AUTHOR INDEX

A

Abe, Satoshi

Application of Immersed Boundary Method for Jet Flow in Grating Type Structure

CIGMA Experimental Investigation on Heat and Mass Transfer Phenomena Induced by Natural Convection with Density Stratification in the Enclosure Vessel

Addad, Yacine

Numerical Prediction of the Reactor Pressure Vessel Melting under IVR-ERVC Conditions

Ahn, Ji Soo

Quantification of Uncertainties in a SAS-SST Simulation Caused by the Unknown High-Wave Number Damping Factor Using Surrogate Modelling

Airiau, C.

Mass Transfer Measurement in a Rectangular Channel for Heat Transfer Analogy

Aji, Indarta Kuncoro

Study on Melting Process of Solid Salt Contained in Metal Vessel

Akand, M. A. Rafiq

A Modified Liquid Sublayer Dryout Model for Subcooled Flow Boiling Critical Heat Flux Prediction in IVR Condition

Alilou, Youssef

Development of a Numerical Tool to Predict the Thermal and Hydraulic Behavior of a Heat Exchanger

Almadih, Mustafa H.

Acoustic Analysis of the Effects of Vapor-Liquid Interfacial Morphology on Pool-Boiling Heat Transfer

Almudhhi, T.

Acoustic Analysis of the Effects of Vapor-Liquid Interfacial Morphology on Pool-Boiling Heat Transfer

Amidu, Muritala A

Numerical Prediction of the Reactor Pressure Vessel Melting under IVR-ERVC Conditions

An, WeiJian

Non-Nuclear Transient Simulation Experiment of a Heat Pipe Cooled Nuclear Reactor System

Andrs, D.

Sockeye Heat Pipe Code Theory Development: Based on the 7-Equation, Two-Phase Flow Model of RELAP-7

Angeli, Diego

Direct Numerical Simulation of Natural, Mixed and Forced Convection in Liquid Metals: Selected Results

Angeli, Pierre-Emmanuel

Toward an Innovative CFD-Based Upscaling Methodology to Elaborate Closures for the FLICA4 Subchannel Code

Attavino, Andrea

Multicomponent Diffusion Modelling for Light Gases Predictions in Water Cooled Nuclear Reactors

Augier, Loic

CFD Study of an Innovative Safety System for Pressurized Water Reactors

B

Badea, Aurelian Florin

ATHLET Simulation of PKL IBLOCA I2.2 Benchmark Test and Quantitative Assessment

Badel, P.

Advanced Benchmark of the Flow through a Mixing Vane Grid – Large Eddy Simulation Validation

Bajard, S.

Impact of Fuel Pellet-Clad Gap Characteristics on an Unprotected Loss of Flow Transient in a Sodium Fast Reactor

Bajorek, Stephen M.

Acoustic Analysis of the Effects of Vapor-Liquid Interfacial Morphology on Pool-Boiling Heat Transfer

Pressure and Oscillatory Flow Effects on the Two-Phase Flow and Heat Transfer in a Rod Bundle

Bang, Young S.

Multi-Dimensional Calculation of Reflood Behavior in a SCTF Experiment at Partial Blockage Condition

Bao, Han

Demonstration of a Data-Driven Physics-Based Approach for Computationally Efficient CFD Prediction of Two-Phase Bubbly Flow

Bardiaux, Nicolas

Key Learnings of Full Scope Simulator’s Nuclear Steam Supply System (NSSS) Model Re-Hosting Project at EDF

Bartosiewicz, Yann

High Fidelity Simulations in Support to Assess and Improve RANS for Modeling Turbulent Heat Transfer in Liquid Metals: The Case of Forced Convection

Barzilov, Alexander

GeN-FOAM Model of Graphite Moderator of a Molten Salt Reactor

Beck, Faith

Pressure and Oscillatory Flow Effects on the Two-Phase Flow and Heat Transfer in a Rod Bundle

Benhamadouche, Sofiane

Advanced Benchmark of the Flow through a Mixing Vane Grid – Large Eddy Simulation Validation

Blurring the Lines between CAD, Mesh and Solver in Code_Saturne to Improve Predictive Capabilities of Finite Volume CFD Modelling

Towards Direct Numerical Simulation of a 5X5 Rod Bundle

Turbulence Models Assessment for Ascending Mixed Convection Flows

Bergeron, Andr´e

Toward an Innovative CFD-Based Upscaling Methodology to Elaborate Closures for the FLICA4 Subchannel Code

Berry, Ray A.

Multidimensional SAM Equations with Volume Fraction Effects (or Porosity) for Use in Pronghorn

Sockeye Heat Pipe Code Theory Development: Based on the 7-Equation, Two-Phase Flow Model of RELAP-7

Bersano, A.

Experimental Analysis of the Start-Up of a Natural Circulation Loop in Single and Two-Phase Flow

Bertani, C.

Experimental Analysis of the Start-Up of a Natural Circulation Loop in Single and Two-Phase Flow

Bertrand, M.

Validation of the Hydrodynamics in a Turbulent Un-Baffled Vortex-Reactor at Two Different Stirring Reynolds Numbers

Bestion, D.

Some Progress Made in Multiscale Analysis, Multiscale Simulation and Multi-Scale Validation in Reactor Thermalhydraulics

Some Progresses in System Code Modelling Validation and Application Including 3D Modelling

Bieder, Ulrich

Toward an Innovative CFD-Based Upscaling Methodology to Elaborate Closures for the FLICA4 Subchannel Code

Validation of the Hydrodynamics in a Turbulent Un-Baffled Vortex-Reactor at Two Different Stirring Reynolds Numbers

Bigot, B.

Use of CFD Results to Model Heat Transfer in a Thin Metal Layer

Blanc, V.

Impact of Fuel Pellet-Clad Gap Characteristics on an Unprotected Loss of Flow Transient in a Sodium Fast Reactor

Bluck, Michael J.

Quantification of Uncertainties in a SAS-SST Simulation Caused by the Unknown High-Wave Number Damping Factor Using Surrogate Modelling

Bois, Guillaume

Validation of the Hydrodynamics in a Turbulent Un-Baffled Vortex-Reactor at Two Different Stirring Reynolds Numbers

Vapour Bubble Growth during Nucleate Boiling Accounting for Contact-Line Evaporation

Bolotnov, Igor A.

Demonstration of a Data-Driven Physics-Based Approach for Computationally Efficient CFD Prediction of Two-Phase Bubbly Flow

Detailed Analysis of the Effects of Spacer-Grid and Mixing Vanes on Turbulence in a PWR Sub-Channel under DFFB Conditions Based on DNS Data

Bonne, Alexandre

Key Learnings of Full Scope Simulator’s Nuclear Steam Supply System (NSSS) Model Re-Hosting Project at EDF

Bouyer, V.

Upgrading the PLINIUS Platform toward Smarter Prototypic-Corium Experimental R&D

Brooks, Caleb S.

Beyond Time-Averaged Measurements Using Conductivities Probes

Experimental Study of Fluid Motion and Mass Transfer in a Cylindrical Bubble Column

Bryk, Rafał

Solving Thermal Hydraulic Safety Issues of PWRs through Experiments in the Integral Test Facility PKL

Bures, L.

CFD Study of the Effect of Sliding Bubbles on Heat Transfer in Laminar Regime

C

Cadiou, Thierry

CFD Study of an Innovative Safety System for Pressurized Water Reactors

Cai, Junjie

A CFD Investigation into the Dispersion of Radionuclides within the Street Canyon

Campo, Gabriel Fernando Narváez

High-Fidelity Simulation of Heat-Transfer in Turbulent Pipe Flow

Camy, Romain

RCS Flow Rate from Elbow Taps - Validation of Computational Fluid Dynamics Calculations

Canals, Inés Mateos

Numerical Simulation of a Compressible Air Bubble Rising in Water with Variable Thermophysical Properties

Cao, Yuanwei

Numerical Simulation of a Compressible Air Bubble Rising in Water with Variable Thermophysical Properties

Carasik, Lane B.

Noninvasive Interrogation of Local Flow Phenomena in Twisted Tape Swirled Flow via Positron Emission Particle Tracking (PEPT)

Charollais, F.

Upgrading the PLINIUS Platform toward Smarter Prototypic-Corium Experimental R&D

Chen, Guangliang

Research on the Significance of Small Scale TH Analysis for PWR Fuel Assemblies

Chen, Jiaqi

Experimental Study of Fluid Motion and Mass Transfer in a Cylindrical Bubble Column

Chen, Ronghua

Theoretical Investigation on CHF Characteristics of Natural Circulation under Moving Condition

Cheng, Hui.

Progress of Recent Studies on Sloshing Motion in a Liquid Pool with Solid Particles

Cheng, Songbai.

Progress of Recent Studies on Sloshing Motion in a Liquid Pool with Solid Particles

Cheng, Xu

ATHLET Simulation of PKL IBLOCA I2.2 Benchmark Test and Quantitative Assessment

Cheng-cheng, Deng

Numerical Simulation and Validation of Passive Safety System of Generation III+ PWR with RELAP5

Cheung, Fan-Bill

Acoustic Analysis of the Effects of Vapor-Liquid Interfacial Morphology on Pool-Boiling Heat Transfer

Pressure and Oscillatory Flow Effects on the Two-Phase Flow and Heat Transfer in a Rod Bundle

Chikhi, N.

Upgrading the PLINIUS Platform toward Smarter Prototypic-Corium Experimental R&D

Cho, Yong Jin

Effects of the Bubble Size Distributions on the Decontamination Factors during Bubble Rise in the Pool Scrubbing

Chorda, V.

Feasibility Studies in Support to the Update of Tabletop Facility

Cimarelli, Andrea

Direct Numerical Simulation of Natural, Mixed and Forced Convection in Liquid Metals: Selected Results

Cissé, M.

Mass Transfer Measurement in a Rectangular Channel for Heat Transfer Analogy

Clifford, I.

Making the Switch from Pipe to Vessel Components

Colas, Clément

A Collocated Finite Volume Scheme with an Integral Formulation for Flows with Fluid Section Jumps

Cruz, Rodrigo Vicente

High-Fidelity Simulation of Heat-Transfer in Turbulent Pipe Flow

F

Fang, J.

CFD Evaluation of Pressure Change along Coolant Passages in Sodium-Cooled Fast Reactor Using Nek5000

Fang, Zhu

Experimental and Numerical Investigations on Micro-Sized Particle Wall Collision in Pebble-Bed High Temperature Gas Cooled Reactors

Farges, B.

Advanced Benchmark of the Flow through a Mixing Vane Grid – Large Eddy Simulation Validation

Farina, Elodie

Turbulence Models Assessment for Ascending Mixed Convection Flows

Faucher, V.

Advanced Benchmark of the Flow through a Mixing Vane Grid – Large Eddy Simulation Validation

Feng, Jinyong

Demonstration of a Data-Driven Physics-Based Approach for Computationally Efficient CFD Prediction of Two-Phase Bubbly Flow

Ferrand, Martin

A Collocated Finite Volume Scheme with an Integral Formulation for Flows with Fluid Section Jumps

Blurring the Lines between CAD, Mesh and Solver in Code_Saturne to Improve Predictive Capabilities of Finite Volume CFD Modelling

Ferroukhi, H.

Making the Switch from Pipe to Vessel Components

Fillion, P.

CATHARE-3 V2.1: The New Industrial Version of the CATHARE Code

Some Progress Made in Multiscale Analysis, Multiscale Simulation and Multi-Scale Validation in Reactor Thermalhydraulics

Some Progresses in System Code Modelling Validation and Application Including 3D Modelling

Fiore, Matilde

Multicomponent Diffusion Modelling for Light Gases Predictions in Water Cooled Nuclear Reactors

Foral, Stepan

Validation of the ALTHAMC12 Subchannel Code

Fournier, Yvan

Blurring the Lines between CAD, Mesh and Solver in Code_Saturne to Improve Predictive Capabilities of Finite Volume CFD Modelling

p class="authorPaper">RCS Flow Rate from Elbow Taps - Validation of Computational Fluid Dynamics Calculations

François, Juan-Luis

Heat Transfer Correlations Effects on Fuel Temperature in SCWR with Fractional Neutron Point Kinetics

Fregni, Andrea

Direct Numerical Simulation of Natural, Mixed and Forced Convection in Liquid Metals: Selected Results

H

Hamdani, Ari

CIGMA Experimental Investigation on Heat and Mass Transfer Phenomena Induced by Natural Convection with Density Stratification in the Enclosure Vessel

Han, Bin

Multi-Level CFD Modeling and Applications for Subchannel Thermal-Hydraulics, Experimental Designs, and Safety Analysis

Han, Ye

Non-Nuclear Transient Simulation Experiment of a Heat Pipe Cooled Nuclear Reactor System

Hansel, J.

Sockeye Heat Pipe Code Theory Development: Based on the 7-Equation, Two-Phase Flow Model of RELAP-7

Hassan, Yassin A

Modal Decomposition of the Flow in a Randomly Packed Pebble Bed with Direct Numerical Simulation

Hassi, Tarik

Turbulence Models Assessment for Ascending Mixed Convection Flows

Henry, H.

Numerical Simulation of Droplet Formation by Rayleigh-Taylor Instability in Multiphase Corium

Hérard, Jean-Marc

A Collocated Finite Volume Scheme with an Integral Formulation for Flows with Fluid Section Jumps

Hirose, Yoshiyasu

Application of Immersed Boundary Method for Jet Flow in Grating Type Structure

Hollands, T.

Validation of ATHLET 3.2 on an SBO Scenario Test at the PWR PACTEL Test Facility

Howell, A.

Acoustic Analysis of the Effects of Vapor-Liquid Interfacial Morphology on Pool-Boiling Heat Transfer

Hoxie, Chris

Pressure and Oscillatory Flow Effects on the Two-Phase Flow and Heat Transfer in a Rod Bundle

Hu, Gu

Non-Nuclear Transient Simulation Experiment of a Heat Pipe Cooled Nuclear Reactor System

Hurisse, Olivier

Simulations of Simplified LOCA Scenario with a Non-Equilibrium Homogeneous Model

Hyvärinen, Juhani

PASI – A Test Facility for Research on Passive Heat Removal

L

Laboureur, Delphine

Multicomponent Diffusion Modelling for Light Gases Predictions in Water Cooled Nuclear Reactors

Lainet, M.

Impact of Fuel Pellet-Clad Gap Characteristics on an Unprotected Loss of Flow Transient in a Sodium Fast Reactor

Lamballais, Eric

High-Fidelity Simulation of Heat-Transfer in Turbulent Pipe Flow

Lampunio, Lisa

Thermal Stripping Analysis in T-Junctions with Different Entry Flow Profiles

Le Coupanec, Erwan

A Collocated Finite Volume Scheme with an Integral Formulation for Flows with Fluid Section Jumps

RCS Flow Rate from Elbow Taps - Validation of Computational Fluid Dynamics Calculations

Turbulence Models Assessment for Ascending Mixed Convection Flows

Le Tellier, R.

Numerical Simulation of Droplet Formation by Rayleigh-Taylor Instability in Multiphase Corium

Use of CFD Results to Model Heat Transfer in a Thin Metal Layer

Lee, Yoonhee

Effects of the Bubble Size Distributions on the Decontamination Factors during Bubble Rise in the Pool Scrubbing

Leterrier, N.

Validation of the Hydrodynamics in a Turbulent Un-Baffled Vortex-Reactor at Two Different Stirring Reynolds Numbers

Li, C.

Assessment of Wall Boiling Model to Predict Critical Heat Flux Using CFD

Li, Lei

Research on the Significance of Small Scale TH Analysis for PWR Fuel Assemblies

Li, Lin-kun

The Sensitive Analysis of Thermal Hydraulics Phenomena of a Suppression Pool with the System Analysis Code

Li, S.

Impact of Fuel Pellet-Clad Gap Characteristics on an Unprotected Loss of Flow Transient in a Sodium Fast Reactor

Li, Xiaowei

Time Domain Theoretical Study on Two-Phase Flow Instability

Li, Yi

Study on Automatic Depressurization System of SMR

Liang, Qian

Time Domain Theoretical Study on Two-Phase Flow Instability

Liu, Aiguo

Multi-Level CFD Modeling and Applications for Subchannel Thermal-Hydraulics, Experimental Designs, and Safety Analysis

Liu, Huaqiang

Investigation of the Effects of Surface Wettability and Surface Roughness on Nanoscale Boiling Process Using Molecular Dynamics Simulation

Liu, W.

A Modified Liquid Sublayer Dryout Model for Subcooled Flow Boiling Critical Heat Flux Prediction in IVR Condition

Liu, Xiao

Startup Transient Thermal-Hydraulic Analysis of a Lithium Heat Pipe Cooled Reactor Core

Liu, Xiong-bin

Numerical Simulation of a Toroidal Single-Phase Natural Circulation Loop with κ-κL-ω Transitional Turbulence Model

Liu, Ziping

Preliminary Discussion on the Equivalent Thermal Conductivity Affected by the Inner Heat Source

Lommers, L.

Sensitivity of SC-HTGR Conduction Cooldown to Reactor Cavity Cooling System Operation

Lopes, S.

Hunting for the Correct Pressure Drop in a Scaled Reactor Pool: Effect of Geometry, Mesh Resolution, Turbulence Model and Mass Flow

Louie, David L.Y.

MELCOR Study of Alkaline Carbonate Cooling to Mitigate Ex-Vessel Molten Corium Accidents

Lowery, Brian

Pressure and Oscillatory Flow Effects on the Two-Phase Flow and Heat Transfer in a Rod Bundle

M

Ma, Rui

Research on the Significance of Small Scale TH Analysis for PWR Fuel Assemblies

Macián-Juan, Rafael

Numerical Simulation of a Compressible Air Bubble Rising in Water with Variable Thermophysical Properties

Marin, Oana

Towards Direct Numerical Simulation of a 5X5 Rod Bundle

Marino, A.

Feasibility Studies in Support to the Update of Tabletop Facility

Martín-del-Campo, Cecilia

Heat Transfer Correlations Effects on Fuel Temperature in SCWR with Fractional Neutron Point Kinetics

Martineau, R.C.

Sockeye Heat Pipe Code Theory Development: Based on the 7-Equation, Two-Phase Flow Model of RELAP-7

Matkovič, Marko

Turbulent Flow over a Confined Backward Facing Step: Measurements and Simulations

Matsumoto, T.

A Modified Liquid Sublayer Dryout Model for Subcooled Flow Boiling Critical Heat Flux Prediction in IVR Condition

Mattassoglio, C.

Upgrading the PLINIUS Platform toward Smarter Prototypic-Corium Experimental R&D

Matteo, L.

CATHARE-3 V2.1: The New Industrial Version of the CATHARE Code

Mauger, G.

CATHARE-3 V2.1: The New Industrial Version of the CATHARE Code

Mays, B.

Sensitivity of SC-HTGR Conduction Cooldown to Reactor Cavity Cooling System Operation

Mekkas, A.

CATHARE-3 V2.1: The New Industrial Version of the CATHARE Code

Mercz, Julius

Mechanical Evaluations To Define Possible Fuel Element Designs For The Conversion Of Frm Ii

Merigoux, N.

Some Progress Made in Multiscale Analysis, Multiscale Simulation and Multi-Scale Validation in Reactor Thermalhydraulics

Merzari, Elia

CFD Evaluation of Pressure Change along Coolant Passages in Sodium-Cooled Fast Reactor Using Nek5000

Modal Decomposition of the Flow in a Randomly Packed Pebble Bed with Direct Numerical Simulation

Towards Direct Numerical Simulation of a 5X5 Rod Bundle

Miao, Xinyi

Multi-Level CFD Modeling and Applications for Subchannel Thermal-Hydraulics, Experimental Designs, and Safety Analysis

Mikityuk, K.

CFD Study of the Effect of Sliding Bubbles on Heat Transfer in Laminar Regime

Miller, Douglas

Pressure and Oscillatory Flow Effects on the Two-Phase Flow and Heat Transfer in a Rod Bundle

Mimouni, S.

Some Progress Made in Multiscale Analysis, Multiscale Simulation and Multi-Scale Validation in Reactor Thermalhydraulics

Min, Jiesheng

Numerical Investigation on Complete Reactor Vessel Flow with Code_Saturne

Mitenkova, E. F.

Accurate Calculations “Neutronic-Thermal Hydraulic” by MCU/OpenFOAM Codes for Light Water and Liquid Metal Cooled Systems

Moghaddam, Nader Maleki

Heat Transfer Correlations Effects on Fuel Temperature in SCWR with Fractional Neutron Point Kinetics

Molina, D.

Upgrading the PLINIUS Platform toward Smarter Prototypic-Corium Experimental R&D

Morita, K.

A Modified Liquid Sublayer Dryout Model for Subcooled Flow Boiling Critical Heat Flux Prediction in IVR Condition

Mou, Jian

Non-Nuclear Transient Simulation Experiment of a Heat Pipe Cooled Nuclear Reactor System

Moulinec, Charles

Simulations of Heat Transfer Impairment in AGR Fuel Assemblies

S

Saikali, E.

Validation of the Hydrodynamics in a Turbulent Un-Baffled Vortex-Reactor at Two Different Stirring Reynolds Numbers

Saini, Nadish

Detailed Analysis of the Effects of Spacer-Grid and Mixing Vanes on Turbulence in a PWR Sub-Channel under DFFB Conditions Based on DNS Data

Sauvecane, P.

Upgrading the PLINIUS Platform toward Smarter Prototypic-Corium Experimental R&D

Schmidt, Holger

Solving Thermal Hydraulic Safety Issues of PWRs through Experiments in the Integral Test Facility PKL

Schöffel, P.

Validation of ATHLET 3.2 on an SBO Scenario Test at the PWR PACTEL Test Facility

Schollenberger, Simon Philipp

Solving Thermal Hydraulic Safety Issues of PWRs through Experiments in the Integral Test Facility PKL

Shahrokhi, F.

Sensitivity of SC-HTGR Conduction Cooldown to Reactor Cavity Cooling System Operation

Shaver, D.R.

CFD Evaluation of Pressure Change along Coolant Passages in Sodium-Cooled Fast Reactor Using Nek5000

Shehu, Kaltrina

Mechanical Evaluations To Define Possible Fuel Element Designs For The Conversion Of Frm Ii

Shin, Andong

Multi-Dimensional Calculation of Reflood Behavior in a SCTF Experiment at Partial Blockage Condition

Sibamoto, Yasuteru

Application of Immersed Boundary Method for Jet Flow in Grating Type Structure

CIGMA Experimental Investigation on Heat and Mass Transfer Phenomena Induced by Natural Convection with Density Stratification in the Enclosure Vessel

Silverman, Ido

Topology Based Multi-Phase Flow Model for Nuclear Safety Applications

Stalio, Enrico

Direct Numerical Simulation of Natural, Mixed and Forced Convection in Liquid Metals: Selected Results

Stempniewicz, M.M.

Molten Salt Modelling Capabilities in Spectra and Application to MSRE

Stewart, Jeff

GeN-FOAM Model of Graphite Moderator of a Molten Salt Reactor

Stratta, Elisabetta

CFD Study of an Innovative Safety System for Pressurized Water Reactors

Su, G.H.

Preliminary Neutronic/Thermal-Hydraulic and Safety Assessment of Pressurized Water Reactor Loaded with Fully Ceramic Microencapsulated Fuel

Steady State and Transient Analysis of Gas-Cooled Reactor Space Nuclear Power System

Theoretical Investigation on CHF Characteristics of Natural Circulation under Moving Condition

Su, Guanghui

Numerical Investigation on Complete Reactor Vessel Flow with Code_Saturne

Startup Transient Thermal-Hydraulic Analysis of a Lithium Heat Pipe Cooled Reactor Core

Su, Yang

Time Domain Theoretical Study on Two-Phase Flow Instability

Suk, Ladislav

Validation of the ALTHAMC12 Subchannel Code

Sun, Jun

Preliminary Discussion on the Equivalent Thermal Conductivity Affected by the Inner Heat Source

Sun, Xiaobo

Non-Nuclear Transient Simulation Experiment of a Heat Pipe Cooled Nuclear Reactor System

Sun, Yan

Study on Automatic Depressurization System of SMR

Sun, Zhongning

Enhanced Tolerance Limit Evaluation Method to Determine Statistically Meaningful Minimum Sampling Size

Suteau, C.

Upgrading the PLINIUS Platform toward Smarter Prototypic-Corium Experimental R&D

W

Waddington, G.

Assessment of Wall Boiling Model to Predict Critical Heat Flux Using CFD

Wald, Jean-Francois

Turbulence Models Assessment for Ascending Mixed Convection Flows

Wang, Chenglong

Preliminary Neutronic/Thermal-Hydraulic and Safety Assessment of Pressurized Water Reactor Loaded with Fully Ceramic Microencapsulated Fuel

Startup Transient Thermal-Hydraulic Analysis of a Lithium Heat Pipe Cooled Reactor Core

Steady State and Transient Analysis of Gas-Cooled Reactor Space Nuclear Power System

Wang, Jianjun

Enhanced Tolerance Limit Evaluation Method to Determine Statistically Meaningful Minimum Sampling Size

Wang, Jijun

Research on the Significance of Small Scale TH Analysis for PWR Fuel Assemblies

Wang, Lianfa

Numerical Investigation on Complete Reactor Vessel Flow with Code_Saturne

Wang, Mingjun

Numerical Investigation on Complete Reactor Vessel Flow with Code_Saturne

Wang, Yifeng

MELCOR Study of Alkaline Carbonate Cooling to Mitigate Ex-Vessel Molten Corium Accidents

Wei, Mingzhe

Experimental and Numerical Investigations on Micro-Sized Particle Wall Collision in Pebble-Bed High Temperature Gas Cooled Reactors

Wiggins, Cody S.

Noninvasive Interrogation of Local Flow Phenomena in Twisted Tape Swirled Flow via Positron Emission Particle Tracking (PEPT)

Wong, K.W.

CFD Study of the Effect of Sliding Bubbles on Heat Transfer in Laminar Regime

Wu, Di

Preliminary Neutronic/Thermal-Hydraulic and Safety Assessment of Pressurized Water Reactor Loaded with Fully Ceramic Microencapsulated Fuel

Theoretical Investigation on CHF Characteristics of Natural Circulation under Moving Condition

Wu, Xinxin

Experimental and Numerical Investigations on Micro-Sized Particle Wall Collision in Pebble-Bed High Temperature Gas Cooled Reactors

Time Domain Theoretical Study on Two-Phase Flow Instability

Wu, Yingwei

Preliminary Neutronic/Thermal-Hydraulic and Safety Assessment of Pressurized Water Reactor Loaded with Fully Ceramic Microencapsulated Fuel

Z

Zajec, Boštjan

Turbulent Flow over a Confined Backward Facing Step: Measurements and Simulations

Zanella, R.

Numerical Simulation of Droplet Formation by Rayleigh-Taylor Instability in Multiphase Corium

Zang, Jin-guang

The Sensitive Analysis of Thermal Hydraulics Phenomena of a Suppression Pool with the System Analysis Code

Zerkak, O.

Making the Switch from Pipe to Vessel Components

Zhang, Dalin

Preliminary Neutronic/Thermal-Hydraulic and Safety Assessment of Pressurized Water Reactor Loaded with Fully Ceramic Microencapsulated Fuel

Zhang, Hongbin

Demonstration of a Data-Driven Physics-Based Approach for Computationally Efficient CFD Prediction of Two-Phase Bubbly Flow

Zhang, Kui

Theoretical Investigation on CHF Characteristics of Natural Circulation under Moving Condition

Zhang, Ran

Steady State and Transient Analysis of Gas-Cooled Reactor Space Nuclear Power System

Zhang, Yan

The Sensitive Analysis of Thermal Hydraulics Phenomena of a Suppression Pool with the System Analysis Code

Zhang, Yiyang

Experimental and Numerical Investigations on Micro-Sized Particle Wall Collision in Pebble-Bed High Temperature Gas Cooled Reactors

Zhang, Zhijian

Research on the Significance of Small Scale TH Analysis for PWR Fuel Assemblies

Zhao, Jiyun

A CFD Investigation into the Dispersion of Radionuclides within the Street Canyon

Investigation of the Effects of Surface Wettability and Surface Roughness on Nanoscale Boiling Process Using Molecular Dynamics Simulation

Zhao, Shumiao

Experimental and Numerical Investigations on Micro-Sized Particle Wall Collision in Pebble-Bed High Temperature Gas Cooled Reactors