles cooled by liquid sodium (2021) (3)
- Fragmentation characteristics of molten materials jet dropped into liquid sodium pool (2019) (3)
- Experimental and numerical investigation on flow characteristics of inter-wrapper channel in LMFBR (2021) (3)
- Numerical study on the thermal-hydraulic characteristics of the choked flow through micro cracks for various conditions (2020) (3)
- Experimental Study of Air-Steam–Mixture Condensation Underneath Containment Vessel Surface (2021) (3)
- Flow blockage analysis for fuel assembly in a lead-based fast reactor (2021) (3)
- Modification and application of Relap5 Mod3 code to several types of nonwater‐cooled advanced nuclear reactors (2018) (3)
- Code development and analysis of heat pipe cooled passive residual heat removal system of Molten salt reactor (2020) (3)
- Transient safety analysis for simplified accelerator driven system with gas-lift pump (2018) (3)
- Study on the water seal formation process in advanced PWR pressurizer using CFD method (2020) (3)
- Loss-of-Flow-Accidents (LOFA) Study for 100 MW IPWR (2014) (3)
- Generating Hexahedral Mesh for Wire-wrapped Fuel Assembly With RBF Mesh Deformation Method (2021) (3)
- Development of fuel rod behavior analysis code and its application to supercritical CO2 cooled nuclear reactor (2021) (3)
- Phenomena identification and ranking table of station blackout accidents for China sodium cooled fast reactor (2021) (3)
- Numerical research on local heat transfer distribution of liquid sodium turbulent flow in an annulus (2013) (3)
- Model application research for liquid entrainment through ADS-4 pipe in AP1000 (2017) (3)
- Numerical Simulation on Direct Contact Condensation of Single Bubble in Subcooled Water using MPS method (2010) (3)
- An experiment‐based validation of a system code for prediction of passive natural circulation in sodium‐cooled fast reactor (2020) (3)
- The Research on Core Melting Process: Oxidation (2013) (3)
- Study on startup characteristics of prototype once-through steam generator for China fast reactor (2022) (3)
- Neutronics influence of poloidal nonuniform neutron wall loading on helium-cooled ceramic breeder blanket for CFETR (2020) (3)
- Investigation of Pressure Drop for Fluid Flow Through Porous Media: Application to a Pebble-Bed Reactor (2010) (3)
- Conceptual design and comprehensive optimization analysis of a fusion-fission hybrid reactor water-cooled pressure tube blanket (2018) (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)
- Spatial temperature distribution of fuel assembly pre-simulation for a new simple core degradation experiment (2019) (3)
- Preliminary design and assessment of a heat pipe residual heat removal system for the reactor driven subcritical facility (2021) (3)
- Molecular dynamics simulation of the evaporation of liquid sodium film in the presence of non-condensable gas (2022) (3)
- Transient behavior and maximum heat flux ratios of two-layer corium pool (2022) (3)
- CFD/RELAP5 coupling analysis of the ISP No. 43 boron dilution experiment (2021) (3)
- Transient analysis of tritium transport characteristics in fluoride-salt-cooled high-temperature reactor (2019) (3)
- A dryout mechanism model for rectangular narrow channels at high pressure conditions (2020) (3)
- Numerical investigation of dynamic characteristics of debris bed formation based on CFD-DEM method (2023) (3)
- Research on the nuclear fuel rods melting behaviors by alternative material experiments (2021) (3)
- Development a methodology for evaluating inter‐assembly heat transfer effect through reactor core in system safety analysis of sodium‐cooled fast reactor (2021) (2)
- Preliminary development and validation of ACENA code for heavy liquid metal-gas two phase flow simulation (2021) (2)
- Numerical studies of stepwise radial fuel shuffling in a traveling wave reactor (2014) (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)
- Analysis of the natural circulation test of PHENIX reactor by the THACS code (2020) (2)
- Start-up characteristics for the test facility of a prototype sodium heated OTSG (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)
- Analysis of AP1000 ex-vessel steam explosion behavior using TEXAS-V code (2015) (2)
- Study on high-temperature hydrogen dissociation for nuclear thermal propulsion reactor (2022) (2)
- Sub-Channel Analysis of Pb-Bi-Cooled Reactor With Modified COBRA-EN (2014) (2)
- Thermo-Hydraulic Analysis of the Optimized Helium Cooled Solid Breeder Blanket for CFETR (2016) (2)
- 3D Flow Field Analysis for a Traditional II+ PWR Containment Under Normal Condition (2014) (2)
- Validation of TRACE capability to simulate unprotected transients in Sodium Fast Reactor using FFTF LOFWST Test #13 (2021) (2)
- Three-dimensional validation and analyses of the optimized CFETR HCCB blanket (2020) (2)
- CFD Simulation of thermal hydraulic characteristics in a typical upper plenum of RPV (2021) (2)
- Numerical simulation on thermal‐hydraulic and thermoelectric characteristics of the TOPAZ‐II reactor core (2020) (2)
- CFD simulation based on film model of high temperature potassium heat pipe at different positions: Horizontal, vertical, and 45° inclined (2022) (2)
- Parameter sensitivity study on startup characteristics of high temperature potassium heat pipe (2022) (2)
- Experimental investigation on heat transfer characteristics of high temperature air in round tube (2021) (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 study on improved design of passive residual heat removal system for China pressurizer reactor (2021) (2)
- SEINA: A two-dimensional steam explosion integrated analysis code (2022) (2)
- Mechanism Study and Numerical Simulation on Blistering of Plate-Type Fuel (2016) (2)
- Development of TSAC1.0 and application to reactivity insertion accident of CARR (2011) (2)
- Experimental research on the influence of rolling motions on the convection behaviors inside two-layer corium pools (2020) (2)
- Development of thermal hydraulic analysis code of annular fuel under flow blockage condition (2021) (2)
- CFD simulation of thermal hydraulic phenomena in enclosed cavity of nuclear power plants (2021) (2)
- Numerical simulation study on the fluid excitation force on a nuclear fuel rod with a spacer grid (2)
- Numerical approaches and analysis of spray characteristics for pressuriser nozzles (2014) (2)
- Molecular dynamics study of liquid sodium film evaporation and condensation by Lennard-Jones potential (2022) (2)
- Thermal-hydraulic performance evaluation of annular fuel based on modified FROBA-ANNULAR (2021) (2)
- Numerical study on the enhanced heat transfer characteristics of steam generator with axial economizer (2022) (2)
- Numerical simulation of bubble transport during steam generator tube rupture accident of Lead-cooled Fast Reactor (2021) (2)
- Numerical Study of Bubble Rising and Coalescence Characteristics under Flow Pulsation Based on Particle Method (2019) (2)
- Analysis for Fuel Rod Performance under LOCA Based on the FROBA-ROD 2.0 Code (2021) (2)
- Program development and preliminary CHF characteristics analysis for natural circulation loop under moving condition (2020) (2)
- Performance of radial fuel shuffling sodium cooled Breed and Burn reactor core (2016) (2)
- Experimental investigation on hot water seal over an analogous U-shaped device (2018) (2)
- Numerical method development for oxidation particle formation during sodium spray fires in SFR containment (2020) (2)
- Theoretical analysis of the characteristics of critical heat flux in vertical narrow rectangular channels under motion conditions (2015) (2)
- Research on pressure drop characteristics in inverted half U-tube bundle under two-phase cross-flow condition (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)
- Heat transfer of air turbulent mixed convection in the passive containment air-cooling system of a modular small nuclear reactor (2022) (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)
- Flow and heat transfer evaluation of lead-bismuth eutectic coolant for nuclear power application (2021) (2)
- Experimental study on helium pressure drop across randomly packed bed for fusion blanket (2017) (2)
- Theoretical Study on the Characteristics of Critical Heat Flux in Rectangular Channel of Natural Circulation under Motion Conditions (2020) (1)
- Comparison of CORA and MELCOR Core Degradation Simulation and MELCOR Oxidation Model (2014) (1)
- Numerical Investigation of Dissolution Reaction between UO 2 and Molten Zry-4 using MPS method (2018) (1)
- Analysis on the Rotary Inertial of the Primary Pump for China Advanced Research Reactor (2008) (1)
- A deep-learning reduced-order model for thermal hydraulic characteristics rapid estimation of steam generators (2022) (1)
- Numerical investigation on thermohydraulic performance of high temperature hydrogen in twisted rod channels (2021) (1)
- Heat transfer characteristics of single-layer and two-layer corium pool in elliptical lower head (2022) (1)
- Numerical Investigation on Heat Removal Capacity of Passive Residual Heat Removal Heat Exchanger (2014) (1)
- Water film covering characteristic on horizontal fuel rod under impinging cooling condition (2022) (1)
- Simulation on Pellet-Cladding Mechanical Interaction (PCMI) of Accident Tolerant Fuel (ATF) With Coated Cladding (2017) (1)
- COPRA and LIVE tests on transient and steady-state heat transfer in a melt pool (2016) (1)
- An effective method for modeling 1D two-phase two-fluid six-equation model with automatic differentiation approach (2022) (1)
- Research on scaling analysis and design parameters of integral test facilities for PWR (2021) (1)
- Numerical Study on External Environmental Radiation of Nuclear Ramjet Reactor Tory-Ii C (2022) (1)
- Investigation of single bubble behavior under rolling motions using multiphase MPS method on GPU (2020) (1)
- Preliminary development of a multi-physics coupled fuel performance code for annular fuel analysis under normal conditions (2022) (1)
- Experimental study on molten corium-concrete interaction with simulant metal and oxide (2022) (1)
- Analysis of heat flux and velocity effects on nucleation superheat in liquid metals based on dynamic effects (2014) (1)
- Thermal-hydraulic research on rod bundle in the LBE fast reactor with grid spacer (2022) (1)
- Three-Dimensional Steady Simulation on Two-Phase Flow in Secondary Side of Steam Generator (2013) (1)
- The Thermal-Hydraulic Analyses of Transients in PBWFR (2012) (1)
- Numerical Investigation of Flow Diffuser Optimization for a PWR Reactor With Code_Saturne: Analysis on EPR Type Reactor (2016) (1)
- Development of a thermo-mechanical coupling code based on an annular fuel sub-channel code (2019) (1)
- Analysis of Heat Transfer and Flow Characteristics of AP1000 Passive Residual Heat Removal Heat Exchanger (2014) (1)
- Preliminary conceptual design and analysis of a 100 kWe level Nuclear Silent Thermal‐Electrical Reactor (NUSTER‐100) (2022) (1)
- Application of Film Dryout Model in Liquid Metal CHF Prediction (2014) (1)
- Experimental investigation of pressure fluctuation and steam transport under SGTR accident in Lead-cooled Fast Reactors (2023) (1)
- Experimental research and theoretical analysis of flow instability in advanced secondary passive residual heat removal system (2023) (1)
- Experimental Study on Flow Patterns in Narrow Rectangular Channels (2023) (1)
- Pressure Drop Experiments of Liquid Sodium Flowing in a 7-Rod Bundle (2018) (1)
- EXPERIMENTAL AND NUMERICAL INVESTIGATION OF HEAT TRANSFER AND PRESSURE DROP IN STAGGERED ARRANGEMENT HELICALLY FINNED-TUBE BUNDLE (2015) (1)
- Numerical investigation on radiative and evaporative characteristics of a liquid droplet radiator through Monte-Carlo method (2022) (1)
- Neutronics and Thermo-Hydraulic Analysis of Water-Cooled Blanket Based on PWR and SCWR Water Conditions for CFETR (2016) (1)
- Development and validation of thermo-mechanical analysis code of metallic fuel under steady-state conditions in LMFR (2020) (1)
- Effects of inclined condition on LOCA for a small offshore reactor with OTSG (2021) (1)
- Analysis of CHF characteristics with fuel rods in the natural circulation system under motion conditions (2022) (1)
- Thermal-hydraulic analysis of a lead–bismuth small modular reactor under moving conditions (2021) (1)
- Numerical simulation on the thermal stratification in the lead pool of lead-cooled fast reactor (LFR) (2022) (1)
- Experimental study on turbulent natural convection of air between the open-ended parallel plates with one-side heating (2023) (1)
- Vapor condensation with low air mass fraction inside water seal branch tube under free convection (2021) (1)
- Development of a steady thermal-hydraulic analysis code for the China Advanced Research Reactor (2007) (1)
- Study on the Prediction of DNB-Type Critical Heat Flux in Rod Bundle Under Motion Conditions (2018) (1)
- Research of Liquid Entrainment Through ADS-4 in AP1000 (2014) (1)
- ICONE23-1836 PRELIMINARY STUDY ON THE EFFECT OF ACCIDENT TOLERANT FUELS ON PWR SEVERE SBO (2015) (1)
- Optimization of Moving Particle Semi-Implicit (MPS) Method and Studying of Flow Instability (2018) (1)
- Implementation of Liquid Metal Properties in RELAP5 MOD3.2 for Safety Analysis of Sodium-Cooled Fast Reactors (2017) (1)
- Parallelization and application of SACOS for whole core thermal-hydraulic analysis (2021) (1)
- Development of Boron Dilution Model in COBRA-EN (2018) (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)
- Neutronic and Thermo-Hydraulic Analyses of Water-Cooled Blanket Based on Pressurized/Supercritical Water Conditions for CFETR (2019) (1)
- Experimental study on fuel rod melting based on alternative materials (2022) (1)
- Numerical analysis of liquid fall type gas entrainment in pool-type fast reactor (2021) (1)
- Finite element based fuel performance investigation of U3Si2–FeCrAl design under normal and RIA conditions (2022) (1)
- Preliminary thermal-hydraulic influence of the poloidal nonuniform neutron wall loading on the CFETR HCCB blanket (2021) (1)
- Single/multi‐objective optimization and comparative analysis of liquid‐metal heat pipe (2022) (1)
- Experimental and theoretical study on fluid-structure interaction and non-equilibrium of the flow through micro cracks (2020) (1)
- Numerical Analysis of Bubble Rising Behavior in a Liquid Metal Using MPS (2011) (1)
- Theoretical study of steady-state characteristics of natural circulation system (2020) (1)
- Numerical investigation of oxidation and dissolution behavior in the fuel cladding using MPS-CV method (2021) (1)
- Investigations of near-wall bubble behavior in wire heaters pool boiling (2020) (1)
- Numerical Analysis of the Corium Behavior Within the Fuel Support Piece by MPS (2016) (1)
- Analysis of a Loss of Heat Removal Accident in a PWR Spent Fuel Pool (2014) (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)
- Study on the thermal and geometrical parameters of helical coil once-through steam generator system (2021) (0)
- NUCLEAR ENGINEERING AND TECHNOLOGY (2019) (0)
- A Prediction of the Leakage Through Cracks for Leak Before Break (2014) (0)
- Experimental investigation of nano-particle deposited wick Structure's heat transfer characteristics (2022) (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)
- Experimental Study on Heat Transfer Characteristics of Leb Flow in a Vertical Tube Under Static and Rolling Conditions (2023) (0)
- Three-dimensional thermal-hydraulic characteristics analysis of plate-type fuel reactor core based on OpenFOAM (2023) (0)
- Validation of the ATHROC Code With NUPEC Tests (2016) (0)
- Validation of Lead-Bismuth Thermal Hydraulic Facilities Based on Modified Relap5 (2022) (0)
- Numerical investigation of natural convection characteristics of a heat pipe-cooled passive residual heat removal system for molten salt reactors (2020) (0)
- Thermal-Hydraulic Analysis of TOPAZ-II With Modified RELAP5 (2018) (0)
- Development of a Thermal-Hydraulic Code for Chinese Helium-Cooled Ceramic Breeder TBM Cooling System (2013) (0)
- Heat Transfer Mechanism Investigation of Bubble Growth on the Superhydrophilic Nano-Structured Surface Using Moving Particle Semi-Implicit Method (2023) (0)
- CFD Analysis of Subcooled Wall Boiling at Shell Side of Steam Generator With TSP (2014) (0)
- Editorial: CFD Applications in Nuclear Engineering (2021) (0)
- Experimental Study on Post-Dryout Heat Transfer of Dispersed Flow in Vertical Narrow Annuli (2004) (0)
- Flow Fluctuations and Flow Friction Characteristics of Lead-Bismuth Eutectic in a Vertical Tube Under Rolling Conditions (2023) (0)
- Development of the Expanding Mandrel Test Facility for Investigation of Zircaloy Cladding Performance Under Loading Strain Rate Similar to Power Ramp (2022) (0)
- Prediction of Post-Dryout Heat Transfer in Vertical Annular Channels Using Artificial Neural Network Method (2008) (0)
- Development and Verification of Thermal Hydraulic Subchannel Analysis Code for Motion Conditions (2016) (0)
- Development of a hybrid model for fuel performance analysis of spherical fuel elements under normal conditions (2023) (0)
- Experimental Investigation and Model Analysis on Upper Plenum Entrainment in AP1000 (2018) (0)
- CFD Simulation of Thermal-Hydraulic Characteristics of Water Seal Structure in PWR Pressurizer (2017) (0)
- Numerical Study on Thermal-Hydraulic Characteristics of Lead-Bismuth Loop System Under Moving Conditions (2022) (0)
- Nuclear Thermal Coupling Optimization of Baffled Ntp Reactor (2023) (0)
- Program development for mass flowrate distribution optimization in the nuclear power plant (2023) (0)
- Extension of GeN-Foam to modeling of boiling water and validation against the OECD/NRC PSBT benchmark (2023) (0)
- The Code Development for the Thermo-Hydrodynamic Characteristics Study of Reflood Phase (2014) (0)
- The evaporation of nanoscale sodium liquid film on the non-ideal nanostructure surface: A molecular dynamics study (2023) (0)
- Multiple solvers for implicit temperature calculation of plate heat conduction with MPS method (2022) (0)
- SIMULATION AND VALIDATION OF TURBULENT MIXING IN CHANNEL WITH NEK5000 (2019) (0)
- Experimental and Theoretical Research on Liquid Entrainment in AP 1000 ADS Blowdown Phase of SBLOCA (2015) (0)
- Experimental investigation and modeling of falling film heat transfer on partial dry-out condition (2023) (0)
- Numerical simulation of Taylor bubble rising in liquid lead-bismuth eutectic based on MPS method (2013) (0)
- Experimental Investigation on Critical Heat Flux From Downward-Facing Flat Plate for Different Orientation Angles (2018) (0)
- Numerical Study on Flow and Heat Transfer in Concentric and Eccentric Annuli (2010) (0)
- Sacos-Plate: A New Thermal-Hydraulic Subchannel Analysis Code for Plate Type Fuel Assemblies (2023) (0)
- Investigation on the Accident of Loss of Offsite Power of CARR (2010) (0)
- Thermal Hydraulic Studies of a Fluoride Salt Cooled High Temperature Test Reactor With Different CFD Methods (2014) (0)
- Preliminary study on FROBA-SCO2 with transient models and its application for Reactivity Initiated Accident and loss of flow accident (2022) (0)
- CONCEPTUAL DESIGN OF A MICRO NUCLEAR REACTOR POWER SOURCE FOR MULTI-APPLICAITON (2019) (0)
- Numerical Study on the Heat Transfer Characteristics of COPRA-L1 Melt Pool Based on the LES Method (2016) (0)
- Thermohydraulic and Safety Analysis for CARR Under Station Blackout Accident (2006) (0)
- ICONE23-1570 THE FLOW AND HEAT TRANSFER CHARACTERISTICS OF A PASSIVE RESIDUAL HEAT REMOVAL SYSTEM UNDER OCEAN CONDITIONS (2015) (0)
- Impact of axial power distribution on thermal-hydraulic characteristics for thermionic reactor (2021) (0)
- Start-Up Simulation of the Improved TOPAZ-II Space Power System (2016) (0)
- ICONE19-43372 Numerical Simulation of Opposing Mixed Convection Heat Transfer of Lithium-Lead in a Vertical Square Channel with Heat Source (2011) (0)
- 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)
- FLUENT-based computationfor a time-space-dependent neutron kinetics model (2015) (0)
- Molecular dynamics simulation of tensile deformation behavior of single-crystal Fe–Cr–Al before and after irradiation (2022) (0)
- Characterization and Experimental Investigation for the Dynamic Performance of the Hydraulically Suspended Passive Shutdown System in China Sodium-Cooled Fast Reactor (2018) (0)
- Transient Analysis of CP300 Based on RELAP5/MOD3.4 (2014) (0)
- Experimental Investigation of Liquid Entrainment in ADS-4 Branch Line (2014) (0)
- Data for: Radiative and evaporative analysis of a liquid droplet layer for space applications (2019) (0)
- Neurtonics/Thermal-hydraulic analyses of the CFETR HCCB blanket for multiple operation modes under the poloidal nonuniform neutron wall loading condition (2021) (0)
- Water Hammer Characteristics for Parallel Pumps Water Supply Systems (2008) (0)
- Numerical studies of stepwise radial fuel shuffling in a traveling wave reactor (2014) (0)
- Transient Safety Analysis of 125mwth Fluoride-Salt-Cooled High-Temperature Advanced Reactor (2023) (0)
- Numerical study on inter-wrapper flow and heat transfer characteristics in liquid metal-cooled fast reactors (2023) (0)
- Simulation on Pellet–Cladding Mechanical Interaction of Accident Tolerant Fuel With Coated Cladding (2019) (0)
- A Subchannel Analysis Code Star for Sodium-Cooled Fast Reactor (2022) (0)
- Numerical and experimental analysis of LBE flow and heat transfer characteristics in hexagonal rod bundles (2023) (0)
- Safety Analyses for Pb-Bi-Cooled Direct Contact Boiling Water Fast Reactor (PBWFR) (2014) (0)
- Experimental Study on Natural Circulation in a Lead Bismuth Eutectic Loop (2017) (0)
- A framework of the transport model for high-order eddy viscosity tensor in two-dimensional turbulent flow (2023) (0)
- Corrigendum to “Entrainment at T-junction: A review work” [Prog. Nucl. Energy 70 (January 2014) 221–241] (2014) (0)
- MULTIPLE SOLVERS FOR IMPLICIT TEMPERATURE CALCULATION OF HEAT CONDUCTION WITH THE MPS METHOD (2022) (0)
- Study on the Improvement of TOPAZ-II system by Using a Heat Pipe Radiator (2015) (0)
- The Severe Accident Analysis of CPR1000 Based on MELCOR Code (2013) (0)
- Tritium Transport Characteristics Analysis in Molten Salt Reactor Under Transient Conditions (2018) (0)
- Experimental and numerical investigation on characteristics of MCCI with exothermic thermite (2021) (0)
- Transient Study on Sodium Heat Pipe in Passive Heat Removal System of Molten Salt Reactor (2013) (0)
- Numerical investigation on heat transfer and pressure drop characteristics of moisture separator reheater with porous media method (2022) (0)
- Design and Optimal Thermal Efficiency Analysis on Closed Brayton Cycle System of Fluoride-Salt-Cooled High-Temperature Advanced Reactor (Fustar) (2022) (0)
- Hydraulic Characteristics Research on SG Under Tube Plugging Operations Using FLUENT (2018) (0)
- Numerical Research on Fuel Rod Progression During Core Degradation Process Using MELCOR (2018) (0)
- Development of a PCCS module in the ATHROC for simulation of passive containment cooling system (2022) (0)
- ICONE23-2163 SEVERE ACCIDENT ANALYSIS OF A PWR SPENT FUEL POOL IN CASE OF LOSS OF POOL COOLANT (2015) (0)
- Probability analysis of ex-vessel steam explosion induced pressure load based on analysis code SEINA (2022) (0)
- Cover Image, Volume 43, Issue 9 (2019) (0)
- Experimental Research on Energy Release and Fragments Characteristics Under Molten Materials Discharged Into Liquid Sodium (2018) (0)
- Neutronic/Thermal-Hydraulic Coupling Analysis of Heat Pipe Reactor Nuster-100 Based on Comsol (2022) (0)
- Thermal-Hydraulic Analysis of Design Basis Accidents for Chinese Helium-Cooled Solid Breeder TBM (2012) (0)
- Transient Thermoelectric Characteristics of the Principle Prototype for the Heat Pipe Cooled Nuclear Silent Themoelectirc Reactor (Nuster) (2023) (0)
- Performance analysis of the SPRHRS for the 1000 MWe class PWR in coping with station black out (2020) (0)
- Investigations on thermoelectric characteristic of heat pipe thermoelectric generator waste heat utilization device in nuclear power system (2023) (0)
- An investigation of characteristics of flow and heat transfer in the two-layer molten pool under swing motion condition (2022) (0)
- Experimental Study on the Steam-Water Co-Current Flow Friction Multiplier of the AP1000 Surge Line (2017) (0)
- An improved MPS-DEM numerical model for fluid–solid coupling problem in nuclear reactor (2022) (0)
- ICONE23-1345 DEVELOPMENT AND VALIDATION OF STAF : A STEAM GENERATOR 3D THERMOHYDRAULICS ANALYSIS CODE BASED ON FLUENT (2015) (0)
- APPLICATION OF RPI MODEL : PREDICTION OF SUBCOOLED BOILING AND DNB IN VERTICAL PIPES (2015) (0)
- Steady-State Multi-Physics Coupling Analysis of Heat Pipe Cooled Reactor Core (2022) (0)
- Numerical simulation on bubble growth and departure by MPS (2011) (0)
- Low temperature overpressurization analysis for CPR1000 (2021) (0)
- Thermal-Hydraulics Design of Water-Cooled Pressure Tube Blanket for a Fusion Driven Subcritical Reactor (2012) (0)
- A Novel Point Estimate Procedure for IVR Calculations in Core-Molten Severe Accident (2010) (0)
- THREE DIMENSIONAL THERMAL HYDRAULIC COUPLING METHOD ON PWR STEAM GENERATOR USING CFD METHOD (2019) (0)
- The fouling and thermal hydraulic coupling study on the typical 5 × 5 rod bundle in PWRs (2022) (0)
- The stability criterion based on the spurious pressure oscillation analysis of MPS method (2022) (0)
- Effect of Rolling Motion on Flow Instability of Parallel Rectangular Channels of Natural Circulation (2018) (0)
- Experimental study on thermoelectric characteristics of heat pipe reactor (NUSTER-100) Single Assembly (2022) (0)
- ICONE23-1537 EFFECTIVENESS ANALYSIS OF SEVERE ACCIDENT MANAGEMENT STRATEGIES IN LOCA SCENARIOS FOR AP1000 (2015) (0)
- Boiling incipience of liquid sodium flow in an annular channel based on wavelet analysis (2020) (0)
- Transient thermal‐hydraulic analysis of heat pipe cooled passive residual heat removal system of molten salt reactor (2020) (0)
- Preliminary Development of a Coupling Environment Based on MOOSE and OpenFOAM and Its Application on Plate Fuel Modeling (2022) (0)
- Numerical simulation of corrosion phenomena in oxygen-controlled environment for a horizontal Lead-bismuth reactor core (2022) (0)
- Theoretical Study on Single Bubble Expansion After Pressurized Subcooled Water Injected in Thermal Glycerin (2021) (0)
- Simulation of Molten Corium Concrete Interaction With the MOCO Code (2014) (0)
- SIMULATIONS OF ECC SAFETY INJECTION FOR SINGLE PHASE AND STRATIFIED PHASE FLOW (2015) (0)
- tudy on the characteristic points of boiling curve by using avelet analysis and genetic neural network (2009) (0)
- Numerical Simulation of Concrete Ablation and Corium Cooling for Molten Corium-Concrete Interaction (MCCI) (2020) (0)
- Theoretical Analysis of Type-I Flow Instability of Natural Circulation (2021) (0)
- Molecular dynamics study of the wettability effect on the evaporation of thin liquid sodium film (2023) (0)
- COPRA EXPERIMENTS ON NATURAL CONVECTION HEAT TRANSFER WITH HIGH RAYLEIGH NUMBERS (2015) (0)
- Development and Application of a UTSG Thermal-Hydraulic Analysis Code (2014) (0)
- Multi-Dimensional Coupling Analysis of the Control Rod Withdraw Accident with Scam in the Typical Lfr (2023) (0)
- Study on criteria and prediction method of liquid fall type gas entrainment in pool-type sodium-cooled fast reactors (2022) (0)
- Multi-physics coupling analysis on neutronics, thermal hydraulic and mechanics characteristics of a nuclear thermal propulsion reactor (2022) (0)
- DEVELOPMENT OF AN IN-VESSEL SEVERE ACCIDENT ANALYSIS CODE MIDAC (2015) (0)
- Development and validation of transient thermal‐hydraulic evaluation code for a lead‐based fast reactor (2021) (0)
- Experimental Investigation on Analogous U-Shaped Tube Water Seal in Front of Pressurizer Safety Valve (2016) (0)
- CorTAF: A nuclear reactor core three-dimensional thermal-hydraulic characteristics analysis code based on OpenFOAM (2023) (0)
- Numerical Study on Transverse Mixing Characteristics of Flow Sweeping in Helical Cruciform Rod Bundle (2022) (0)
- Thermal–hydraulic analysis of space nuclear reactor TOPAZ-II with modified RELAP5 (2019) (0)
- ICONE19-43763 DESIGN AND TRANSIENT ANALYSES OF PASSIVE EMERGENCY FEEDWATER SYSTEM OF CPR1000 : PART I: AIR COOLING CONDITION (2011) (0)
- Grand challenges in advanced nuclear reactor design (2022) (0)
- Multi-Objective Optimization Design of Plate-type Fuel via Co-simulation Method (2021) (0)
- Numerical simulation of pressure force for control rod guide tube in PWR (2022) (0)
- ICONE23-1792 DEVELOPMENT OF TRANSIENT THERMAL-HYDRAULIC ANALYSIS CODE FOR THE SPACE THERMIONIC REACTOR (2015) (0)
- Experimental Study on Boiling Two-Phase of Liquid Sodium Along a 7-Rod Bundle – Part I:Pressure Drop Characteristics (2023) (0)
- ICONE23-1996 CFD SIMULATIONS OF THERMAL MIXING AT ECC SAFETY INJECTION FOR SINGLE PHASE AND AIR-WATER BUBBLY PHASE FLOW (2015) (0)
- Design, optimization and thermodynamic analysis of SCO2 Brayton cycle system for FHR (2023) (0)
- Development of a New Method for Simulating Gas-to-Particle Conversion During Sodium Pool Fires in SFR Containment (2020) (0)
- Numerical Simulation on Single Bubble Rising Behavior in Liquid Metal Using Moving Particle Semi-implicit Method (2011) (0)
- Numerical Simulation of Three Dimensional Internal Flow of a PWR Reactor (2016) (0)
- Coupled Analysis of Thermal Hydraulics and Neutronics for a Molten Salt Reactor (2017) (0)
- EXPERIMENTAL STUDY ON VOID FRACTION OF ECCS TWO-PHASE FLOW (2017) (0)
- An enhanced implicit viscosity ISPH method for simulating free-surface flow coupled with solid-liquid phase change (2022) (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)
- 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)
- High-Fidelity Neutronics and Thermal-Hydraulics Analysis of Helical Cruciform Fuel Based on Small Modular Fhr (2023) (0)
- Experimental Study on Spray Pattern of Pressure-Swirl Nozzle in Reactor Containment (2018) (0)
- Numerical simulation of natural convection around the dome in the passive containment air-cooling system (2023) (0)
- Development of Safety Analysis Code TACOS and Application to Fuel Qualification Test Loop (2017) (0)
- Heat transfer of hydrogen with variable properties in a heated tube (2023) (0)
- Comparison of Transient Responses for SCWRs With Different Flow Path Designs Under Loss of Flow Accident (2012) (0)
- Optimization Analysis of Nuclear Thermal Coupling for a Small Nuclear Thermal Propulsion (Sntp) Reactor (2023) (0)
- Thermal hydraulic design and analysis of Thorium-based Advanced CANDU Reactor (TACR) (2017) (0)
- Experimental and Simulative Investigation of ADS-4 Depressurization Process in AP1000 (2016) (0)
- ICONE19-43215 NUMERICAL RESEARCH ON THE THERMAL HYDRAULICS OF THE COOLANT IN A PEBBLE BED REACTOR CORE BY CFD (2011) (0)
- Preliminary Analysis of Three ULOFAs Based on the Dual-Functional Lithium Lead Test Blanket Module Configuration in ITER (2010) (0)
- Development of a Thermal-Hydraulic Analysis Code and Transient Analysis for a Fluoride-Salt-Cooled High-Temperature Test Reactor (2015) (0)
- NUMERICAL INVESTIGATION ON THE MELTING BEHAVIOR MECHANISM OF FUEL ROD USING MPS-CV METHOD (2019) (0)
- Transient and Safety Analysis Code for TP-1 Sodium Cooled TWR (2013) (0)
- Oxidation behavior and kinetics of magnetron-sputtered Cr-coated Zr alloy cladding in 1000–1300 ℃ steam environment (2023) (0)
- CFD Analysis of Cross Flow in Rod Bundles Under Rolling Motion (2016) (0)
- Study on the safety characteristics of molten corium in-vessel retention of annular fuel core (2023) (0)
- Experimental study on boiling two-phase of liquid sodium along a 7-rod bundle – Part Ⅱ: Heat transfer characteristics (2023) (0)
- Melting and relocation behavior of metal and force balance analysis of metallic droplet (2023) (0)
- Steady-State Thermal-Hydraulic Analysis of a Plate Type Reactor (2008) (0)
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What Schools Are Affiliated With Wen-xi Tian?
Wen-xi Tian is affiliated with the following schools:
