Author Index

Spatially-Resolved Measurement of Gas Phase Temperature and Velocity in the Subchannels of a Fuel Element during Dry-Out

Arlit, Martin

Aronson, Arnold

TRACE/PARCS Analysis of ATWS with Instability for a MELLLA+ BWR/5

Artoun, Narbeh

Study of Abnormal Heat Transfer during Forced and Natural Convection Scenarios in a Prismatic Core of a VHTR: Numerical and Experimental Results

Atkhen, Kresna

Effects of Porous Superhydrophilic Surfaces on Flow Boiling Critical Heat Flux in IVR Accident Scenarios

Atkins, Michael D.

Validation Test Plan of a CANDU-6 Moderator Tank Scaled-Down Test Facility

Aubert, P.

Plateau Facility in Support to ASTRID and the SFR Program: An Overview of the First Mock-Up of the ASTRID Upper Plenum MICAS

Auliano, Manuel

Evaluation of 1-D Void and Pressure Drop Models over a Wide Range of Fuel Bundle Geometries and Operating Conditions

Aumiller, D. L.

Fundamental Experiments of Condensation Heat Transfer on Water Jets in the Presence of Noncondensable Gas

Aumiller, D.

On the Definition of a Minimum Set of Requirements to Assess the Adequacy of the RELAP5-3D Multidimensional Flow Capability with Selected Canonical Problems

Simulation of Faraday Waves with RELAP5-3D Thermal-Hydraulic Code

On the Level of Approximation of the Multi-Dimensional Potential Flow Solution in Complex Geometries with Thermal-Hydraulic System Codes

Aumiller, David L.

Development of a Sub-Grid Liquid Jet Condensation Model

A Discussion of Uncertainty Quantification for CHF as Performed in COBRA-IE

An Assessment of Void Fraction Data with COBRA-IE

Large Open Region Interfacial Drag Modeling Package in COBRA-IE

Effects of Steam-Water vs. Air-Water Fluid Pairs and Pressure on Flooding in Large Diameter Tubes

Aumiller, David

Avigni, P.

Pseudo-3D Steady State Thermal-Hydraulic Modeling of the Advanced High Temperature Reactor Fuel Assembly

Avramova, M. N.

Anisotropic Azimuthal Power and Temperature Distribution as a Driving Force for Hydrogen Redistribution

Avramova, M.

Testing Coupled MCNP6/CTF on an Assembly Level Problem with an Acceleration Technique

CTF Application to BWR Modeling and Simulations

CTF Void Drift Validation

Development of Burnup Dependent Fuel Rod Model in CTF

Avramova, Maria N.

Uncertainty and Sensitivity Analysis of COBRA-TF for the OECD LWR UAM Benchmark using DAKOTA

Analysis of Improved Fuel Rod Modeling in Coupled Thermal-Hydraulics/Neutronics Calculations

Avramova, Maria

CTF Residual Formulation Solid Liquid Coupling

Aydogan, Fatih

Six-Field Governing Equation Development for Advanced System Codes

Azizian, R.

Simulation of Orientation Effects on Critical Heat Flux in Downward-Facing Channel for IVR

Azizian, Reza

Effects of Porous Superhydrophilic Surfaces on Flow Boiling Critical Heat Flux in IVR Accident Scenarios

Azuma, Mie

A Dynamic Model of Hydrostatic Reactor Coolant Pump Seals for RELAP5/MOD3.3

B

Bachrata, A.

Comparison of an Advanced Analytical Tool with the SIMMER Code to Support Astrid Severe Accident Mitigation Studies

Badalassi, V.

Interface Tracking Based Evaluation of Bubble Growth Rates in High Pressure Pool Boiling Conditions

Badalassi, Vittorio

Numerical Study of Heat Diffusion Controlled Bubble Growth in a Pressurised Liquid

Badillo, A.

Synthesis of the OECD/NEA-PSI CFD Benchmark Exercise

Bae, B. U.

Experimental Investigation on Thermal-Hydraulics Behavior during a Station Blackout Transient in a Pressurized Water Reactor

Bae, B.U.

An SBLOCA Test of Pressurizer Safety Valve Line Break with the SMART-ITL Facility and its MARS-KS Code Simulation

Bae, Hwang

Bae, S. W.

Numerical Simulation of Supercritical Pressure Fluids with Variable Turbulent Prandtl Number and Modified Damping Function (1/2)

Bae, Y. Y.

Baek, Je Hyun

Suppression of Chemical Reactivity of Sodium-Titanium Nano Fluid in Sodium-Water Vapor Reaction

Baek, Joo Seok

Analysis of LOCA Scenarios in the NIST Research Reactor Before and After Fuel Conversion

TRACE/PARCS Analysis of ATWS with Instability for a MELLLA+ BWR/5

Baghai, Ramine

Detailed Measurements of Local Parameters in Annular Two-Phase Flow in Fuel Bundle under BWR Operating Conditions

Baglietto, E.

A Methodology for Characterizing Representativeness in Power Plant Performance Indicator Measurements with CFD Simulations

Modeling of the Groundwater Transport Around a Deep Borehole Nuclear Waste Repository

A Reevaluation of the Lift Force in Eulerian Multiphase CFD

Baglietto, Emilio

Modeling of Rayleigh-Taylor Instability for Steam Direct Contact Condensation

Application of CD-ADAPCO Best Practices to NESTOR OMEGA MVG Benchmark Exercises Using STAR-CCM+

Implementation and Validation of a Surface Tension Model for the Multi-Scale Approach GENTOP

Structure-Based Resolution of Turbulence for Sodium Fast Reactor Thermal Striping Applications

Non-Linear Eddy Viscosity Turbulence Modeling in Hydra-TH for Fuel Related Applications

A Structure-Based Approach for Topological Resolution of Coherent Turbulence: Overview and Demonstration

CFD Simulations to Determine the Effects of Deformations on Liquid Metal Cooled Wire Wrapped Fuel Assemblies

Bai, Bofeng

Interfacial Stability in Vertical Swirling Annular Two-Phase Flow

Bai, Wei

Requirements Analysis and Research of Severe Accident Process Simulation Based on COS-SA Code and Emergency Decision Support

Bai, Yunqing

Unprotected Transient Analyses of Natural Circulation LBE-Cooled Accelerator Driven Sub-Critical System

Thermal-Hydraulic Design and CFD Analysis of Fuel Assembly for China Lead-Based Research Reactor

Baik, Seungjoon

Printed Circuit Heat Exchanger Design, Analysis and Experiment

Experimental Study on the CO₂ to Water Heat Exchanger Performance Near the CO₂ Critical Point

Bajorek, S. M.

Development, Validation and Assessment of the TRACE Thermal-Hydraulics Systems Code

Bajorek, Stephen M.

Experimental Study of Laminar Mixed Convection in a Rod Bundle with Mixing Vane Spacer Grids

A Regulator’s Perspective on the State-of-the-Art in Nuclear Thermal-Hydraulics

Bajs, Tomislav

Benchmark Analysis of EBR-II Protected Loss-of-Flow Transient

Bakouta, N.

Bals, C.

Simulation of LIVE-L4 with ATHLET-CD

Banati, Jozsef

Validation of RELAP5/MOD3.3 Against a Load Step Transient at RINGHALS 4 NPP

Band, S.

Re-Evaluation of PAR Concept in German PWR with Revised PAR Model

ATHLET-CD/COCOSYS Analyses of Severe Accidents in Fukushima (Units 2 and 3) within the OECD/NEA BSAF Project, Phase 1

Bandini, G.

Transient Analyses for the MYRRHA-FASTEF Reactor by SIMMER Code

Bandini, Giacomino

Single and Two-Phase Sodium Flow Analysis for two TUCOP CABRI Tests Using the ASTEC-Na Code

Banfield, Kevin

Heat Up and Potential Failure of BWR Upper Internals during a Severe Accident

Bang, In Cheol

Feasibility Study of Hybrid Heat Pipe with Control Rod as Passive In-Core Cooling System for Advanced Nuclear Power Plant

Experimental Investigation of Heat Transfer Phenomenon of Annular Heat Pipe for Passive In-Core Cooling System

Heat Removal Characteristics of IVR-ERVC Cooling System Using Gallium Liquid Metal

Thermal-Hydraulic Analysis of a 7-Pin Sodium Fast Reactor Fuel Bundle with a New Pattern of Helical Wire-Wrap Spacer

Heat Removal Capacity of Heat Pipe Designs for In-Core Passive Decay Heat Removal System

A Visual Study of Molten Metal Fuel Coolant Interactions Under an Initial Phase of SFR Severe Accident using Gallium Metal vs Water or R123

Critical Heat Flux Enhancement Mechanism by Surface Modification based on Hydrodynamic Instability Mode

Bang, Young Seok

Comparison of MARS-KS to COBRA-TF for Models and Correlations in Pre-CHF Regime

Bao, J.

CATHARE-TransAT Coupling for the Prediction of Boron Dilution in the Rocom Test Facility

Bardet, Philippe M.

Surrogate Spacer Grid Design for Fluid-Structure Interactions Studies in Fuel Bundles

Initial Condition Effects on Kelvin-Helmholtz Instabilities and Development of a Round Jet

Barone, Gianluca

Fuel Pin Bundle Experimental Characterization in HLM Large Pool System

Barrachin, M.

Fukusima Core Melt Composition Simulation with ASTEC

Barrachin, Marc

Past and Future R&D at IRSN on Corium Progression and Related Mitigation Strategies in a Severe Accident

Barrachina, T.

Assessment of TRACE/PARCS Benchmark Against Leibstadt Plant Data During the Turbine Trip Test

Bartosiewicz, Yann

Uncertainty Analysis of Delayed Equilibrium Model (DEM) using the CIRCE Methodology

Implementation and Assessment of the Delayed Equilibrium Model for Computing Flashing Choked Flows into a Multi-Field CFD Code

Baruch, I.

The Effect of Thermal Conditions and Jet Properties on Steam Explosion

Basso, S.

Development of TEXAS-V Code Surrogate Model for Assessment of Steam Explosion Impact in Nordic BWR

Effect of Particle Spreading on Coolability of Ex-Vessel Debris Bed

Experiments and Modeling of Particulate Debris Spreading in a Pool

Basu, Sud

Key Findings and Remaining Questions in the Areas of Core-Concrete Interaction and Debris Coolability

Bates, E. A.

Modeling of the Groundwater Transport Around a Deep Borehole Nuclear Waste Repository

Batra, Chirayu

Benchmark Analysis of EBR-II Protected Loss-of-Flow Transient

Batta, A.

Analysis of Pressure Drop in Rod Bundles in Heavy Liquid Metal

Baudin, Nicolas

Transient Convective Boiling: Analysis of Experimental Results

Baudry, C.

Verification, Validation and Application of Neptune _ CFD to Two-Phase Pressurized Thermal Shocks

Assessment of RANS at Low PRANDTL Number and Simulation of Sodium Boiling Flows with a CMFD Code

Baudry, Cyril

Progress on Computation of Boiling Flow in Fuel Assemblies with NEPTUNE_CFD

A Generalized Turbulent Dispersion Model for Bubbly Flow Numerical Simulation in NEPTUNE_CFD

Bazin, P.

Validation of CATHARE Code on the 3D ROSA-LSTF Pressure Vessel

Bechta, S.

Severe Accident Progression in the BWR Lower Plenum and the Modes of Vessel Failure

Bechta, Sevostian V.

Core Melt Stabilization Concepts for Existing and Future LWRs and Associated R&D Needs

Bechta, Sevostian

Severe Accident Facilities for European Safety Targets,

Beck, F. R.

Enhancement of Downward Facing Boiling Heat Transfer by the Cold Spray Technique

Beeny, B.

MELCOR and GOTHIC Analyses of a Large Dry Pressurized Water Reactor Containment to Support Resolution of GSI-191

A Sensitivity Study Supporting Comparative Analysis of MELCOR and GOTHIC Large Dry Pressurized Water Reactor Containment Models

Belguet, A. L.

Bellet, S.

Verification, Validation and Application of Neptune _ CFD to Two-Phase Pressurized Thermal Shocks

Belloni, Francesco

Influence of the 3-D Phenomena on the Safety Parameters during a ULOF Accident in the MYRRHA Reactor

Benhamadouche, Sofiane

Wall Resolved Large Eddy Simulation of a Flow Through a Square-Edged Orifice in a Round Pipe at RE=25000

Benhamadouche, S.

On the Use of (U)RANS and LES Approaches for Turbulent Incompressible Single Phase Flows in Nuclear Engineering Applications

Benhamadouche, Sofiane

Pressure Drop Predictions Using Code_Saturne in NESTOR CFD Benchmark

Bennett, A.

Testing Coupled MCNP6/CTF on an Assembly Level Problem with an Acceleration Technique

Bentaïb, A.

Hydrogen Safety: Laminar and Turbulent Flame Speed of Spherical Flame in a Fan-Stirred Closed Vessel

Bentaib, Ahmed

Hydrogen Management Strategies and Analysis Codes Implemented by the OECD Member Countries

A First Orienting Investigation of the Interaction of Cable Fire Products with Passive Auto-Catalytic Recombiners (PARs)

Benteboula, Sonia

Nodalization Schemes for Lumped-Parameter Calculations of Representative Nuclear Reactor Severe Accident Tests in the MISTRA Facilty

Bentivoglio, F.

Description of an Improved Turbomachinery Model to be Developed in the CATHARE3 Code for Astrid Power Conversion System Application

Benz, Matthias

A Novel Approach for Turbulence Modeling of Wavy Stratified Two-Phase Flow

Bergagio, M.

Instrumentation for Temperature and Heat Flux Measurement on a Solid Surface under BWR Operating Conditions

Bergagio, Mattia

Measurement of Wall Temperature Fluctuations During Thermal Mixing of Non-Isothermal Water Streams

Bergmann, Uffe

Detailed Measurements of Local Parameters in Annular Two-Phase Flow in Fuel Bundle under BWR Operating Conditions

Bernard, M.

Development, Validation and Assessment of the TRACE Thermal-Hydraulics Systems Code

Bertrand, F.

Comparison of an Advanced Analytical Tool with the SIMMER Code to Support Astrid Severe Accident Mitigation Studies

Transient Analysis of the ASTRID Demonstrator Including a Gas Nitrogen Power Conversion System with the CATHARE2 Code

Bertrand, Frederic

Analytical Modelling of the Primary Phase of an Unprotected Loss of Flow

Bestion, D.

Scaling Considerations About LWR Core Thermal Hydraulics

System Thermal Hydraulics for DBA Analysis and Simulation Status of Tools and Methods and Direction for Future R&D

Bestion, Dominique

The CATHARE Code Condensation Modelling Confronted to the TOPFLOW-PTS Steady-State Experiments

Betschart, T.

Interfacial Area Density Measurement using a Three-Layer Wire-Mesh Sensor

Beuzet, E.

Simulation of FARO L-28 and L-31 Tests to Assess Molten Jet Fragmentation Modeling in MAAP

Beyer, M.

Direct Condensation and Entrainment Steam Experiments at the TOPFLOW-DENISE Facility

Uncertainty Analysis of an Interfacial Area Reconstruction Algorithm

Evaluating Performance of Two Group Interfacial Area Transport Equation for Large Diameter Pipes

Beyer, Matthias

Experimental and Numerical Investigation of Flow Structure and Heat Transfer During High Pressure Condensation in a Declined Pipe at COSMEA Facility

Bezlepkin, Vladimir V.

Core Melt Stabilization Concepts for Existing and Future LWRs and Associated R&D Needs

Bhatt, Santosh

Application and Validation of AREVA’s Advanced Thermal-Hydraulic Methods and Codes for PWR Level III Crud Risk Assessment

Bhattacharjee, Saptarshi

Modeling of Fluctuating Fluid Forces Exerted on the Walls of a Concentric Annular Pipe Using Large Eddy Simulation

Bhimanadam, V. R.

Fluid-Structure Interaction in a Wire-Wrapped Rod Bundle Cooled with Supercritical Water

Bi, K.

Critical Heat Flux with Subcooled Flowing Water in Tubes for Pressures from Atmosphere to Near-Critical Point

A Natural Circulation Experiment of Passive Residual Heat Removal Heat Exchanger for AP1000

Bian, J.W.

Experiment of Condensation in T-Junction: Steam-Water Flow in Water-Injected Condition

Bicer, Erol

Scaling Analysis for DVI Line Break Accident of APR1400 based on ATLAS Experiment

Bickel, J. E.

Design, Fabrication and Startup Testing in the Compact Integral Effects Test Facility in Support of Fluoride-Salt-Cooled, High-Temperature Reactor Technology

Bieberle, André

Investigations on Centrifugal Pumps under Air Entrainment Conditions

Bieder, U.

Nuclear Reactor Containment Flows—Modelling of Stably Stratified Layer Erosion by a Turbulent Jet

CFD Analysis of Non-Axial Flow in Fuel Assemblies

Bieder, Ulrich

Overview of the TRIOCFD Code: Main Features, V&V Procedures and Typical Applications to Nuclear Engineering

Bier, Vicki

Development of a Societal-Risk Goal for Nuclear Power Safety

Bijleveld, Henny

Turbulent Gas Mixing in Strong Density Stratified Shear and Non-Shear Flows

Bindra, Hitesh

Thermal Effects of Material Discontinuities and Oxidation on Graphite Matrix in HTGRs

Bisogni, Dario

Influence of the 3-D Phenomena on the Safety Parameters during a ULOF Accident in the MYRRHA Reactor

Bissett, Teresa A.

Computational Fluid Dynamics Benchmark using AP1000^®1/4-Scale Upper Head Test Data

Blandford, E.

Thermal Hydraulic Benchmarking Exercises to Support Fluoride-Salt-Cooled, High-Temperature Reactor (FHR) Licensing

Blandford, Edward D.

Overview of the Flume Integral Effects and Separate Effects Testing and Analysis (FIESTA) Facility for Investigating Containment Debris Transport and Sump Strainer Head Loss

Conventional and Chemical Head Loss Modeling of Multi-Constituent Debris Beds in Resolution of GSI-191

Bloemeling, F.

The Development of Surface Vortices in Strongly Rotating Flow in a Cylindrical Vessel: Numerical Simulation

Blowe, Ted

CFD Methodologies for a PWR Fuel Rod Assembly

Blue, T. E.

Experimental Study of DRACS Thermal Performance in a Low-Temperature Test Facility

Blyth, T.

Analyses of LOCAs in the Primary Heat Transfer System of the Helium Cooled Pebble Bed Blanket Concept

Boccaccini, Lorenzo V.

Bodkha, Kapil

A Supercritical Pressure Parallel Channel Natural Circulation Loop

Boissavit, M.

Bolotnov, I. A.

Spectral Analysis of the Turbulent Energy Spectrum in Single and Two-Phase Bubbly Flows in Different Geometries Based on Direct Numerical Simulation Results

Bolotnov, Igor A.

Interface Tracking Simulations of Bubbly Flows in the PWR Relevant Geometries

Bonnet, Jean Michel

Past and Future R&D at IRSN on Corium Progression and Related Mitigation Strategies in a Severe Accident

Bonneville, Herve

Fukusima Core Melt Composition Simulation with ASTEC

Bottomley, David

Severe Accident Facilities for European Safety Targets,

Bourdon, Serge

Hot Fuel Element Thermal-Hydraulic Modeling in the Jules Horowitz Reactor Nominal and LOFA Conditions

Bouyer, Viviane

Plinius Prototypic Corium Experimental Platform: Major Results and Future Works

Bradbury, Michael

Comparison of COBRA-TF and VIPRE-01 Against Low Flow Code Assessment Problems

Bratfisch, Christian

Preliminary Results of a Comparative Assessment of ATHLET-CD and MELCOR by Simulating the Experiment PHEBUS FPT1

Bratfisch, Christoph

First Results of the Simulation of the Fukushima-Daiichi Unit 3 Accident for an Assessment of the Applicability and Capability of the Code ATHLET-CD

Breitung, Wolfgang

Three Dimensional Scalable All-Speed CFD Code Gasflow-MPI: Applications to Turbulent Combustion of Premixed Hydrogen-Air Mixtures with Heat and Mass Transfer

Bremer, Nathan

Distributed Temperature Sensor Testing in Liquid Sodium

Key Findings and Remaining Questions in the Areas of Core-Concrete Interaction and Debris Coolability

Brewster, Robert

Application of CD-ADAPCO Best Practices to NESTOR OMEGA MVG Benchmark Exercises Using STAR-CCM+

Brigantic, Adam

Applying Uncertainty and Sensitivity on Thermal Hydraulic Subchannel Analysis for the Multi-Application Small Light Water Reactor

Briggs, L.

EBR-II Passive Safety Demonstration Tests Benchmark Analyses—Phase 2

Brillant, G.

Capability of ASTEC V2.1 to Simulate a Severe Accident in a Nuclear Power Plant —Application to a TMI-2-Like Accident Scenario

Brockmeyer, L. M.

CFD Investigation of Wire-Wrapped Fuel Rod Bundles and Flow Sensitivity to Bundle Size

Brooks, C. S.

Turbulence-Induced Bubble Collision Force Model Development and Assessment for Adiabatic Dispersed Air-Water Two-Phase Flow with the Two-Fluid Model

Brooks, Caleb S.

Assessment of RELAP5/MOD3.3 for Subcooled Boiling, Flashing and Condensation in a Vertical Annulus

Brooks, Caleb

Uncertainty Quantification of TRACE Wall Heat Transfer Modeling in Subcooled Boiling Using BFBT Experiments

Brown, C. S.

Spectral Analysis of the Turbulent Energy Spectrum in Single and Two-Phase Bubbly Flows in Different Geometries Based on Direct Numerical Simulation Results

Brunett, A. J.

Recent Developments for the SAS4A/SASSYS-1 Safety Analysis Code

Bruyere, Benoit

Core Coolability in Loss of Coolant Accident: The COAL Experiments

Bucci, M.

Experimental Study of Heat Transfer Mechanisms Under Exponential Power Excursion in Plate-Type Fuel

Buchanan, J. R., Jr.

Assessment of an Interfacial Shear Term for Adiabatic Dispersed Air-Water Two-Phase Flow with the Two-Fluid Model

Derivation of a Generic Multi-Field Two-Fluid Model

Buchanan, J. R.

Turbulence-Induced Bubble Collision Force Model Development and Assessment for Adiabatic Dispersed Air-Water Two-Phase Flow with the Two-Fluid Model

Buchanan, John R.

Experimental Characterization of Interchannel Mixing Through a Narrow Gap

Buchholz, S.

Validation of ANSYS CFX for Gas and Liquid Metal Flows with Conjugate Heat Transfer Within the European Project THINS

Study of Safety and International Development of Small Modular Reactors (SMR)

Buchlin, Jean-Marie

Experimental Results from a Water Scale Model for the Thermal-Hydraulic Analysis of a HLM Reactor

CFD and Experimental Investigation of Sloshing Parameters for the Safety Assessment of HLM Reactors

Buckingham, S.

Tracking of Fuel Particles After Pin Failure in Nominal, Loss-of-Flow and Shutdown Conditions in the MYRRHA Reactor

Buckingham, Sophia

MyrrhaFoam: A CFD Model for the Study of the Thermal Hydraulic Behavior of MYRRHA

Buffe, Laurence

Needs for Large Mass Phototype Corium Experiments: The PLINIUS-2 Platform

Buongiorno, J.

Balance of Plant and Power Transmission for the Offshore Floating Nuclear Plant

Ocean-Based Passive Decay Heat Removal in the Offshore Floating Nuclear Plant (OFNP)

Experimental Study of Heat Transfer Mechanisms Under Exponential Power Excursion in Plate-Type Fuel

Buongiorno, Jacopo

Effects of Porous Superhydrophilic Surfaces on Flow Boiling Critical Heat Flux in IVR Accident Scenarios

Synthesis of CRUD and its Effects on Pool and Subcooled Flow Boiling

Buschman, F. X.

Fundamental Experiments of Condensation Heat Transfer on Water Jets in the Presence of Noncondensable Gas

On the Definition of a Minimum Set of Requirements to Assess the Adequacy of the RELAP5-3D Multidimensional Flow Capability with Selected Canonical Problems

Buschman, F.

Simulation of Faraday Waves with RELAP5-3D Thermal-Hydraulic Code

On the Level of Approximation of the Multi-Dimensional Potential Flow Solution in Complex Geometries with Thermal-Hydraulic System Codes

Buschman, Francis X.

Development of a Sub-Grid Liquid Jet Condensation Model

C

Cachon, L.

Experimental and Numerical Activities in Support of the Design of ASTRID Sodium-Gas Heat Exchanger

Cadiou, Thierry

Numerical Analysis of Core Thermal-Hydraulic for Sodium-Cooled Fast Reactors

Cai, Rong

Simulations of ECC Safety Injection for Single Phase and Stratified Phase Flow

Campello, Damien

The R&D PERFROI Project on Thermal Mechanical and Thermal Hydraulics Behaviors of a Fuel Rod Assembly during a Loss of Coolant Accident

Canepa, S.

Towards a Consolidated Approach for the Validation of Plant System Codes and Models: Case Study for a BWR Fast Depressurization Event

Cao, Liping

COBRA-TF Evaluation and Application for PWR Steamline Break DNB Analysis

Core Exit Thermocouple Response to Inadequate Core Cooling Using CFD Dynamic Mesh

Carasik, L. B.

URANS Simulations of Thermal Stratification in a Large Enclosure for Severe Accident Scenarios

Cardoni, Jeffrey Neil

RCIC Governing Equation Scoping Studies for Severe Accidents

Carenini, L.

Fukusima Core Melt Composition Simulation with ASTEC

Carloni, Dario

Analyses of LOCAs in the Primary Heat Transfer System of the Helium Cooled Pebble Bed Blanket Concept

Carnemolla, Sebastien

The R&D PERFROI Project on Thermal Mechanical and Thermal Hydraulics Behaviors of a Fuel Rod Assembly during a Loss of Coolant Accident

Carnevali, S.

Validation of CATHARE Code on the 3D ROSA-LSTF Pressure Vessel

Carotti, F.

Experimental and Modeling Studies of Over-Cooling Transients in Fluoride-Salt Cooled High-Temperature Reactors

Carpenter, Cassandra

Application of CD-ADAPCO Best Practices to NESTOR OMEGA MVG Benchmark Exercises Using STAR-CCM+

Carrilho, L. A.

Experimental and Computational Study of Ribbed Cladding for PWR Rod Bundles Heat Transfer Enhancement

Cassiaut-Louis, Nathalie

Plinius Prototypic Corium Experimental Platform: Major Results and Future Works

Castelliti, Diego

Experimental Fuel Pin Bundle Characterization in the NACIE-UP HLM Facility

Cati, Stefano

Caviezel, D.

DNS of Turbulent Convective Flow Boiling in a Channel

Ceccio, Steven L.

Experimental Characterization of Interchannel Mixing Through a Narrow Gap

Centrih, Vasilij

Influence of Oxidation on Fuel Coolant Interaction

Ceuca, S. C.

Investigation of Multidimensional Flow Mixing Phenomena in the Reactor Pressure Vessel with the System Code ATHLET

Chahi, H.

System Analysis and Isothermal Separate Effect Experiments of the Accident Behavior in PWR Spent Fuel Storage Pools

Chai, M.

Determination of In-Vessel Retention under Molten Corium Pool Attack

Chai, Penghui

Investigation of MCCI Phenomena with Multi-Physics MPS Simulation

Chalyy, R. V.

SOCRAT-BN Simulation of Siena Loss-of-Flow Experiments

Chandraker, D. K.

Quenching of a Heated Rod: Physical Phenomena and Heat Transfer

Chandraker, Dinesh Kumar

Design of High Power Density Annular Fuel Rod Core for Advanced Heavy Water Reactor

Chandraker, Dinesh

Chang, Huajian

Analysis of Wave Influence on Steam Condensation with Non-Condensable Gases Using CFD

CHF Experiment of RPV Lower Head with Real Surface Material for ERVC-IVR Strategy

Turbulent Convection Experiment to Support IVR Strategy

Chang, Seok-Kyu

Flow Mixing Characteristics in Subchannels of a Wire-Wrapped 61-Pin Rod Assembly for a Sodium-Cooled Fast Reactor

Measurements of the Flow Distribution in Subchannels of a Wire Wrapped 37-Pin Rod Assembly

Chang, Soon Heung

Onset of Flow Instability Due to the Mergence of Facing Bubble Layers in a Vertical Narrow Rectangular Channel

Chang, X.

Experimental and Numerical Study on Heat Transfer of Supercritical Water Flowing Upward in 2x2 Rod Bundles

Charon-Charles, Marylise

Experimental and Theoretical Study of Iron Concentration on Clogging Phenomenon in Secondary Circuit of Pressurized Nuclear Power Plant

Chatelain, A.

A Review of AREVA’s Experimental Validation of State-of-the-Art Single-Phase CFD Methods with Application to PWR Fuel Analysis and Design

Chatelain, Alexandre

Validation of AREVA’s Best Practices in the Round Robin CFD Benchmark

Chatelard, P.

Capability of ASTEC V2.1 to Simulate a Severe Accident in a Nuclear Power Plant —Application to a TMI-2-Like Accident Scenario

Chaudhari, V.

RELAP/SCDAPSIM/MOD4.0 Modification for Transient Accident Scenario of Test Blanket Modules Involving Helium Flows into Heavy Liquid Metal

Chaumeix, N.

Hydrogen Safety: Laminar and Turbulent Flame Speed of Spherical Flame in a Fan-Stirred Closed Vessel

Chen, Che-Hao

Assessment of Station Blackout Mitigation Strategy Applying the Ultimate Response Guideline to MAANSHAN PWR

Chen, G. L.

Research on Flow Characteristics for the Optimal Design of Experiment for the Typical Pressured Water Reactor

Chen, Gang

Requirements Analysis and Research of Severe Accident Process Simulation Based on COS-SA Code and Emergency Decision Support

Chen, Liuli

Experimental Study on Natural Circulation and Gas Injection Enhanced Circulation in KYLIN-II Mixed Circulation Loop

Chen, Minghui

Fabrication and Testing of a High-Temperature Printed Circuit Heat Exchanger

Chen, Peipei

An Experimental Study of Air-Water Pool Entrainment in High Gas Flux Region

ADS-IRWST Transient Evaluation Model for AP1000 SBLOCA Analysis

Chen, Qiaoyan

Investigation of Operational Charactistics of Passive Containment Cooling System for an Advanced PWR

Chen, R.H.

Experimental Investigation of CCFL in Pressurizer Surge Line with Air-Water

Chen, Ronghua

Simulations of ECC Safety Injection for Single Phase and Stratified Phase Flow

Chen, S. W.

The Analysis of TRACE/FRAPTRAN in Ultimate Response Guideline for Lungmen ABWR Nuclear Power Plant

Chen, Shao-Wen

Assessment of Station Blackout Mitigation Strategy Applying the Ultimate Response Guideline to MAANSHAN PWR

Methodology using MELCOR2.1/SNAP to Establish an SBO Model of Chinshan BWR/4 Nuclear Power Plant

Developments and Applications of TRACE/CFD Model of Maanshan PWR Pressure Vessel

Chen, Shaw-Wen

The Impact of Vertical Acceleration on the Nonlinear Behaviors of Multiple Parallel Boiling Channels

Chen, Y.

Critical Heat Flux with Subcooled Flowing Water in Tubes for Pressures from Atmosphere to Near-Critical Point

A Natural Circulation Experiment of Passive Residual Heat Removal Heat Exchanger for AP1000

Chen, Yixue

Requirements Analysis and Research of Severe Accident Process Simulation Based on COS-SA Code and Emergency Decision Support

Chen, Yushuang

Numerical Prediction of Turbulent Convective Heat Transfer with Molten Salt in Circular Pipe

Chenaud, Marie-Sophie

Computational Thermal Hydraulics Schemes for SFR Transients Studies

Cheng, Lap-Yan

Analysis of LOCA Scenarios in the NIST Research Reactor Before and After Fuel Conversion

TRACE/PARCS Analysis of ATWS with Instability for a MELLLA+ BWR/5

Cheng, Maosong

Preliminary Steady State and Transient Analysis of a Molten Salt Based Reactor using RELAP/SCDAPSIM/MOD4.0

Cheng, X.

Development and Validation of a Scaling Method for Supercritical Fluid Heat Transfer

Status and Challenges of Nuclear Thermal-Hydraulics Research in China

Cheng, Xu

Phase-Field Modeling of Binary Eutectic Alloy Solidification With Convection

Evaluation of Passive Containment Cooling with an Advanced Water Film Model in a Lumped-Parameter Code

Numerical Simulation on Melting and Solidification Based on Lagrangian Approach

Cheol Bang, In

Effects of Coating Structure by Al₂O₃ Nanoparticles Deposition on Critical Heat Flux of R123 in Flow Boiling

Quenching Performance in Nanofluids and Nanoparticles-Deposited Surfaces

Cherubini, Marco

Benchmark Analysis of EBR-II Protected Loss-of-Flow Transient

Cheung, F. B.

Enhancement of Downward Facing Boiling Heat Transfer by the Cold Spray Technique

Fundamental Experiments of Condensation Heat Transfer on Water Jets in the Presence of Noncondensable Gas

Cheung, Fan-Bill

Experimental Study of Laminar Mixed Convection in a Rod Bundle with Mixing Vane Spacer Grids

Chiang, Show-Chyuan

Assessment of Station Blackout Mitigation Strategy Applying the Ultimate Response Guideline to MAANSHAN PWR

Chiang, Yu

Methodology using MELCOR2.1/SNAP to Establish an SBO Model of Chinshan BWR/4 Nuclear Power Plant

Chikhi, N.

Experimental Study of Pressure Drops in Coarse Particle Beds,

Chikhi, Nourdine

First Experimental Results of Large Scale Debris Bed Reflood Tests in the PEARL Facility

Chino, Masamichi

Source Term Estimation for the Fukushima Daiichi Nuclear Power Station Accident by Combined Analysis of Environmental Monitoring and Plant Data Through Atmospheric Dispersion Simulation

Chiva, S.

Local Parameters of Air-Water Two-Phase Flow at a Vertical T-Junction

Cho, Chungho

Experimental Evaluation on Sodium-to-Air Heat Exchanger Performance for PGSFR Design Code Validation

Cho, Hyoung Kyu

Multi-Scale Thermal-Hydraulic Analysis of Safety Systems of Advanced PWRs using the CUPID Code

Cho, Hyoung-Kyu

Assessment of Multi-Dimensional Component of Mars with Air-Water Cross Flow Experiment

Heat Transfer Analysis of Horizontal U-Shaped Heat Exchanger Submerged in a Pool using MARS Code

Cho, Yeon-Sik

An SBLOCA Test of Pressurizer Safety Valve Line Break with the SMART-ITL Facility and its MARS-KS Code Simulation

Cho, Yongjin

Analysis of APR1400 Core Degradation under Cavity-Flooded Condition using MELCOR

Cho, Youngil

Experimental Evaluation on Sodium-to-Air Heat Exchanger Performance for PGSFR Design Code Validation

Choi, Chi-Jin

Assessment of Multi-Dimensional Component of Mars with Air-Water Cross Flow Experiment

Choi, Chiwoong

Validation of MARS-LMR Code for Heat Transfer Models in the DHRS of the PGSFR

Choi, Dong-Jae

Experimental Study of Condensation Heat Transfer in the Presence of Noncondensable Gas on the Vertical Tube

Choi, Hae Seob

Flow Mixing Characteristics in Subchannels of a Wire-Wrapped 61-Pin Rod Assembly for a Sodium-Cooled Fast Reactor

Measurements of the Flow Distribution in Subchannels of a Wire Wrapped 37-Pin Rod Assembly

Choi, Hae Sup

Experimental Evaluation of Local Bubble Parameters of Subcooled Boiling Flow in a Pressurized Vertical Annulus Channel

Choi, Hae-Seob

Effect of a Blockage Length on the Coolability during Reflood in a 2x2 Rod Bundle with a 90% Partially Blocked Region

Choi, Jinyoung

Development of CHF Mapping Method for Fin Structured Surface

Choi, K. Y.

Experimental Investigation on Thermal-Hydraulics Behavior during a Station Blackout Transient in a Pressurized Water Reactor

Choi, N. H.

Experimental Investigation on Thermal-Hydraulics Behavior during a Station Blackout Transient in a Pressurized Water Reactor

Choi, Seok-Ki

The Present State-of-the-Art Thermal Striping Studies for Sodium Cooled Fast Reactors

Choi, Sun Rock

Flow Mixing Characteristics in Subchannels of a Wire-Wrapped 61-Pin Rod Assembly for a Sodium-Cooled Fast Reactor

Choi, Young Jae

CHF Measurement for Downward Facing SUS 304 and Carbon Steel Plates under Atmospheric and Pool Boiling Conditions

Christensen, R. N.

Preliminary Structural Assessment of a Printed Circuit Heat Exchanger with S-Shaped Fins

Experimental Study of DRACS Thermal Performance in a Low-Temperature Test Facility

Christensen, Richard N.

Fabrication and Testing of a High-Temperature Printed Circuit Heat Exchanger

Christensen, Richard

Conceptual Design of Tritium Removal Facility for FHRs

Christon, Mark A.

Non-Linear Eddy Viscosity Turbulence Modeling in Hydra-TH for Fuel Related Applications

Chu, I. C.

On the Application of Wall Boiling Models to Prediction of Subcooled Flow Boiling using EAGLE Code

Chu, In-Cheol

Observation of CHF Phenomena Based on a Visualization of Near Wall Boiling Structure in Vertical Narrow Channel Submerged in a Pool

Experimental Evaluation of Local Bubble Parameters of Subcooled Boiling Flow in a Pressurized Vertical Annulus Channel

Chun, Chong Kuk

Assessment of the Best Estimate Thermal Design Method using THALES Subchannel Code

Chun, Chongkuk

Reactor Core Analysis at Low Flow Condition Using THALES Subchannel Code

Chung, B. D.

Analysis of Pressure Drop in Rod Bundles in Heavy Liquid Metal

Class, A.

Class, Andreas

Live Experiments on the In-Vessel Melt Pool Behaviour with Different External Cooling Conditions and the Simulation Results with a Coupled MELCOR-PECM Approach

Class, M. Viellieber A.

Investigating Reactor Components with the Coarse-Grid-Methodology

Clavier, R.

Experimental Study of Pressure Drops in Coarse Particle Beds,

Clifford, I.

Computational Fluid Dynamics Analysis of the Fluid Flow and Heat Transfer in the Core Bypass Region of a PWR

Cohen, Robert

Synthesis of CRUD and its Effects on Pool and Subcooled Flow Boiling

Colin, Catherine

Transient Convective Boiling: Analysis of Experimental Results

Collins, Benjamin

Validation and Application of the 3D Neutron Transport MPACT within CASL VERA-CS

Colombo, M.

Multiphase RANS Simulations of Turbulent Bubbly Flows

Cong, Tenglong

Application of RPI Model: Prediction of Subcooled Boiling and DNB in Vertical Pipes

Conner, Michael E.

Westinghouse CFD Modeling and Results for EPRI NESTOR CFD Round Robin Exercise of PWR Rod Bundle Testing

Conti, Alain

Numerical Analysis of Core Thermal-Hydraulic for Sodium-Cooled Fast Reactors

Corradini, M. L.

Experimental Investigation of a Scaled Reactor Cavity Cooling System with Air for the VHTR

Corradini, M.

Comparison of Experimental Critical Heat Flux Data to Prediction Methods for Conditions Prototypical of Light Water Small Modular Reactors

Analytical Modeling of a Scaled Reactor Cavity Cooling System (RCCS) with Air

Temperature Profiles and Mixing in a Natural Circulation Cooling Facility via Distributed Optical Sensors

U.S. DOE Severe Accident Research Following the Fukushima Daiichi Accidents

Corradini, Michael L.

Assessment of the MELCOR and RELAP5-3D Code for Condensation in the Presence of Noncondensable Gas

PHEBUS FPT-1 Simulation, using MELCOR: Blockage Model Analysis

Phenomenological Modeling Approach to Anisotropic Ablation in Molten Core Concrete Interactions

Corradini, Michael

Development of a Societal-Risk Goal for Nuclear Power Safety

Corradini, Mike

Reactor Safety Gap Evaluation of Accident Tolerant Components and Severe Accident Analysis

Costa, Alessandro

Molten Core Relocation Analysis of CORA-17 and CORA-18 for SAMPSON/MCRA Validation

Cowen, Haley Michelle

TRACG Analysis and Results of Phase 1 of the OECD/NEA Oskarshamn-2 BWR Stability Benchmark

Coy, Jorday

Graphite Oxidation Rates in Comparison to Regimes with Application to the Oregon State Over University High Temperature Test Facility

Coyle, Carolyn

Synthesis of CRUD and its Effects on Pool and Subcooled Flow Boiling

Cuadra, Arantxa

TRACE/PARCS Analysis of ATWS with Instability for a MELLLA+ BWR/5

D

D’Auria, Francesco

Benchmark Analysis of EBR-II Protected Loss-of-Flow Transient

Validation of CATHARE TH-SYS Code Against Experimental Reflood Tests

Scaling Issues for the Experimental Characterization of Reactor Coolant System in Integral Test Facilities and Role of System Code as Extrapolation Pool

Dabbene, Frederic

Nodalization Schemes for Lumped-Parameter Calculations of Representative Nuclear Reactor Severe Accident Tests in the MISTRA Facilty

Dai, Zhimin

Preliminary Steady State and Transient Analysis of a Molten Salt Based Reactor using RELAP/SCDAPSIM/MOD4.0

Damiani, Gemma

Calibration and Optimization of Pressurized Thermal Shock for Benchmarking Direct Numerical Simulation

Dances, C.

CTF Residual Formulation Solid Liquid Coupling

Dances, Christopher A.

Dang, V. N.

Ranking of Uncertain Parameters for Dynamic Event Tree Analysis: A Case Study based on a Station Blackout Scenario

Dasgupta, A.

Validation and Cross-Verification of Three Mechanistic Codes for Annular Two-Phase Flow Simulation and Dryout Prediction

Dasgupta, Arnab

Design of High Power Density Annular Fuel Rod Core for Advanced Heavy Water Reactor

Quenching of a Heated Rod: Physical Phenomena and Heat Transfer

Evaluating Performance of Two Group Interfacial Area Transport Equation for Large Diameter Pipes

Dave, A.

Dave, Akshay

Uncertainty Analysis of an Interfacial Area Reconstruction Algorithm

Dbai, M. Abou

Experimental and Modeling Studies of Over-Cooling Transients in Fluoride-Salt Cooled High-Temperature Reactors

de Bertodano, M. Lopez

On Well-Posedness and Stability of the Two-Fluid Model for Vertical Bubbly Flows

de Bertodano, Martin Lopez

Effect of Viscosity on a Well-Posed One-Dimensional Two-Fluid Model for Wavy Two-Phase Flow Beyond the Kelvin-Helmholtz Instability: Limit Cycles and Chaos

De Crecy, Agnes

Uncertainty Analysis of Delayed Equilibrium Model (DEM) using the CIRCE Methodology

De Fayard, R.

Measurements of the Vertical Distribution of the Void Fraction using X-ray Attenuation for Different Flow Regimes in a Horizontal Pipe

de les Valls, E. Mas

RELAP/SCDAPSIM/MOD4.0 Modification for Transient Accident Scenario of Test Blanket Modules Involving Helium Flows into Heavy Liquid Metal

de Paula, Alexandre Vagtinski

Symbolic Dynamics Applied in the Identification of Flow Patterns Inside Tube Banks

De Ridder, J.

CFD Benchmark for a Heavy Liquid Metal Fuel Assembly

De Rosa, Felice

Scaling Issues for the Experimental Characterization of Reactor Coolant System in Integral Test Facilities and Role of System Code as Extrapolation Pool

de Souza, T. Cardoso

Calibration of High Fidelity Bare Rod Bundle Simulations for Various Prandtl Fluids

de Souza, Thiago Cardoso

CFD Simulations to Determine the Effects of Deformations on Liquid Metal Cooled Wire Wrapped Fuel Assemblies

Degroote, J.

CFD Benchmark for a Heavy Liquid Metal Fuel Assembly

Dehbi, A.

A Generalized Correlation for Steam Condensation Rates in the Presence of Air-Helium Mixture

Del Nevo, A.

EBR-II Passive Safety Demonstration Tests Benchmark Analyses—Phase 2

Experimental and Numerical Investigations of Interaction Between Heavy Liquid Metal and Water for Supporting the Safety of LFR GEN. IV Reator Design

Qualification of a RELAP5-3D© System Code Nodalization of EBR-II

Experimental and Numerical Investigation of Double Wall Bayonet Tubes Performances in Pool Type Integral Test Facility

del Pra, Claudia Lopez

Lessons Learned from the Fukushima Analysis: The Modeling of Severe Accidents in Nuclear Power Plants

Delfino, C.

Commercial Grade Dedication of RELAP5-3D^©

Delfino, Claudio

NRELAP5 Predictions of KAIST High Pressure Condensation Data Using Existing and Extended Shah Condensation Correlation

Comparison of COBRA-TF and VIPRE-01 Against Low Flow Code Assessment Problems

Demaziere, C.

Wall Superheat Prediction in Narrow Rectangular Channels Under Fully Developed Boiling of Water at Low Pressures

Deng, Yangbin

Development of a Thermal-Mechanical-Material Behavior Analysis Code for the Dispersion-Plate-Type Fuel

Dennhardt, L.

Developments on High Pressure Two Phase Flow Measurement Techniques

Deokule, Abhijit Pandurang

Design of High Power Density Annular Fuel Rod Core for Advanced Heavy Water Reactor

Deshpande, Kaushik

Validation of CATHARE 3 Code on the PIERO Experiment

Di Pasquale, Yann

Di Piazza, I.

CFD Benchmark for a Heavy Liquid Metal Fuel Assembly

Di Piazza, I.

Di Piazza, Ivan

Fuel Pin Bundle Experimental Characterization in HLM Large Pool System

CFD Pre-Test Analysis of the Fuel Pin Bundle Simulator Experiment in the NACIE-UP HLM Facility

Experimental Fuel Pin Bundle Characterization in the NACIE-UP HLM Facility

Di, Zhi

An Experimental Study of Air-Water Pool Entrainment in High Gas Flux Region

Diakodimitris, C.

Thermal-Hydraulic Study of Siphon Breaking Phenomenon on a Two-Phase Gas/Liquid Flow

Conceptual Design Approach of Passive Cooling Systems

Diamond, David

Analysis of LOCA Scenarios in the NIST Research Reactor Before and After Fuel Conversion

TRACE/PARCS Analysis of ATWS with Instability for a MELLLA+ BWR/5

Didier, Jacquemain

Past and Future R&D at IRSN on Corium Progression and Related Mitigation Strategies in a Severe Accident

Didier, Vola

Past and Future R&D at IRSN on Corium Progression and Related Mitigation Strategies in a Severe Accident

Dietrich, Philipp

Live Experiments on the In-Vessel Melt Pool Behaviour with Different External Cooling Conditions and the Simulation Results with a Coupled MELCOR-PECM Approach

Ding, Wenjie

Implementation of Strong Implicit Procedure for the Energy Equations in Subchannel Code ATHAS

Dinh, Nam T.

Treatment of Nucleation and Bubble Dynamics in High Heat Flux Boiling

do Santos, R. S.

The Sub-Criticality Level Effects in Operational Transients of Beam Interruption in Power and Startup in Accelerator Driven Systems

Doda, Norihiro

Analysis of Natural Circulation Tests in the Experimental Fast Reactor JOYO

Dokhane, Abdelhamid

TRACE/SIMULATE-3K Analysis of the NEA/OECD Oskarshamn-2 Stability Benchmark

Dolleans, Philippe

Experimental and Theoretical Study of Iron Concentration on Clogging Phenomenon in Secondary Circuit of Pressurized Nuclear Power Plant

Dominguez, Cristina

The R&D PERFROI Project on Thermal Mechanical and Thermal Hydraulics Behaviors of a Fuel Rod Assembly during a Loss of Coolant Accident

Dong, B.

Experimental Investigation of CCFL in Pressurizer Surge Line with Air-Water

Dong, X. M.

Research on Flow Characteristics for the Optimal Design of Experiment for the Typical Pressured Water Reactor

Dong, Yujie

Analysis on Anticipated Transient Without SCRAMS (ATWS) Accidents of the HTR-10GT

Dooies, B.

Film-Droplet Split Correlation at the Onset of Annular-Mist Flow

Doolaard, H. J.

CFD Benchmark for a Heavy Liquid Metal Fuel Assembly

Doolaard, Heleen

Thermal-Hydraulic Study of the LBE-Cooled Fuel Assembly in the MYRRHA Reactor: Experiments and Simulations

Experimental Investigation of the Pressure Loss Characteristics of the Full-Scale MYRRHA Fuel Bundle in the COMPLOT LBE Facility

CFD Simulations to Determine the Effects of Deformations on Liquid Metal Cooled Wire Wrapped Fuel Assemblies

Dor, Isabelle

The CATHARE Code Condensation Modelling Confronted to the TOPFLOW-PTS Steady-State Experiments

Dornseiffer, Jürgen

A First Orienting Investigation of the Interaction of Cable Fire Products with Passive Auto-Catalytic Recombiners (PARs)

Douxchamps, P. A.

Conceptual Design Approach of Passive Cooling Systems

Douxchamps, P.-A.

Thermal-Hydraulic Study of Siphon Breaking Phenomenon on a Two-Phase Gas/Liquid Flow

Downar, Thomas J.

Validation and Application of the 3D Neutron Transport MPACT within CASL VERA-CS

Downar, Thomas

A Physical Mechanism for Rotating Lines of Symmetry in BWR Out-of-Phase Limit Cycle Oscillations

Drai, P.

Capability of ASTEC V2.1 to Simulate a Severe Accident in a Nuclear Power Plant —Application to a TMI-2-Like Accident Scenario

Driscoll, M. J.

Modeling of the Groundwater Transport Around a Deep Borehole Nuclear Waste Repository

Droin, Jean-Baptiste

Analytical Modelling of the Primary Phase of an Unprotected Loss of Flow

Du, Daiquan

Numerical Simulations of Turbulent Mixing Factor in 2x2 Rod Bundles at Supercritical Pressures

Du, Dongxiao

Theoretical Analysis of the Characteristics of Critical Heat Flux in Vertical Narrow Rectangular Channels Under Motion Conditions

Du, K.

Critical Heat Flux with Subcooled Flowing Water in Tubes for Pressures from Atmosphere to Near-Critical Point

A Natural Circulation Experiment of Passive Residual Heat Removal Heat Exchanger for AP1000

Du, Wangfang

Experimental Methods of the PCCS Containment Wall Condensation with Non-Condensable Gas

Du, Zheng

Experimental Investigation on Transient Heat Transfer Characteristics of C-Shape Heating Rod Bundle used in PRHR HX

Duan, M.

A Natural Circulation Experiment of Passive Residual Heat Removal Heat Exchanger for AP1000

Duan, Ri Qiang

Effect of End Plate on the Flow Crossing a Yawed Circular Cylinder

Duan, Y.

Numerical Investigation of Buoyancy-Aided Flow in Rod-to-Wall Gap Regions

Duarte, J. P.

Comparison of Experimental Critical Heat Flux Data to Prediction Methods for Conditions Prototypical of Light Water Small Modular Reactors

An Initial Uncertainty Analysis on the Critical Heat Flux Evaluation for a Small-Scale Pressurized Nuclear Reactor using the COBRA Code

Dumazet, Julien

Numerical Investigations of a Spent Fuel Storage Pool in Abnormal Conditions

Duponcheel, Matthieu

Implementation and Assessment of the Delayed Equilibrium Model for Computing Flashing Choked Flows into a Multi-Field CFD Code

Durse, Megan

Analysis of the AP1000® Passive Containment Cooling System Air Flow Path Using Computational Fluid Dynamics

Durville, Benoit

The R&D PERFROI Project on Thermal Mechanical and Thermal Hydraulics Behaviors of a Fuel Rod Assembly during a Loss of Coolant Accident

Duspiva, J.

Analytical Simulation of In-Vessel Retention Strategy for VVER-1000/320 Reactor using MELCOR Code

Duval, Fabien

On the Use of Hybrid RANS/LES Methods for the Simulation of the Erosion of a Stratified Layer by a Turbulent Buoyant Jet

Dzodzo, M. B.

Experimental and Computational Study of Ribbed Cladding for PWR Rod Bundles Heat Transfer Enhancement

E

E, Yanzhi

A Specialized Thermal-Hydraulic Code with Porous Media Model and SIMPLEC Algorithm for PB-FHRs

Eboli, M.

Transient Analyses for the MYRRHA-FASTEF Reactor by SIMMER Code

Eden, T. J.

Enhancement of Downward Facing Boiling Heat Transfer by the Cold Spray Technique

Ederli, Stefano

Single and Two-Phase Sodium Flow Analysis for two TUCOP CABRI Tests Using the ASTEC-Na Code

Edh, Nicholas

Tailored Experiments for Validation of CFD with FSI for Nuclear Applications

Edwards, Jacob

Steam Condensation in Packed Beds—An Experimental Study

Eiholzer, J.

Pulsed Injection Tracer Mixing in Annular Liquid Films

Einerson, Jeffrey J.

Uncertainty Quantification of Calculated Temperatures for Advanced Gas Reactor Fuel Irradiation Experiments

Eisenberg, J.

Interfacial Area Density Measurement using a Three-Layer Wire-Mesh Sensor

El-Genk, Mohamed S.

Convection Heat Transfer Analysis and Correlation for Alkali Liquid Metals in Uniformly Heated Tubes

SLIMM Decay Heat Removal by Natural Circulation of Ambient Air

Natural Circulation Model and Performance Analysis of “SLIMM”—A Small, Modular Reactor

Ellison, Phillip

Reactor Safety Gap Evaluation of Accident Tolerant Components and Severe Accident Analysis

Elsinga, G. E.

Natural Convection Driven Heat Transfer in Fluids with Strongly Variable Properties: A Particle Image Velocimetry Study

Emmanuel, Raimond

Past and Future R&D at IRSN on Corium Progression and Related Mitigation Strategies in a Severe Accident

Endo, Hiroto

Experimental Investigation of the High Performance Steam Injector Operation

Engelen, J.

Conceptual Design Approach of Passive Cooling Systems

Eoh, Jae-Hyuk

Experimental Evaluation on Sodium-to-Air Heat Exchanger Performance for PGSFR Design Code Validation

Epiney, A.

Towards a Consolidated Approach for the Validation of Plant System Codes and Models: Case Study for a BWR Fast Depressurization Event

Epiney, A.

Ranking of Uncertain Parameters for Dynamic Event Tree Analysis: A Case Study based on a Station Blackout Scenario

Epstein, Michael

An Explanation of BORAX-1, SPERT-1 and the SL-1 Accident

Investigation of MCCI Phenomena with Multi-Physics MPS Simulation

Erkan, Nedjet

Erkan, Nejdet

Analysis of Panda Spray Experiments Performed in Two Interconnected Vessels with OpenFOAM

Heat Transfer from Finned Surface in Downward-Facing Subcooled Flow Boiling

Erkhan, Nejdet

Passive Decay Heat Removal Capability of Fixed Bed Nuclear Reactor Fuel Chamber

Escobar, S. Castrillon

A Two-Scale Approach for Modeling the Corium Melt Fragmentation during Fuel-Coolant Interaction

Espinosa, Ruben

A Dynamic Model of Hydrostatic Reactor Coolant Pump Seals for RELAP5/MOD3.3

Euh, D. J.

On the Application of Wall Boiling Models to Prediction of Subcooled Flow Boiling using EAGLE Code

Euh, Dong Jin

Observation of CHF Phenomena Based on a Visualization of Near Wall Boiling Structure in Vertical Narrow Channel Submerged in a Pool

Experimental Evaluation of Local Bubble Parameters of Subcooled Boiling Flow in a Pressurized Vertical Annulus Channel

Euh, Dong-Jin

Condensation Heat Transfer Coefficient Correlation based on Slip Ratio Model in a Horizontal Heat Exchanger

Assessment of Multi-Dimensional Component of Mars with Air-Water Cross Flow Experiment

Flow Mixing Characteristics in Subchannels of a Wire-Wrapped 61-Pin Rod Assembly for a Sodium-Cooled Fast Reactor

Measurements of the Flow Distribution in Subchannels of a Wire Wrapped 37-Pin Rod Assembly

Evan Peters, Matt Hertel

Graphite Oxidation Rates in Comparison to Regimes with Application to the Oregon State Over University High Temperature Test Facility

Excoffon, Jacques

Experimental Study of Gas Entrainment from Surface Swirl

F

Fairweather, M.

Multiphase RANS Simulations of Turbulent Bubbly Flows

Fang, Jun

Interface Tracking Simulations of Bubbly Flows in the PWR Relevant Geometries

Fanning, T. H.

Recent Developments for the SAS4A/SASSYS-1 Safety Analysis Code

Farawila, Yousef M.

A Method to Prevent Severe Power and Flow Oscillations in Boiling Water Reactors

Analytical Stability Analogue for a Single-Phase Natural Circulation Loop

Farmer, M. T.

Fukushima Daiichi Unit 1 Ex-Vessel Prediction: Core Melt Spreading

U.S. DOE Severe Accident Research Following the Fukushima Daiichi Accidents

Farmer, Mitchell T.

Fukushima Daiichi Unit 1 Ex-Vessel Prediction: Core-Concrete Interaction

Key Findings and Remaining Questions in the Areas of Core-Concrete Interaction and Debris Coolability

Reactor Safety Gap Evaluation of Accident Tolerant Components and Severe Accident Analysis

Fauchet, Gauthier

Overview of the TRIOCFD Code: Main Features, V&V Procedures and Typical Applications to Nuclear Engineering

Fauske, Hans K.

An Explanation of BORAX-1, SPERT-1 and the SL-1 Accident

Fenoll, Marina Garcia

Control Rod Drop Transient: Uncertainty and Sensitivity Analysis of Thermal-Hydraulic Variables using a 3D Model with TRACE V5.0P3/PARCS 3.0

Fernandez-Moguel, L.

Analysis of the Fukushima Daiichi NPP Unit 3 with MELCOR_2.1

Fernandez, Elena

Lessons Learned from the Fukushima Analysis: The Modeling of Severe Accidents in Nuclear Power Plants

Ferrand, M.

Software Quality Assurance and V&V Procedure During the Development Stages of EdF CFD Tool Code_SATURNE: Focus on Verification Tests

Ferroni, P.

CFD Modeling of Sodium-Oxide Deposition in Sodium-Cooled Fast Reactor Compact Heat Exchangers

Ferroukhi, H.

Towards a Consolidated Approach for the Validation of Plant System Codes and Models: Case Study for a BWR Fast Depressurization Event

Computational Fluid Dynamics Analysis of the Fluid Flow and Heat Transfer in the Core Bypass Region of a PWR

Ferroukhi, Hakim

TRACE/SIMULATE-3K Analysis of the NEA/OECD Oskarshamn-2 Stability Benchmark

Fichot, F.

Capability of ASTEC V2.1 to Simulate a Severe Accident in a Nuclear Power Plant —Application to a TMI-2-Like Accident Scenario

Experimental Study of Pressure Drops in Coarse Particle Beds,

First Experimental Results of Large Scale Debris Bed Reflood Tests in the PEARL Facility

Figley, Justin

Core Exit Thermocouple Response to Inadequate Core Cooling Using CFD Dynamic Mesh

Fiori, F.

Assessment Study of RELAP5/SCDAP Capability to Reproduce Liquid Metal Tall Facility Thermal Hydraulic Behaviour

Fischer, Manfred

Core Melt Stabilization Concepts for Existing and Future LWRs and Associated R&D Needs

Fischer, P.

CFD Benchmark for a Heavy Liquid Metal Fuel Assembly

Calibration and Optimization of Pressurized Thermal Shock for Benchmarking Direct Numerical Simulation

Fischer, Paul

Erosion of a Large-Scale Gaseous Stratified Layer by a Turbulent Round Jet S—Simulations with URANS and LES Approaches

Large-Scale Simulation of Nuclear Reactors: Issues and Perspectives

Verification and Validation of Nek5000 for T-Junction, Matis, SIBERIA, and Max Experiments

Florian, Fichot

Past and Future R&D at IRSN on Corium Progression and Related Mitigation Strategies in a Severe Accident

Fontaine, J.

Software Quality Assurance and V&V Procedure During the Development Stages of EdF CFD Tool Code_SATURNE: Focus on Verification Tests

Fontanet, Joan

Lessons Learned from the Fukushima Analysis: The Modeling of Severe Accidents in Nuclear Power Plants

Forgione, N.

Transient Analyses for the MYRRHA-FASTEF Reactor by SIMMER Code

Experimental and Numerical Investigations of Interaction Between Heavy Liquid Metal and Water for Supporting the Safety of LFR GEN. IV Reator Design

Forgione, Nicola

Fuel Pin Bundle Experimental Characterization in HLM Large Pool System

Experimental Fuel Pin Bundle Characterization in the NACIE-UP HLM Facility

Forsyth, David R.

Impact of Flow Induced Vibration Acoustic Loads on the Design of the Peach Bottom Replacement Steam Dryer

Fortman, R. A.

Qualification of CHF Test Facility at Stern Laboratories using Mitsubishi PWR Fuel

Single-Phase and Two-Phase CFD Simulations of the Coolant Flow Inside a Bruce/Darlington CANDU Flow Channel

Foubert, F.

First Experimental Results of Large Scale Debris Bed Reflood Tests in the PEARL Facility

Fouquart, Pascal

Plinius Prototypic Corium Experimental Platform: Major Results and Future Works

Franceschini, Fausto

Validation and Application of the 3D Neutron Transport MPACT within CASL VERA-CS

Francis, M. W.

Fukushima Daiichi Unit 1 Ex-Vessel Prediction: Core Melt Spreading

Francis, Matthew W.

Fukushima Daiichi Unit 1 Ex-Vessel Prediction: Core-Concrete Interaction

Francis, Matthew

Reactor Safety Gap Evaluation of Accident Tolerant Components and Severe Accident Analysis

Freels, James D.

Advanced Multiphysics Thermal-Hydraulics Models for the High Flux Isotope Reactor

Freeman, John

Boiled-Up Pool Heat Transfer for a Horizontal Tube Bundle

Freitas, Roberto

Validation of CATHARE 3 Code on the PIERO Experiment

Freixa, J.

Revisiting ISP-13 with RELAP/SCDAPSIM/MOD3.5 using Core SCDAP Components

Freixa, Jordi

Core Exit Temperature Response during an SBLOCA Event in the Ascó NPP

Freixa,, J.

RELAP/SCDAPSIM/MOD4.0 Modification for Transient Accident Scenario of Test Blanket Modules Involving Helium Flows into Heavy Liquid Metal

Frepoli, C.

On the Definition of a Minimum Set of Requirements to Assess the Adequacy of the RELAP5-3D Multidimensional Flow Capability with Selected Canonical Problems

Simulation of Faraday Waves with RELAP5-3D Thermal-Hydraulic Code

On the Level of Approximation of the Multi-Dimensional Potential Flow Solution in Complex Geometries with Thermal-Hydraulic System Codes

Frepoli, Cesare

10 CFR 50.46c Rulemaking: A Novel Approach in Restating the LOCA Problem for PWRs

Experimental Test Facility Data Synthesis with the Dynamical System Scaling Methodology

Demonstration of Test Facility Design Optimization with the Dynamical System Scaling Methodology

The Dynamical System Scaling Methodology: Comparing Dimensionless Governing Equations with the H2TS and FSA Methodologies

Fricano, J. W.

On the Definition of a Minimum Set of Requirements to Assess the Adequacy of the RELAP5-3D Multidimensional Flow Capability with Selected Canonical Problems

Simulation of Faraday Waves with RELAP5-3D Thermal-Hydraulic Code

On the Level of Approximation of the Multi-Dimensional Potential Flow Solution in Complex Geometries with Thermal-Hydraulic System Codes

Frid, Wiktor

Measurement of Wall Temperature Fluctuations During Thermal Mixing of Non-Isothermal Water Streams

Frutuoso e Melo, Paulo Fernando F.

Simulation of the Inadvertent Rod Cluster Control Assembly Bank Withdrawal at Power for ANGRA I NPP using an LQR Digital Controller

Frutuoso e. Melo, P. F.

An Initial Uncertainty Analysis on the Critical Heat Flux Evaluation for a Small-Scale Pressurized Nuclear Reactor using the COBRA Code

Frybort, O.

Blind and Aftermath Numerical Analyses of Supercritical Water Flow and Heat Transfer in 1/12 of 7-Rod Bundle with Spacers

Fu, Wen

Assessment of the MELCOR and RELAP5-3D Code for Condensation in the Presence of Noncondensable Gas

Fu, X.L.

Experiment of Condensation in T-Junction: Steam-Water Flow in Water-Injected Condition

Fu, Yao

Loss of Coolant Flow Accident Analysis for Fluoride Salt Cooled High Temperature Reactor

Disturbed Transient Analysis with Stable Operation Mode of TMSR-SF1

New AESJ Thermo-Hydraulics Roadmap for LWR Safety Improvement and Development after Fukushima-Daiichi Accident

Fujii, Tadashi

Fukano, Yoshitaka

Safety Margins after Failure of Fuel Cladding during Protected Loss-of-Heat-Sink Accidents in a Sodium-Cooled Fast Reactor

Fukuda, K.

Influence of Boiling Initiation Surface Superheat on Subcooled Water Flow Boiling Critical Heat Flux in a SUS304 Circular Tube at High Liquid Reynolds Number

Fukuda, Katsuya

Numerical Solution of Heat Transfer Process in a Prismatic VHTR Considering Core Bypass Flow and Cross Flow

Fullmer, W. D.

On Well-Posedness and Stability of the Two-Fluid Model for Vertical Bubbly Flows

Fullmer, William D.

Effect of Viscosity on a Well-Posed One-Dimensional Two-Fluid Model for Wavy Two-Phase Flow Beyond the Kelvin-Helmholtz Instability: Limit Cycles and Chaos

Assessment of RELAP5/MOD3.3 for Subcooled Boiling, Flashing and Condensation in a Vertical Annulus

Furuya, Masahiro

Suppression Measures and Effective Triggering Retardant of Steam Explosions

Analysis of Metal Vessel Wall Ablation Experiment with High Temperature Liquid by MPS Method

Boiled-Up Level and Boiling Two-Phase Flow Dynamics in 5x5 Heated Rod Bundle during Boil-Off Process under Atmospheric Pressure Conditions

G

Gabor, Jeff R.

Reactor Safety Gap Evaluation of Accident Tolerant Components and Severe Accident Analysis

Gabor, Jeff

Gabriel, Harry

ORFEOTM—A CHF Correlation Form Applied to GAIA, AREVA’s Advanced PWR Fuel Assembly Design

Gaillard, Pierre

The CATHARE Code Condensation Modelling Confronted to the TOPFLOW-PTS Steady-State Experiments

Gajev, Ivan

TRACE/SIMULATE-3K Analysis of the NEA/OECD Oskarshamn-2 Stability Benchmark

Galarin, Jérémie

OSCARD Coupling Software for Main Steam Line Break Fault Analysis—Assessment of the Mixing Phenomena in the Vessel

Galati, C.

Experimental and Numerical Activities in Support of the Design of ASTRID Sodium-Gas Heat Exchanger

Galimov, Azat

Comparison of COBRA-TF and VIPRE-01 Against Low Flow Code Assessment Problems

Gallardo, Sergio

Analysis of Kv in Power-to-Volume Scaling. Application to a SBLOCA Transient

Galushin, S.

Development of TEXAS-V Code Surrogate Model for Assessment of Steam Explosion Impact in Nordic BWR

Gam, Da-Young

Experimental Evaluation on Sodium-to-Air Heat Exchanger Performance for PGSFR Design Code Validation

Gan, Fujun

Developments on High Pressure Two Phase Flow Measurement Techniques

Ganzmann, I.

Gao, Sheng

Experimental Study on Natural Circulation and Gas Injection Enhanced Circulation in KYLIN-II Mixed Circulation Loop

Gao, Zhan

Experimental Methods of the PCCS Containment Wall Condensation with Non-Condensable Gas

Garcia, Oscar Puebla

A Validation of Westinghouse Mechanistic and Empirical Dryout Prediction Methods Under Realistic BWR Transient Conditions

Garcin, T.

First Experimental Results of Large Scale Debris Bed Reflood Tests in the PEARL Facility

Garrett, Alfred J.

Thermal Hydraulics Analysis for Cooling Tower Performance

Gaudron, B.

Numerical Investigations of a Spent Fuel Storage Pool in Abnormal Conditions

Gauntt, Randall O.

Overview and Outcomes of Benchmark Study of the Accident at the Fukushima Daiichi NPS (OECD/NEA BSAF Project)

Gauntt, Randy

Reactor Safety Gap Evaluation of Accident Tolerant Components and Severe Accident Analysis

Gaus-Liu, Xiaoyang

Live Experiments on the In-Vessel Melt Pool Behaviour with Different External Cooling Conditions and the Simulation Results with a Coupled MELCOR-PECM Approach

Ge, Li

Thermal-Hydraulic Design and Transient Analysis of Passive Air Cooling System for CPR1000 Spent Fuel Storage Pool

Analysis of the SBLOCA on the Improved CPR1000 with Passive Systems

Typical Accidents Analysis on the Loss of Flow and External Neutron Source Changing Accidents for a 800 MWth ADS

Ge, Zengfang

Thermal-Hydraulic Design and CFD Analysis of Fuel Assembly for China Lead-Based Research Reactor

Geffray, C.

Multiscale Analysis of Forced and Natural Convection Including Heat Transfer Phenomena in the TALL-3D Experimental Facility

Gehin, Jess

Validation and Application of the 3D Neutron Transport MPACT within CASL VERA-CS

Geissler, Thomas

Experimental and Numerical Investigation of Flow Structure and Heat Transfer During High Pressure Condensation in a Declined Pipe at COSMEA Facility

George, T. L.

GOTHIC 8.1 Benchmark to THAI Facility Experiment with Steam-Helium Stratification

Development of a Multiple Liquid Component Capability in GOTHIC to Better Support Boric Acid, Radiological, and GSI-191 Analyses

Momentum Convection within the Staggered Grid Formulation

Containment Analysis of Fukushima Daiichi Unit 1 Power Station using GOTHIC

A Lumped Parameter Modeling for Mixing and Stratification in a BWR Mark I Pressure Suppression Pool

Gerardi, Craig D.

Thermal Cycling Testing of Distributed Fiber Optic Temperature Sensors for High-Temperature Applications

Distributed Temperature Sensor Testing in Liquid Sodium

Gerardi, Craig

Key Findings and Remaining Questions in the Areas of Core-Concrete Interaction and Debris Coolability

Gergar, M.

CTF Void Drift Validation

Germain, Philippe

The CATHARE Code Condensation Modelling Confronted to the TOPFLOW-PTS Steady-State Experiments

Gerschenfeld, Antoine

Numerical Analysis of Core Thermal-Hydraulic for Sodium-Cooled Fast Reactors

Simulation of GR19 Sodium Boiling Experiments with CATHARE 2 System Code and TRIO_U MC Subchannel Code

Computational Thermal Hydraulics Schemes for SFR Transients Studies

Ghione, A.

Wall Superheat Prediction in Narrow Rectangular Channels Under Fully Developed Boiling of Water at Low Pressures

Giannini, N.

Experimental and Numerical Investigations of Interaction Between Heavy Liquid Metal and Water for Supporting the Safety of LFR GEN. IV Reator Design

Giannotti, Daniel

Experimental Fuel Pin Bundle Characterization in the NACIE-UP HLM Facility

Gibert, R .J.

Experimental and Analytic Study of the Damped Rocking Movement of a Cylindrical Shell in a Flowing Annular Channel

Gilad, Erez

Analysis of Protected RIA and LOFA in Plate Type Research Reactor Using Coupled Neutronics Thermal-Hydraulics System Code

Gimeno, L. Sanmiguel

Validation and Cross-Verification of Three Mechanistic Codes for Annular Two-Phase Flow Simulation and Dryout Prediction

Gingrich, C.

Development, Validation and Assessment of the TRACE Thermal-Hydraulics Systems Code

Giust, F.

Assessment of TRACE/PARCS Benchmark Against Leibstadt Plant Data During the Turbine Trip Test

Giustini, G.

Interface Tracking Based Evaluation of Bubble Growth Rates in High Pressure Pool Boiling Conditions

Giustini, Giovanni

Microlayer Models for Nucleate Boiling Simulations: The Significance of Conjugate Heat Transfer

Numerical Study of Heat Diffusion Controlled Bubble Growth in a Pressurised Liquid

Glantz, Tony

Core Coolability in Loss of Coolant Accident: The COAL Experiments

Godfrey, Andrew

Validation and Application of the 3D Neutron Transport MPACT within CASL VERA-CS

Goel, Paridhi

Development of a Computational Model to Determine Performance of a Self-Priming Venturi Scrubber for Thorium Reactor

Golay, M.

Balance of Plant and Power Transmission for the Offshore Floating Nuclear Plant

Ocean-Based Passive Decay Heat Removal in the Offshore Floating Nuclear Plant (OFNP)

Golchert, Brian M.

Computational Fluid Dynamics Assessment of Emergency Core Cooling System Check Valves at Comanche Peak

Gomez, Ana Jambrina

Analysis of Improved Fuel Rod Modeling in Coupled Thermal-Hydraulics/Neutronics Calculations

Gonfiotti, Bruno

Analyses of LOCAs in the Primary Heat Transfer System of the Helium Cooled Pebble Bed Blanket Concept

Gong, Houjun

Evaluation of RELAP5/MOD3.2 for ACP1000 Passive Residual Heat Removal System

Gong, Shengjie

Hot Fuel Element Thermal-Hydraulic Modeling in the Jules Horowitz Reactor Nominal and LOFA Conditions

Gonnier, Christian

Goodheart, K.

A Review of AREVA’s Experimental Validation of State-of-the-Art Single-Phase CFD Methods with Application to PWR Fuel Analysis and Design

Goodheart, Kevin

Validation of AREVA’s Best Practices in the Round Robin CFD Benchmark

Gorade, G. J.

Quenching of a Heated Rod: Physical Phenomena and Heat Transfer

Gordon, D.

Developments on High Pressure Two Phase Flow Measurement Techniques

Gorsse, Yannick

Numerical Analysis of Core Thermal-Hydraulic for Sodium-Cooled Fast Reactors

Gosdin, C.

CTF Application to BWR Modeling and Simulations

Gose, Garry

Comparison of COBRA-TF and VIPRE-01 Against Low Flow Code Assessment Problems

Gou, Junli

Thermal-Hydraulic Design and Transient Analysis of Passive Air Cooling System for CPR1000 Spent Fuel Storage Pool

Analysis of the SBLOCA on the Improved CPR1000 with Passive Systems

Improvement and Validation of the Wall Heat Transfer Package of RELAP5/MOD3.3

Study on Startup Characteristics of Heat Pipe Cooled Space Reactor

Typical Accidents Analysis on the Loss of Flow and External Neutron Source Changing Accidents for a 800 MWth ADS

Accident Analysis of Heat Pipe Cooled Space Reactor

Gould, Dan

Thermal Effects of Material Discontinuities and Oxidation on Graphite Matrix in HTGRs

Gould, Daniel

Steam Condensation in Packed Beds—An Experimental Study

Goulier, J.

Hydrogen Safety: Laminar and Turbulent Flame Speed of Spherical Flame in a Fan-Stirred Closed Vessel

Gradeck, M.

A Two-Scale Approach for Modeling the Corium Melt Fragmentation during Fuel-Coolant Interaction

Gradeck, Michel

The R&D PERFROI Project on Thermal Mechanical and Thermal Hydraulics Behaviors of a Fuel Rod Assembly during a Loss of Coolant Accident

Greco, M.

Pre-Test Computational Fluid Dynamics and System Thermal Hydraulics Calculations of The E-SCAPE Scaled LBE Pool Facility

Greco, Matteo

Experimental Results from a Water Scale Model for the Thermal-Hydraulic Analysis of a HLM Reactor

Greenwood, M. S.

Comparison of Experimental Critical Heat Flux Data to Prediction Methods for Conditions Prototypical of Light Water Small Modular Reactors

Gregor, K.

Blind and Aftermath Numerical Analyses of Supercritical Water Flow and Heat Transfer in 1/12 of 7-Rod Bundle with Spacers

Gremme, Florian

ASTEC Simulation of a SBO with Re-Flood in a German KONVOI NPP

Grischenko, D.

Multiscale Analysis of Forced and Natural Convection Including Heat Transfer Phenomena in the TALL-3D Experimental Facility

Grishchenko, D.

Development of TEXAS-V Code Surrogate Model for Assessment of Steam Explosion Impact in Nordic BWR

Grishchenko, Dmitry

Development of TALL-3D Test Matrix for APROS Code Validation

Experimental Investigation of Debris Bed Agglomeration and Particle Size Distribution using WO3-ZRO2 Melt

Grissom, Phil

RoverD: Use of Test Data in GSI-191 Risk Assessment

Grunloh, Timothy Paul

Comparison of Overlapping and Separate Domain Coupling Methods

Gruy, Frederic

Numerical Modeling of the Two-Phase Underexpanded Reactive CO₂-into-Sodium Jets in the Frame of Sodium Nuclear Fast Reactors

Gu, H. Y.

Experimental and Numerical Study on Heat Transfer of Supercritical Water Flowing Upward in 2x2 Rod Bundles

Gu, Hanyang

Concept Design and Thermal-Hydraulic Analysis for Helium-Cooled ADS

Gu, Long

Guba, Attila

Sources and Effects of Non-Condensable Gases in Reactor Coolant System of LWR

Gudibande, Niranjan

Thermal Shrinkage Based Model for Predicting the Voids during Solidification of Lead

Guénadou, D.

Plateau Facility in Support to ASTRID and the SFR Program: An Overview of the First Mock-Up of the ASTRID Upper Plenum MICAS

Guilbert, P. W.

Assessment of an Interfacial Shear Term for Adiabatic Dispersed Air-Water Two-Phase Flow with the Two-Fluid Model

Guillodo, Michael

Experimental and Theoretical Study of Iron Concentration on Clogging Phenomenon in Secondary Circuit of Pressurized Nuclear Power Plant

Guingo, M.

Verification, Validation and Application of Neptune _ CFD to Two-Phase Pressurized Thermal Shocks

Combined Evaluation of Bubble Dynamics, Polydispersion Model and Turbulence Modeling for Adiabatic Two-Phase Flows

Guingo, Mathieu

Progress on Computation of Boiling Flow in Fuel Assemblies with NEPTUNE_CFD

A Generalized Turbulent Dispersion Model for Bubbly Flow Numerical Simulation in NEPTUNE_CFD

Guo, Liancheng

A New Lumped Thermal Resistance Heat Transfer Model for Fuel Pin Structure

Guo, Yujun

On the Aspect of Evaluation of Critical Channel Power and Associated Uncertainty in CANDU Slow Loss of Regulation Event Analysis

Guo, Z.

Development of the FHR Advanced Natural Circulation Analysis (FANCY) Code

Experimental Strategy for the Determination of Heat Transfer Coefficients in Pebble-Beds Cooled by Fluoride Salts

Design, Fabrication and Startup Testing in the Compact Integral Effects Test Facility in Support of Fluoride-Salt-Cooled, High-Temperature Reactor Technology

Validation of Best Estimate Models for Fluoride-Salt-Cooled, High-Temperature Reactors Using Data from the Compact Integral Effects Test (CIET 1.0) Facility

Gupta, Sanjeev

Passive Autocatalytic Recombiners (PAR) Induced Ignition and the Resulting Hydrogen Deflagration Behaviour in LWR Containments

Guzzetta, Ashley

Unique Challenges in Making a Regulatory Decision Regarding the Combined Effects of Boric Acid Precipitation and GSI-191

H

Ha, K. S.

Detailed Analysis of Geometry Effect on Two Phase Natural Circulation Flow under IVR-ERVC

Ha, Kwang Soon

Effect of External Water Injection on Core Degradation and Fission Product Release in Fukushima Unit 1 Accident

Flow Structure in Core Catcher Cooling Loop Through an Inclined-to-Vertical Elbow Bend

VESTA Test Facility for Severe Accident Researches at KAERI

Analysis of Fukushima Unit 2 Accident by Considering the Operating Condition of RCIC System and Torus Room Flooding

Ha, KwangSoon

Thermal Hydraulic and Core Relocation Analysis on Fukushima Daiichi Unit 1

Ha, Kwiseok

Validation of MARS-LMR Code for Heat Transfer Models in the DHRS of the PGSFR

Ha, Sang-Jun

Operational Experience of Ceramic Honeycomb Passive Autocatalytic Recombiner as a Hydrogen Mitigation System

Hadaller, G. I.

Qualification of CHF Test Facility at Stern Laboratories using Mitsubishi PWR Fuel

Single-Phase and Two-Phase CFD Simulations of the Coolant Flow Inside a Bruce/Darlington CANDU Flow Channel

Haensch, Susann

Microlayer Models for Nucleate Boiling Simulations: The Significance of Conjugate Heat Transfer

Hagaman, Jordan

Experimental Research on Non-Condensable Gases Effects in Passive Decay Heat Removal System

Hai-jun, Jia

Halford, Noah

Large-Scale Simulation of Nuclear Reactors: Issues and Perspectives

Hallehn, Anders

Detailed Measurements of Local Parameters in Annular Two-Phase Flow in Fuel Bundle under BWR Operating Conditions

High Resolution Thermal Mixing at Westinghouse ODEN Loop

Hamazaki, Ryoichi

A Study on Transient Heat Transfer of the EU-ABWR External Core Catcher using the Phase-Change Effective Convectivity Model

Core Melt Stabilization Concepts for Existing and Future LWRs and Associated R&D Needs

Hammond, Gregory

Development of a Societal-Risk Goal for Nuclear Power Safety

Hammouda, N.

On the Aspect of Evaluation of Critical Channel Power and Associated Uncertainty in CANDU Slow Loss of Regulation Event Analysis

Hampel, U.

Spatially-Resolved Measurement of Gas Phase Temperature and Velocity in the Subchannels of a Fuel Element during Dry-Out

Hampel, Uwe

Investigations on Centrifugal Pumps under Air Entrainment Conditions

Han, Bin

Numerical Study on the Effects of Vane Angle and Dimple on the Thermal Hydraulic Performance of a PWR Fuel Assembly

Han, Ji-Woong

The Present State-of-the-Art Thermal Striping Studies for Sodium Cooled Fast Reactors

Han, Liyong

Analysis of Wave Influence on Steam Condensation with Non-Condensable Gases Using CFD

Han, Xiaofeng

Investigation of Operational Charactistics of Passive Containment Cooling System for an Advanced PWR

Hanamoto, Yukio

An Approach Toward Evaluation of FP Behaviors in NPPs Under Severe Accidents

Haneklaus, N.

Thermal Hydraulic Benchmarking Exercises to Support Fluoride-Salt-Cooled, High-Temperature Reactor (FHR) Licensing

Hanophy, Joshua T.

Towards a Coupled Simulation of Thermal Hydraulics and Neutronics in a Simplified PWR with a 3x3 Pin Assembly

Hans-Josef

Haquet, Jean Fram;ois

Needs for Large Mass Phototype Corium Experiments: The PLINIUS-2 Platform

Haratyk, G.

Compact Steam Generator for Nuclear Application

Hardgrove, Matthew

Axial Conduction Nodalization for TRACE/PARCS Analysis of ATWS with Instability Peter Yarsky, Matthew Hardgrove (NRC)

Harmon, P. L.

Comprehensive Characterization of Motion of a Helical Structure Due to Flow Induced Vibration

Harne, Richard L.

ORFEOTM—A CHF Correlation Form Applied to GAIA, AREVA’s Advanced PWR Fuel Assembly Design

Hartz, Josh

Core Exit Thermocouple Response to Inadequate Core Cooling Using CFD Dynamic Mesh

Haselbauer, Maxime

Numerical Analyses on the Safety Aspects of KASOLA Test Facility

Hasenbein, John

RoverD: Use of Test Data in GSI-191 Risk Assessment

Hashimoto, Yusuke

Subcooled Boiling-Induced Vibration of a Single Heater Rod Confined with Metallic Walls

Haskin, Troy C.

PHEBUS FPT-1 Simulation, using MELCOR: Blockage Model Analysis

Haskins, Denise

Natural Circulation Model and Performance Analysis of “SLIMM”—A Small, Modular Reactor

Hassan, Y. A.

URANS Simulations of Thermal Stratification in a Large Enclosure for Severe Accident Scenarios

MELCOR and GOTHIC Analyses of a Large Dry Pressurized Water Reactor Containment to Support Resolution of GSI-191

A Sensitivity Study Supporting Comparative Analysis of MELCOR and GOTHIC Large Dry Pressurized Water Reactor Containment Models

CFD Investigation of Wire-Wrapped Fuel Rod Bundles and Flow Sensitivity to Bundle Size

Hassan, Yassin A.

Experimental Observations of Boric Acid Precipitation Scenarios

CFD Simulations of Erosion of a Stratified Layer by a Buoyant Jet in a Large Vessel Fatih Sinan Sarikurt

The Effect of Electric Potential on Fibrous Debris Bypass Through a Containment Sump Strainer

Hassan, Yassin

CFD Methodologies for a PWR Fuel Rod Assembly

Hassanaly, M.

Combined Evaluation of Bubble Dynamics, Polydispersion Model and Turbulence Modeling for Adiabatic Two-Phase Flows

Assessment of RANS at Low PRANDTL Number and Simulation of Sodium Boiling Flows with a CMFD Code

Hata, Koichi

Influence of Boiling Initiation Surface Superheat on Subcooled Water Flow Boiling Critical Heat Flux in a SUS304 Circular Tube at High Liquid Reynolds Number

Hatman, A.

A Review of AREVA’s Experimental Validation of State-of-the-Art Single-Phase CFD Methods with Application to PWR Fuel Analysis and Design

Hatman, Anca

Validation of AREVA’s Best Practices in the Round Robin CFD Benchmark

Haurais, F.

Hawkes, Grant L.

Uncertainty Quantification of Calculated Temperatures for Advanced Gas Reactor Fuel Irradiation Experiments

He, Hui

Experimental Study of Pressure Drop and Modelling of Interfacial Shear for Vertical Annular Flow

He, S.

MyrrhaFoam: A CFD Model for the Study of the Thermal Hydraulic Behavior of MYRRHA

Numerical Investigation of Buoyancy-Aided Flow in Rod-to-Wall Gap Regions

Direct Numerical Simulation of Fluid Flow at Supercritical Pressure in a Vertical Channel

Heck, C.

Reactor Core Isolation Cooling TRACG Model

Heck, Charles

Hedberg, P.

Sampling Variance and Bias of Wilks’ Conservative Estimate of Confidence Intervals

Hedberg, Peter Karl Martin

Use of Deterministic Sampling for Uncertainty Quantification in CFD

Hedberg, S.

Instrumentation for Temperature and Heat Flux Measurement on a Solid Surface under BWR Operating Conditions

Hedberg, Stellan

Measurement of Wall Temperature Fluctuations During Thermal Mixing of Non-Isothermal Water Streams

Heidelberg, Daniel

A First Orienting Investigation of the Interaction of Cable Fire Products with Passive Auto-Catalytic Recombiners (PARs)

Heisel, V.

Assessment of RANS at Low PRANDTL Number and Simulation of Sodium Boiling Flows with a CMFD Code

Hemple, Uwe

Experimental and Numerical Investigation of Flow Structure and Heat Transfer During High Pressure Condensation in a Declined Pipe at COSMEA Facility

Henry, Robert E.

An Explanation of BORAX-1, SPERT-1 and the SL-1 Accident

Boiled-Up Pool Heat Transfer for a Horizontal Tube Bundle

Heo, Hyo

Heat Removal Characteristics of IVR-ERVC Cooling System Using Gallium Liquid Metal

A Visual Study of Molten Metal Fuel Coolant Interactions Under an Initial Phase of SFR Severe Accident using Gallium Metal vs Water or R123

Heo, J. S.

Developments on High Pressure Two Phase Flow Measurement Techniques

Herbst, O.

Herer, Christophe

Margins to Critical Heat Flux in Pressurized Water Reactors using Modern Thermal-Hydraulic Methods

Hering, W.

On the Liquid Metal Heat Transfer in Annular Channels: Review, Proposal and Validation of Empirical Models

Hering, Wolfgang

Numerical Analyses on the Safety Aspects of KASOLA Test Facility

Herranz, Luis E.

Lessons Learned from the Fukushima Analysis: The Modeling of Severe Accidents in Nuclear Power Plants

Herrero, Rafael Miro

Control Rod Drop Transient: Uncertainty and Sensitivity Analysis of Thermal-Hydraulic Variables using a 3D Model with TRACE V5.0P3/PARCS 3.0

Hessling, J. P.

Sampling Variance and Bias of Wilks’ Conservative Estimate of Confidence Intervals

Hessling, Peter Jan

Use of Deterministic Sampling for Uncertainty Quantification in CFD

Hewitt, G. F.

Validation and Cross-Verification of Three Mechanistic Codes for Annular Two-Phase Flow Simulation and Dryout Prediction

Hibiki, T.

Turbulence-Induced Bubble Collision Force Model Development and Assessment for Adiabatic Dispersed Air-Water Two-Phase Flow with the Two-Fluid Model

Assessment of an Interfacial Shear Term for Adiabatic Dispersed Air-Water Two-Phase Flow with the Two-Fluid Model

Evaluation of Interfacial Area Transport Equation in Coupled Two-Fluid Model Computation

Hibiki, Takashi

Development and Validation of A New Drift Flux Model in Rod Bundle Geometries

Experimental Study of Pressure Drop and Modelling of Interfacial Shear for Vertical Annular Flow

Hidalga, P.

Assessment of TRACE/PARCS Benchmark Against Leibstadt Plant Data During the Turbine Trip Test

Hille, D.

Developments on High Pressure Two Phase Flow Measurement Techniques

Hiltbrand, D.

RELAP5 BWR-4 Model Development and Validation for NPP Mühleberg (KKM)

Hinis, E. P.

Statistical Characteristics of Free Falling Water Film

Hinis, Evangelos

An Experimental Study on the Quench Front Velocity and Temperature during Rewetting of a Hot Vertical Rod

Hizoum, B.

Film-Droplet Split Correlation at the Onset of Annular-Mist Flow

Ho, A. L.

The Analysis of TRACE/FRAPTRAN in Ultimate Response Guideline for Lungmen ABWR Nuclear Power Plant

Hoang, N. H.

On the Application of Wall Boiling Models to Prediction of Subcooled Flow Boiling using EAGLE Code

Hochbaum, I.

Experimental Investigation of Critical Heat Flux for Zero and Natural Circulation Flow of Water in Three Rods Bundle near Atmospheric Pressure

Hochreiter, L. E.

Fundamental Experiments of Condensation Heat Transfer on Water Jets in the Presence of Noncondensable Gas

Hoehne, Thomas

Numerical Modeling of Horizontal Annular Flows using a Droplet Entrainment Model

Hoffmann, Mathias

First Results of the Simulation of the Fukushima-Daiichi Unit 3 Accident for an Assessment of the Applicability and Capability of the Code ATHLET-CD

Hogan, K. J.

Assessment of an Interfacial Shear Term for Adiabatic Dispersed Air-Water Two-Phase Flow with the Two-Fluid Model

Derivation of a Generic Multi-Field Two-Fluid Model

Hogan, Kevin J.

Experimental Characterization of Interchannel Mixing Through a Narrow Gap

Hohorst, J. K.

Revisiting ISP-13 with RELAP/SCDAPSIM/MOD3.5 using Core SCDAP Components

Hollands, T.

Simulation of LIVE-L4 with ATHLET-CD

Hollands, Thorsten

Numerical Analyses on the Safety Aspects of KASOLA Test Facility

Holler, Tadej

Validation of Two Turbulent Flame-Speed Closure Models for Slow and Fast Hydrogen Deflagration

Holmgren, Magnus

Validation of RELAP5/MOD3.3 Against a Load Step Transient at RINGHALS 4 NPP

Holmkvist, Carolin

Uncertainty Analysis for Lift-Forces on BWR Fuel Assemblies

Home, D.

Determination of In-Vessel Retention under Molten Corium Pool Attack

Honda, T.

Recent Findings on the Damaged Reactors and Containment Vessels of Fukushima Dai-ichi NPS

Hong, Jonggan

Experimental Evaluation on Sodium-to-Air Heat Exchanger Performance for PGSFR Design Code Validation

Hong, S. H.

FCI Test Results Under Conditions of the Partially Flooded Cavity and the Flooded Reactor in the TROI

Hong, S. W.

FCI Test Results Under Conditions of the Partially Flooded Cavity and the Flooded Reactor in the TROI

Hong, Soon-Joon

Heat Transfer Analysis of Horizontal U-Shaped Heat Exchanger Submerged in a Pool using MARS Code

Hong, Sungje

Thermal Hydraulic Analysis in Reactor Vessel Internals Considering Irradiation Heat

Hong, Xu

Analysis of the AP1000® Passive Containment Cooling System Air Flow Path Using Computational Fluid Dynamics

Hong, Z. J.

Flow Characterization within a Sphere-Packed Bed using PIV Measurement

Horvatovic, Ivan

Benchmark Analysis of EBR-II Protected Loss-of-Flow Transient

Hoxie, C. L.

Development, Validation and Assessment of the TRACE Thermal-Hydraulics Systems Code

Hoxie, Chris L.

Experimental Study of Laminar Mixed Convection in a Rod Bundle with Mixing Vane Spacer Grids

Hozer, Zoltan

Severe Accident Facilities for European Safety Targets,

Hózer, Zoltán

Extended Study of Coolability of VVER Bundle with Ballooned Region

Hristov, H. V.

Modeling of the Thermal Hydraulics of Very-High-Temperature Reactors with the System Code ATHLET

Investigation of Multidimensional Flow Mixing Phenomena in the Reactor Pressure Vessel with the System Code ATHLET

Hristov, Hristo V.

Numerical Analyses on the Safety Aspects of KASOLA Test Facility

Hu, Guojun

Uncertainty Quantification of TRACE Wall Heat Transfer Modeling in Subcooled Boiling Using BFBT Experiments

Hu, Lin-Wen

Three-Dimensional Thermal Hydraulic Analysis of a Transportable Fluoride-Salt-Cooled High-Temperature Reactor

Hu, R.

CFD Analysis of Upper Plenum Flow for a Sodium-Cooled Small Modular Reactor

CFD Simulation of Natural Convection Cooling After a Loss-of-Flow Transient

Hu, Rui

Pseudo 3-D Full-Core Conjugate Heat Transfer Modeling of Sodium Fast Reactors

A High-Order System Thermal-Hydraulics Model for Advanced Reactor Safety Analyses

Hu, Teng

CHF Experiment of RPV Lower Head with Real Surface Material for ERVC-IVR Strategy

Hu, W.

EBR-II Passive Safety Demonstration Tests Benchmark Analyses—Phase 2

Hu, Xiao

An Experimental Study of Air-Water Pool Entrainment in High Gas Flux Region

Huajian, Chang

Effects of Additives on CHF Behaviors for ERVC-IVR Strategy with FIRM Facility

Huang, Kai-Chun

Assessment of Station Blackout Mitigation Strategy Applying the Ultimate Response Guideline to MAANSHAN PWR

Huang, Qunying

Experimental Study on Natural Circulation and Gas Injection Enhanced Circulation in KYLIN-II Mixed Circulation Loop

Huang, Siyang

Theoretical Analysis of the Characteristics of Critical Heat Flux in Vertical Narrow Rectangular Channels Under Motion Conditions

Huang, Xi

Evaluation of Passive Containment Cooling with an Advanced Water Film Model in a Lumped-Parameter Code

Huang, Yanping

Numerical Simulations of Turbulent Mixing Factor in 2x2 Rod Bundles at Supercritical Pressures

Experimental and Numerical Investigation on Single Air Bubble Rising in Narrow Rectangular Channel

Development Heat Transfer Correlations for Supercritial CO2 in Natural Circulation Loop

Evaluation of RELAP5/MOD3.2 for ACP1000 Passive Residual Heat Removal System

Numerical Study on the Effects of Vane Angle and Dimple on the Thermal Hydraulic Performance of a PWR Fuel Assembly

Huang, Zheng

Investigation of Operational Charactistics of Passive Containment Cooling System for an Advanced PWR

Validation of the MEWA Code Against POMECO-HT Experiments and Coolability Analysis of Stratified Debris Beds

Melcor Analysis of Early Containment Venting Risk in a Severe Accident Scenario of Boiling Water Reactor

Huber, Hermann

Mesh Sensor for High Temperature High Pressure Applications

Huber, Klaus

Coupled Calculations of SAS4A/SASSYS-1 and STAR-CCM+ for the SHRT-45R Test in EBR-II

Huddar, L. R.

Development of the FHR Advanced Natural Circulation Analysis (FANCY) Code

Validation of Best Estimate Models for Fluoride-Salt-Cooled, High-Temperature Reactors Using Data from the Compact Integral Effects Test (CIET 1.0) Facility

Huddar, L.

Thermal Hydraulic Benchmarking Exercises to Support Fluoride-Salt-Cooled, High-Temperature Reactor (FHR) Licensing

Experimental Strategy for the Determination of Heat Transfer Coefficients in Pebble-Beds Cooled by Fluoride Salts

Hughes, J.

Thermal Hydraulic Benchmarking Exercises to Support Fluoride-Salt-Cooled, High-Temperature Reactor (FHR) Licensing

Huh, Jin

Thermal Hydraulic Analysis in Reactor Vessel Internals Considering Irradiation Heat

Hujala, Elina

CFD Modelling of Chugging Condensation Regime of BWR Suppression Pool Experiments

Hung, Nguyen T.

Flow Structure in Core Catcher Cooling Loop Through an Inclined-to-Vertical Elbow Bend

Hussain, Shadman

Surrogate Spacer Grid Design for Fluid-Structure Interactions Studies in Fuel Bundles

Hwang, Dae-Hyun

A Consideration of Experimental Uncertainties for Predicting CHF in Rod Bundles

Hwang, Inkoo

Experimental Evaluation on Sodium-to-Air Heat Exchanger Performance for PGSFR Design Code Validation

Hyvarinen, J.

Analysis of Reverse Flow in Low-Rise Inverted U-Tube Steam Generator of PWR Factel Facility

Hyvärinen, J.

Numerical Study of Direct Contact Condensation of Steam on Stable Interface in a BWR Supression Pool Test Facility

Hyvarinen, Juhani

Sources and Effects of Non-Condensable Gases in Reactor Coolant System of LWR

Study of Two-Phase Pipe Flow using the Axial Wire-Mesh Sensor

Hyvärinen, Juhani

CFD Modelling of Chugging Condensation Regime of BWR Suppression Pool Experiments

I

Ibarra, Lander

TRACG Analysis and Results of Phase 1 of the OECD/NEA Oskarshamn-2 BWR Stability Benchmark

Il Jang, Byeong

Assessment of the Best Estimate Thermal Design Method using THALES Subchannel Code

Reactor Core Analysis at Low Flow Condition Using THALES Subchannel Code

Il Kim, Sung

Thermal Hydraulic and Core Relocation Analysis on Fukushima Daiichi Unit 1

Effect of External Water Injection on Core Degradation and Fission Product Release in Fukushima Unit 1 Accident

Analysis of Fukushima Unit 2 Accident by Considering the Operating Condition of RCIC System and Torus Room Flooding

Il Yoon, Joo

Reactor Core Analysis at Low Flow Condition Using THALES Subchannel Code

Ilyas, M.

A Simple and Efficient Steam Generator Design for Integral SMRs

Im, Inyoung

Thermal Hydraulic Analysis in Reactor Vessel Internals Considering Irradiation Heat

Imbaratto, David

RoverD: Use of Test Data in GSI-191 Risk Assessment

Ireland, A.

Development, Validation and Assessment of the TRACE Thermal-Hydraulics Systems Code

Ishay, L.

Nuclear Reactor Containment Flows—Modelling of Stably Stratified Layer Erosion by a Turbulent Jet

Ishigaki, Masahiro

Thermal Hydraulic Safety Research at JAEA after the Fukushima Dai-Ichi Nuclear Power Station Accident

Ishii, M.

Turbulence-Induced Bubble Collision Force Model Development and Assessment for Adiabatic Dispersed Air-Water Two-Phase Flow with the Two-Fluid Model

Assessment of an Interfacial Shear Term for Adiabatic Dispersed Air-Water Two-Phase Flow with the Two-Fluid Model

Ishii, Mamoru

Experimental Stability Maps for a BWR-Type Small Modular Reactor

Experimental Study of Pressure Drop and Modelling of Interfacial Shear for Vertical Annular Flow

Ishikawa, Jun

Analysis for Progression of Accident at Fukushima Dai-ichi Nuclear Power Station with THALES2 Code

Issa, Raad

CFD and Experimental Analysis of Single Phase Buoyancy Driven Counter-Current Flow in a Pipe

Ito, Daisuke

Natural Convection Heat Transfer Characteristics of KUR Fuel Assembly during Loss of Coolant Accident

Ito, Kei

Verification of Interface-Tracking Method with Manufactured Solution

Ivanov, K. N.

Anisotropic Azimuthal Power and Temperature Distribution as a Driving Force for Hydrogen Redistribution

Ivanov, K.

Testing Coupled MCNP6/CTF on an Assembly Level Problem with an Acceleration Technique

Ivanov, Kostadin N.

Uncertainty and Sensitivity Analysis of COBRA-TF for the OECD LWR UAM Benchmark using DAKOTA

Analysis of Improved Fuel Rod Modeling in Coupled Thermal-Hydraulics/Neutronics Calculations

Iwasaki, Takashi

Analysis of Natural Circulation Tests in the Experimental Fast Reactor JOYO

Iyer, Kannan

Thermal Shrinkage Based Model for Predicting the Voids during Solidification of Lead

J

TRACG Analysis of Boiling Water Reactor Control Rod Drop Accident to Optimize Analysis Methodology

J. Komen, E. M.

High-Fidelity Numerical Reference Simulation of the Flow Through an Infinite Wire-Wrapped Assembly

Jabaay, Dan

Validation and Application of the 3D Neutron Transport MPACT within CASL VERA-CS

Jaeckel, B.

Analysis of the Fukushima Daiichi NPP Unit 3 with MELCOR_2.1

Jaeckel, Bernd

Melt-Concrete Interface Heat Transfer Models and Coolability Models: KWU PWR Analyses with MELCOR/CORCON and CORQUENCH

Jaeger, W.

On the Liquid Metal Heat Transfer in Annular Channels: Review, Proposal and Validation of Empirical Models

Jaeger, Wadim

Numerical Analyses on the Safety Aspects of KASOLA Test Facility

Jain, P.

Investigation of Plenum-to-Plenum Heat Transfer and Gas Dynamics under Natural Circulation in a Scaled Down Dual Channel Module Mimicking Prismatic VHTR Core with using CFD

Jain, Prashant K.

Advanced Multiphysics Thermal-Hydraulics Models for the High Flux Isotope Reactor

Jain, Varun

Validation of Two Turbulent Flame-Speed Closure Models for Slow and Fast Hydrogen Deflagration

Jana, Anirban

Large Eddy Simulation of Non-Isothermal Turbulent Flow Past a Circular Cylinder

Jang, Beomjun

Assessment of the Best Estimate Thermal Design Method using THALES Subchannel Code

Reactor Core Analysis at Low Flow Condition Using THALES Subchannel Code

Jang, Sunghyon

Numerical Investigation of Self-Wastage Phenomena in Steam Generator of Sodium-Cooled Fast Reactor

Jang, Yeong-Jun

Experimental Study of Condensation Heat Transfer in the Presence of Noncondensable Gas on the Vertical Tube

Jayaraju, S.T.

Heat and Dust Transport in a Pebble Bed HTR

Jeanningros, X.

Experimental and Numerical Activities in Support of the Design of ASTRID Sodium-Gas Heat Exchanger

Jeltsov, M.

Multiscale Analysis of Forced and Natural Convection Including Heat Transfer Phenomena in the TALL-3D Experimental Facility

Jeltsov, Marti

Development of TALL-3D Test Matrix for APROS Code Validation

Jentz, Ian

Modeling the Mechanical Integrity of Airfoil Printed Circuit Heat Exchangers

Jeon, Gyoodong

Effect of Oxide Layer Thickness on the Pool Boiling Critical Heat Flux of Pre-Oxidized RPV Material

Jeon, Seongsu

Heat Transfer Analysis of Horizontal U-Shaped Heat Exchanger Submerged in a Pool using MARS Code

Jeong, Jae Jun

Multi-Scale Thermal-Hydraulic Analysis of Safety Systems of Advanced PWRs using the CUPID Code

Jeong, Ji-Young

Experimental Evaluation on Sodium-to-Air Heat Exchanger Performance for PGSFR Design Code Validation

Flow Mixing Characteristics in Subchannels of a Wire-Wrapped 61-Pin Rod Assembly for a Sodium-Cooled Fast Reactor

Jeong, Uiju

Effects of Various Thin Film Coating Techniques on Pool Boiling Heat Transfer

Effect of Oxide Layer Thickness on the Pool Boiling Critical Heat Flux of Pre-Oxidized RPV Material

Jeong, Yeong Shin

Feasibility Study of Hybrid Heat Pipe with Control Rod as Passive In-Core Cooling System for Advanced Nuclear Power Plant

Experimental Investigation of Heat Transfer Phenomenon of Annular Heat Pipe for Passive In-Core Cooling System

Jeong, Yong Hoon

RANS Simulation of Turbulent Swept Flow over a Wire in a Channel for Core Thermal Hydraulic Design

Effect of Wettability and Two-Phase Flow Conditions on Flow Boiling CHF Enhancement for Slug Flow

Onset of Flow Instability Due to the Mergence of Facing Bubble Layers in a Vertical Narrow Rectangular Channel

CHF Measurement for Downward Facing SUS 304 and Carbon Steel Plates under Atmospheric and Pool Boiling Conditions

Jeong,, Yeong Shin

Heat Removal Capacity of Heat Pipe Designs for In-Core Passive Decay Heat Removal System

Jerng, Dong Wook

A Visual Study of Molten Metal Fuel Coolant Interactions Under an Initial Phase of SFR Severe Accident using Gallium Metal vs Water or R123

Jerng, Dong-Wook

Experimental Study of Condensation Heat Transfer in the Presence of Noncondensable Gas on the Vertical Tube

Jesse, C. J.

Fluid-Structure Interaction (FSI) Modeling of Thin Plates

Jesse, Casey J.

Experimental Investigation of Flat Plate Deflection Under Variable Velocity Parallel Flow

Jeun, Gyoodong

Effects of Various Thin Film Coating Techniques on Pool Boiling Heat Transfer

Ji, Shui

Turbulent Convection Experiment to Support IVR Strategy

Ji, Wei

Thermal Analysis of Pebble-Bed Reactors based on a Tightly Coupled Mechanical-Thermal Model

Jiang, Guangming

Natural Convective Heat Transfer from a Heated Slender Vertical Tube in a Cylindrical Tank

Jiang, Sheng-Yao

Effect of End Plate on the Flow Crossing a Yawed Circular Cylinder

Jiang, Shuying

Preliminary Steady State and Transient Analysis of a Molten Salt Based Reactor using RELAP/SCDAPSIM/MOD4.0

Jiminez, Gonzalo

Experimental Investigation and Flow Visualization of Steam Condensation in a Scaled IRWST-ADS Simulator

Jin, Ming

Unprotected Transient Analyses of Natural Circulation LBE-Cooled Accelerator Driven Sub-Critical System

JingGang, Li

Study on CHF Correlation for PWR at Low Pressure Conditions Based on Stepwise Regression Analysis

Jo, Hang Jin

Experimental Study of Boiling Initiation on a Smooth Heating Surface

Joffre, P. F.

Use of CFD to Predict Critical Heat Flux in Rod Bundles

Joffre, Paul F.

High Resolution Thermal Mixing at Westinghouse ODEN Loop

Johnson, D. K.

Fundamental Experiments of Condensation Heat Transfer on Water Jets in the Presence of Noncondensable Gas

Jones, John

Application and Validation of AREVA’s Advanced Thermal-Hydraulic Methods and Codes for PWR Level III Crud Risk Assessment

Jordan, K. A.

Comparison of Thermal Hydraulic Analysis Methods (Codes) for the University of Florida Training Reactor (UFTR)

Jordan, Thomas

Three Dimensional Scalable All-Speed CFD Code Gasflow-MPI: Applications to Turbulent Combustion of Premixed Hydrogen-Air Mixtures with Heat and Mass Transfer

Josey, Colin

Modeling of Rayleigh-Taylor Instability for Steam Direct Contact Condensation

Journeau, Christophe

Severe Accident Facilities for European Safety Targets,

Needs for Large Mass Phototype Corium Experiments: The PLINIUS-2 Platform

Ju, Peng

Experimental Study of Pressure Drop and Modelling of Interfacial Shear for Vertical Annular Flow

Judd, Jerry

TRACE/SIMULATE-3K Analysis of the NEA/OECD Oskarshamn-2 Stability Benchmark

Jung, Satbyoul

Effects of Surface Orientation on Wall Heat Flux Partitioning During Nucleate Pool Boiling of Saturated Water at Atmospheric Pressure

Jung, Hwa-Young

Numerical Studies of O₂ Leak Modeling in Sodium-CO₂ Heat Exchanger in the SFR Coupled with the S-CO₂ Brayton Cycle

Jung, Jaehoon

VESTA Test Facility for Severe Accident Researches at KAERI

Jung, Min-Hwan

Experimental Evaluation on Sodium-to-Air Heat Exchanger Performance for PGSFR Design Code Validation

K

Käestner, W.

System Analysis and Isothermal Separate Effect Experiments of the Accident Behavior in PWR Spent Fuel Storage Pools

Kaestner, Wolfgang

Investigation of the Release of Zinc in the Reactor Sump and the Behavior of Dissolved Zinc at Hotspots in the Reactor Core after a Loss of Coolant Accident

Kalanich, Donald

Integrated Assessment of Thermal Hydraulic Processes in W7-X Fusion Experimental Facility

Kaliatka, A.

Kaliatka, T.

Integrated Assessment of Thermal Hydraulic Processes in W7-X Fusion Experimental Facility

Kam, Dong Hoon

CHF Measurement for Downward Facing SUS 304 and Carbon Steel Plates under Atmospheric and Pool Boiling Conditions

Kamide, H.

Proposal of Benchmark Problem of Thermal Striping Phenomena in Planar Triple Parallel Jets Tests for Fundamental Code Validation in Sodium-Cooled Fast Reactor Development

Progress of Thermal Hydraulic Evaluation Methods and Experimental Studies on a Sodium-Cooled Fast Reactor and Its Safety

Kanai, Taizo

Boiled-Up Level and Boiling Two-Phase Flow Dynamics in 5x5 Heated Rod Bundle during Boil-Off Process under Atmospheric Pressure Conditions

Kang, Dong Gu

Reevaluation of Station Blackout Risk of OPR-1000 Nuclear Power Plant Applying Combined Approach of Deterministic and Probabilistic Method

Kang, Jun Young

Roles of Boiling Surface Characterized by Micro-Structures on Boiling Heat Transfer and Critical Heat Flux

Kang, K. H.

Experimental Investigation on Thermal-Hydraulics Behavior during a Station Blackout Transient in a Pressurized Water Reactor

Kang, Kyoungmin

Phenomenological Modeling Approach to Anisotropic Ablation in Molten Core Concrete Interactions

Kang, Shin Kyu

CFD Methodologies for a PWR Fuel Rod Assembly

Kannan, Umasankari

Design of High Power Density Annular Fuel Rod Core for Advanced Heavy Water Reactor

Kansal, Anuj Kumar

CFD and Experimental Analysis of Single Phase Buoyancy Driven Counter-Current Flow in a Pipe

Kanzleiter, Teja

Passive Autocatalytic Recombiners (PAR) Induced Ignition and the Resulting Hydrogen Deflagration Behaviour in LWR Containments

Kao, M. M.

Investigation of Plenum-to-Plenum Heat Transfer and Gas Dynamics under Natural Circulation in a Scaled Down Dual Channel Module Mimicking Prismatic VHTR Core with using CFD

Kappes, Matthew J.

The Effect of Electric Potential on Fibrous Debris Bypass Through a Containment Sump Strainer

Kapulla, R.

Synthesis of the OECD/NEA-PSI CFD Benchmark Exercise

Combined Effects of Cooler and Spray Activation on the Hydrogen Distribution in the Presence of a Jet Flow

Kapulla, Ralf

Erosion of a Confined Stratified Layer by a Vertical Jet-Detailed Assessment of a CFD Approach Against the OECD/NEA PSI Benchmark

Parametric Study on Density Stratification Erosion Caused by a Horizontal Steam Jet Interacting with a Vertical Plate Obstruction

Performance of Hydrogen Mitigation Systems for a Scaled Accident Scenario: Overview of Ercosam Project Experimental Results for the Panda Facility

Karanki, D. R.

Ranking of Uncertain Parameters for Dynamic Event Tree Analysis: A Case Study based on a Station Blackout Scenario

Karbojian, K.

Experimental Investigation of Debris Bed Agglomeration and Particle Size Distribution using WO3-ZRO2 Melt

Karoutas, Z. E.

Use of CFD to Predict Critical Heat Flux in Rod Bundles

Karoutas, Zeses

Westinghouse CFD Modeling and Results for EPRI NESTOR CFD Round Robin Exercise of PWR Rod Bundle Testing

Kassab, S.

Measurements of the Vertical Distribution of the Void Fraction using X-ray Attenuation for Different Flow Regimes in a Horizontal Pipe

Katata, Genki

Source Term Estimation for the Fukushima Daiichi Nuclear Power Station Accident by Combined Analysis of Environmental Monitoring and Plant Data Through Atmospheric Dispersion Simulation

Kauppinen, O-P

Analysis of Reverse Flow in Low-Rise Inverted U-Tube Steam Generator of PWR Factel Facility

Kawaji, Masahiro

Role of Radiation Heat Transfer in Cooling of a Scaled Model of a Prismatic Graphite Core in a VHTR

Study of Abnormal Heat Transfer during Forced and Natural Convection Scenarios in a Prismatic Core of a VHTR: Numerical and Experimental Results

Kawara, Zensaku

Experimental Study of Annular Two-Phase Flow on Rod-Bundle Geometry with Spacer

Subcooled Boiling-Induced Vibration of a Single Heater Rod Confined with Metallic Walls

Kazimi, M. S.

Compact Steam Generator for Nuclear Application

Kee, Ernie

RoverD: Use of Test Data in GSI-191 Risk Assessment

Viscous Inertial Shear-Transition-Adaptive (VISTA) Porous Media Head-Loss Formulation

Keheley, T.

A Review of AREVA’s Experimental Validation of State-of-the-Art Single-Phase CFD Methods with Application to PWR Fuel Analysis and Design

Keheley, Thomas

Validation of AREVA’s Best Practices in the Round Robin CFD Benchmark

Keij, T. L. J.

Hydrogen Risk Assessment—CFD Model Validation and Reactor Scale Application

Keijers, S.

CFD Benchmark for a Heavy Liquid Metal Fuel Assembly

Pre-Test Computational Fluid Dynamics and System Thermal Hydraulics Calculations of The E-SCAPE Scaled LBE Pool Facility

Keijers, Steven

CFD Simulations to Determine the Effects of Deformations on Liquid Metal Cooled Wire Wrapped Fuel Assemblies

Kelly, J. M.

Liquid-Side Interfacial Heat Transfer in Inverted Annular Film Boiling

Kelly, J.

Development, Validation and Assessment of the TRACE Thermal-Hydraulics Systems Code

Kelm, S.

Validation and Application of the REKO-DIREKT Code for the Simulation of Passive Auto-Catalytic Recombiners (PARs) Operational Behavior

Kelm, Stephan

Erosion of a Confined Stratified Layer by a Vertical Jet-Detailed Assessment of a CFD Approach Against the OECD/NEA PSI Benchmark

Towards a Coupled Simulation of Thermal Hydraulics and Neutronics in a Simplified PWR with a 3x3 Pin Assembly

Kendrick, Brian

A Control Theory Approach to Adaptive Stepsize Selection for Coupled CFD and CRUD Chemistry Simulations

Kendrick, J. C.

Design, Fabrication and Startup Testing in the Compact Integral Effects Test Facility in Support of Fluoride-Salt-Cooled, High-Temperature Reactor Technology

Kendrick, J.

Thermal Hydraulic Benchmarking Exercises to Support Fluoride-Salt-Cooled, High-Temperature Reactor (FHR) Licensing

Kennedy, Graham

Experimental Investigation of the Pressure Loss Characteristics of the Full-Scale MYRRHA Fuel Bundle in the COMPLOT LBE Facility

Numerical Analysis of MYRRHA Control Rod System Dynamics

Kennedy, J. C.

Fluid-Structure Interaction (FSI) Modeling of Thin Plates

Kennedy, John C.

Experimental Investigation of Flat Plate Deflection Under Variable Velocity Parallel Flow

Khan, A.

A Simple and Efficient Steam Generator Design for Integral SMRs

Khan, Abdul R.

Heat Transfer from Finned Surface in Downward-Facing Subcooled Flow Boiling

Khan, J. A.

Experimental and Computational Study of Ribbed Cladding for PWR Rod Bundles Heat Transfer Enhancement

Kickhofel, John

Mesh Sensor for High Temperature High Pressure Applications

Kim, B. J.

MARS Code Evaluation of Reflood Phenomena in a Partially-Deformed 5x5 Rod Bundle

Kim, B. J.

Rayleigh-Taylor Instability of Viscous Flow with Heat and Mass Transfer

Kim, Byoung Jae

Kim, Byung Jae

Modifications of Critical Heat Flux Models on Horizontal Surfaces in Pool Boiling Using Interfacial Instabilities of Viscous Potential Flows

Kim, Byung-Jae

Effect of a Blockage Length on the Coolability during Reflood in a 2x2 Rod Bundle with a 90% Partially Blocked Region

Kim, Chang-Hyun

Operational Experience of Ceramic Honeycomb Passive Autocatalytic Recombiner as a Hydrogen Mitigation System

Kim, Dehee

The Present State-of-the-Art Thermal Striping Studies for Sodium Cooled Fast Reactors

Kim, Do Yun

Optimization Methodology for Large Scale Fin Geometry on the Steel Containment of a Public Acceptable Simple SMR (PASS)

Kim, Donjoo

Modeling of Interfacial Momentum Exchange for Wall-Bounded Bubbly Flows

Kim, E. S.

Numerical Simulation of Supercritical Pressure Fluids with Variable Turbulent Prandtl Number and Modified Damping Function (1/2)

Kim, Eung Soo

Computational Fluid Dynamics Modeling and Validation of Swirling Flow in a Pipe with Classic Twisted Tape

Kim, Eunkee

Thermal Hydraulic Analysis in Reactor Vessel Internals Considering Irradiation Heat

Kim, H. Y.

Detailed Analysis of Geometry Effect on Two Phase Natural Circulation Flow under IVR-ERVC

Kim, Ho Sik

Optimization Methodology for Large Scale Fin Geometry on the Steel Containment of a Public Acceptable Simple SMR (PASS)

Experimental Study and Validation of MARS Code for CCFL in Passive Emergency Core Cooling System (PECCS) of Public Acceptable Simple SMR (PASS) System

Kim, Hong Ju

Assessment of the Best Estimate Thermal Design Method using THALES Subchannel Code

Kim, Hwan Yeol

VESTA Test Facility for Severe Accident Researches at KAERI

Kim, Hyeon Tae

Printed Circuit Heat Exchanger Design, Analysis and Experiment

Kim, Hyoung T.

Validation Test Plan of a CANDU-6 Moderator Tank Scaled-Down Test Facility

Kim, Hyun Soo

Suppression of Chemical Reactivity of Sodium-Titanium Nano Fluid in Sodium-Water Vapor Reaction

Kim, Hyungdae

Effects of Surface Orientation on Wall Heat Flux Partitioning During Nucleate Pool Boiling of Saturated Water at Atmospheric Pressure

Kim, Hyungmo

Flow Mixing Characteristics in Subchannels of a Wire-Wrapped 61-Pin Rod Assembly for a Sodium-Cooled Fast Reactor

Measurements of the Flow Distribution in Subchannels of a Wire Wrapped 37-Pin Rod Assembly

Kim, In Guk

Feasibility Study of Hybrid Heat Pipe with Control Rod as Passive In-Core Cooling System for Advanced Nuclear Power Plant

Experimental Investigation of Heat Transfer Phenomenon of Annular Heat Pipe for Passive In-Core Cooling System

Heat Removal Capacity of Heat Pipe Designs for In-Core Passive Decay Heat Removal System

Kim, J. R.

Experimental Investigation on Thermal-Hydraulics Behavior during a Station Blackout Transient in a Pressurized Water Reactor

Kim, J.

MARS Code Evaluation of Reflood Phenomena in a Partially-Deformed 5x5 Rod Bundle

Kim, Jong-Man

Experimental Evaluation on Sodium-to-Air Heat Exchanger Performance for PGSFR Design Code Validation

Kim, Jongrok

Experimental Study for Effects of Ballooning and Power Peak on a Coolability of Fuel Rod Bundle

Kim, Jungho

A Study of Heat Transfer Mechanisms and Flow Characteristics for Single Rising Taylor Bubbles

Kim, Jungwoo

Modeling of Interfacial Momentum Exchange for Wall-Bounded Bubbly Flows

Kim, K.

MARS Code Evaluation of Reflood Phenomena in a Partially-Deformed 5x5 Rod Bundle

Kim, Kang Seog

Validation and Application of the 3D Neutron Transport MPACT within CASL VERA-CS

Kim, Kihwan

Effect of a Blockage Length on the Coolability during Reflood in a 2x2 Rod Bundle with a 90% Partially Blocked Region

Kim, Kyung Doo

Rayleigh-Taylor Instability of Viscous Flow with Heat and Mass Transfer

Modifications of Critical Heat Flux Models on Horizontal Surfaces in Pool Boiling Using Interfacial Instabilities of Viscous Potential Flows

Feasibility Study of Hybrid Heat Pipe with Control Rod as Passive In-Core Cooling System for Advanced Nuclear Power Plant

Kim, Kyung Mo

Experimental Investigation of Heat Transfer Phenomenon of Annular Heat Pipe for Passive In-Core Cooling System

Heat Removal Capacity of Heat Pipe Designs for In-Core Passive Decay Heat Removal System

Quenching Performance in Nanofluids and Nanoparticles-Deposited Surfaces

Kim, M. H.

Numerical Simulation of Supercritical Pressure Fluids with Variable Turbulent Prandtl Number and Modified Damping Function (1/2)

Kim, Min-Gil

Comparison of MARS-KS to COBRA-TF for Models and Correlations in Pre-CHF Regime

Kim, Moo Hwan

Roles of Boiling Surface Characterized by Micro-Structures on Boiling Heat Transfer and Critical Heat Flux

Experimental Study of Boiling Initiation on a Smooth Heating Surface

Suppression of Chemical Reactivity of Sodium-Titanium Nano Fluid in Sodium-Water Vapor Reaction

Kim, Seok

Condensation Heat Transfer Coefficient Correlation based on Slip Ratio Model in a Horizontal Heat Exchanger

Kim, Seol Ha

Roles of Boiling Surface Characterized by Micro-Structures on Boiling Heat Transfer and Critical Heat Flux

Kim, Seong Gu

Printed Circuit Heat Exchanger Design, Analysis and Experiment

Kim, Seong-Jin

A Consideration of Experimental Uncertainties for Predicting CHF in Rod Bundles

Kim, Seungjin

Characterization of Horizontal Air-Water Two-Phase Flow

Inlet Effects on Vertical-Downward Air-Water Two-Phase Flow

Kim, Seyun

Development of a Coupled Code System Based on SPACE Safety Analysis Code and RAST-K Three-Dimensional Neutronics Code

Kim, Sin

Experimental Study of Condensation Heat Transfer in the Presence of Noncondensable Gas on the Vertical Tube

Kim, Soo Jae

Suppression of Chemical Reactivity of Sodium-Titanium Nano Fluid in Sodium-Water Vapor Reaction

Kim, Sung Joong

Effects of Various Thin Film Coating Techniques on Pool Boiling Heat Transfer

Effect of Oxide Layer Thickness on the Pool Boiling Critical Heat Flux of Pre-Oxidized RPV Material

Kim, Tae Woon

Thermal Hydraulic and Core Relocation Analysis on Fukushima Daiichi Unit 1

Effect of External Water Injection on Core Degradation and Fission Product Release in Fukushima Unit 1 Accident

Kim, Tae-Joon

Experimental Evaluation on Sodium-to-Air Heat Exchanger Performance for PGSFR Design Code Validation

Kim, Taewan

Scaling Analysis for DVI Line Break Accident of APR1400 based on ATLAS Experiment

Kim, Tongbeum

Validation Test Plan of a CANDU-6 Moderator Tank Scaled-Down Test Facility

Kim, Yo-Han

Development of a Coupled Code System Based on SPACE Safety Analysis Code and RAST-K Three-Dimensional Neutronics Code

Kim, Yongdeog

Evaluation of Thales Subchannel Code Behavior for Loss of Flow and RCP ROTOR Seizure Scenarios

Kimber, Mark L.

An Experimental Investigation of Thermal Loading on a Plate from Parallel Triple Jet

Large Eddy Simulation of Non-Isothermal Turbulent Flow Past a Circular Cylinder

Kimber, Mark

Design of a Unit Cell Facility for Studies of the Prismatic VHTR Lower Plenum

Kinoshita, Ikuo

Development and Validation of A New Drift Flux Model in Rod Bundle Geometries

Kiselova, Monika

Severe Accident Facilities for European Safety Targets,

Kiyofumi, Moriyama

Roles of Boiling Surface Characterized by Micro-Structures on Boiling Heat Transfer and Critical Heat Flux

Experimental Study of Boiling Initiation on a Smooth Heating Surface

Klauck, M.

Validation and Application of the REKO-DIREKT Code for the Simulation of Passive Auto-Catalytic Recombiners (PARs) Operational Behavior

Klebanov, L.

Evaluation of Passive Containment Cooling with an Advanced Water Film Model in a Lumped-Parameter Code

Klein-Hessling, Walter

Klemm, L.

Developments on High Pressure Two Phase Flow Measurement Techniques

Kljenak, I.

Three-Dimensional Simulation of Flooding Waves in a Vertical Pipe

Kljenak, Ivo

Hydrogen Combustion Benchmark Using Experiment in Double-Compartment Experimental Vessel

Kluegel, Jens-Uwe

Melt-Concrete Interface Heat Transfer Models and Coolability Models: KWU PWR Analyses with MELCOR/CORCON and CORQUENCH

Klügel, J.-U.

Simulation of Hydrogen Distribution in the Containment during a Severe Accident with Fast Hydrogen-Steam Release

Ko, Heeran

Scaling Analysis for DVI Line Break Accident of APR1400 based on ATLAS Experiment

Ko, Yung Joo

Flow Mixing Characteristics in Subchannels of a Wire-Wrapped 61-Pin Rod Assembly for a Sodium-Cooled Fast Reactor

Kobalz, Jeffrey

Development and Qualification of an Aerosol Generator for Investigations Under Thermal-Hydraulic Severe Accident Boundary Conditions

Kobayashi, J.

Proposal of Benchmark Problem of Thermal Striping Phenomena in Planar Triple Parallel Jets Tests for Fundamental Code Validation in Sodium-Cooled Fast Reactor Development

Koch, Marco K.

First Results of the Simulation of the Fukushima-Daiichi Unit 3 Accident for an Assessment of the Applicability and Capability of the Code ATHLET-CD

Preliminary Results of a Comparative Assessment of ATHLET-CD and MELCOR by Simulating the Experiment PHEBUS FPT1

ASTEC Simulation of a SBO with Re-Flood in a German KONVOI NPP

Koizumi, Yasuo

Study on Flow Boiling Heat Transfer in Horizontal-Rectangular-Narrow-Flat Flow Channel

Kojima, Yoshihiro

A Study on Transient Heat Transfer of the EU-ABWR External Core Catcher using the Phase-Change Effective Convectivity Model

Koloszar, Lilla

MyrrhaFoam: A CFD Model for the Study of the Thermal Hydraulic Behavior of MYRRHA

Komen, E. M. J.

Calibration and Optimization of Pressurized Thermal Shock for Benchmarking Direct Numerical Simulation

Hydrogen Risk Assessment—CFD Model Validation and Reactor Scale Application

Komen, Ed M. J.

Validation of Two Turbulent Flame-Speed Closure Models for Slow and Fast Hydrogen Deflagration

Komiyama, D.

Qualification of CHF Test Facility at Stern Laboratories using Mitsubishi PWR Fuel

Končar, B.

Three-Dimensional Simulation of Flooding Waves in a Vertical Pipe

Uncertainty Evaluation of CFD Simulation using Optimal Statistical Estimator

Kondo, Masahiro

Investigation of MCCI Phenomena with Multi-Physics MPS Simulation

Kong, Ran

Characterization of Horizontal Air-Water Two-Phase Flow

Konovalenko, A.

Effect of Particle Spreading on Coolability of Ex-Vessel Debris Bed

Experiments and Modeling of Particulate Debris Spreading in a Pool

Konovalenko, Alexander

Experimental Investigation of Debris Bed Agglomeration and Particle Size Distribution using WO3-ZRO2 Melt

Kööp, K.

Multiscale Analysis of Forced and Natural Convection Including Heat Transfer Phenomena in the TALL-3D Experimental Facility

Kööp, Kaspar

Development of TALL-3D Test Matrix for APROS Code Validation

Korysko, Pierre

Surrogate Spacer Grid Design for Fluid-Structure Interactions Studies in Fuel Bundles

Koshizuka, Seiichi

New AESJ Thermo-Hydraulics Roadmap for LWR Safety Improvement and Development after Fukushima-Daiichi Accident

Košmrlj, S.

Uncertainty Evaluation of CFD Simulation using Optimal Statistical Estimator

Kouchunas, Brendan

Validation and Application of the 3D Neutron Transport MPACT within CASL VERA-CS

Kouhia, V.

Analysis of Reverse Flow in Low-Rise Inverted U-Tube Steam Generator of PWR Factel Facility

Kovtonyuk, Andriy

Development and Assessment of a Method for Evaluating Uncertainty of Input Parameters

Kozlowski, Tomasz

Recommendations of Two-Phase Critical Non-Flashing Flow Mixture Calculations in One-Dimensional System Code RELAP5

TRACE/SIMULATE-3K Analysis of the NEA/OECD Oskarshamn-2 Stability Benchmark

Uncertainty Quantification of TRACE Wall Heat Transfer Modeling in Subcooled Boiling Using BFBT Experiments

Kral, P.

Improvement of RELAP5 Models for Condensation of Steam and Steam-Gas Mixture in Horizontal and Inclined Tubes

Kral, Pavel

Sources and Effects of Non-Condensable Gases in Reactor Coolant System of LWR

Kraus, A.

CFD Analysis of Upper Plenum Flow for a Sodium-Cooled Small Modular Reactor

CFD Simulation of Natural Convection Cooling After a Loss-of-Flow Transient

Erosion of a Large-Scale Gaseous Stratified Layer by a Turbulent Round Jet S—Simulations with URANS and LES Approaches

Krepper, E.

Status and Challenges of CFD-Modelling for Poly-Disperse Bubbly Flows

Analysis and Applications of a Generalized Multi-Field Two Fluid Approach for Plunging Jet Configuration

Krepper, Eckhard

Application of CFD Towards the Thermo-Hydraulic Analysis of Spent Fuel Pool Accidents

Kretzschmar, Frank

Live Experiments on the In-Vessel Melt Pool Behaviour with Different External Cooling Conditions and the Simulation Results with a Coupled MELCOR-PECM Approach

Kristo, Paul J.

An Experimental Investigation of Thermal Loading on a Plate from Parallel Triple Jet

Kristo, Paul

Design of a Unit Cell Facility for Studies of the Prismatic VHTR Lower Plenum

Krohn, Benedikt

Turbulent Gas Mixing in Strong Density Stratified Shear and Non-Shear Flows

Kruessenberg, A.- K.

Study of Safety and International Development of Small Modular Reactors (SMR)

Krupa, Bjoern Alexander

Development and Qualification of an Aerosol Generator for Investigations Under Thermal-Hydraulic Severe Accident Boundary Conditions

Kryk, Holger

Investigation of the Release of Zinc in the Reactor Sump and the Behavior of Dissolved Zinc at Hotspots in the Reactor Core after a Loss of Coolant Accident

Ku, Yu-Ting

Developments and Applications of TRACE/CFD Model of Maanshan PWR Pressure Vessel

Kubisova, Lubica

Hydrogen Combustion Benchmark Using Experiment in Double-Compartment Experimental Vessel

Kucukboyaci, Vefa

COBRA-TF Evaluation and Application for PWR Steamline Break DNB Analysis

Kudinov, P.

Multiscale Analysis of Forced and Natural Convection Including Heat Transfer Phenomena in the TALL-3D Experimental Facility

Development of TEXAS-V Code Surrogate Model for Assessment of Steam Explosion Impact in Nordic BWR

Effect of Particle Spreading on Coolability of Ex-Vessel Debris Bed

Experiments and Modeling of Particulate Debris Spreading in a Pool

Kudinov, Paval

Experimental Investigation of Debris Bed Agglomeration and Particle Size Distribution using WO3-ZRO2 Melt

Kudinov, Pavel

Development of TALL-3D Test Matrix for APROS Code Validation

A Study on Transient Heat Transfer of the EU-ABWR External Core Catcher using the Phase-Change Effective Convectivity Model

Kulenovic, R.

Experimental Investigations on the Coolability of Debris Beds under Variation of Inflow Conditions

Kulenovic, Rudi

Numerical Analysis of Influence of Branch Flow on Thermal Mixing in a T-Junction Piping System

Kulkarni, P. P.

Quenching of a Heated Rod: Physical Phenomena and Heat Transfer

Kulkarni, Parimal P.

Modeling of Ex-Vessel Melt Pool Coolability Under Bottom Flooding with Decay Heat Simulation

Kunugi, Tomoaki

Experimental Study of Annular Two-Phase Flow on Rod-Bundle Geometry with Spacer

Subcooled Boiling-Induced Vibration of a Single Heater Rod Confined with Metallic Walls

Verification of Interface-Tracking Method with Manufactured Solution

Improvement of Wall Surface Temperature Evaluation Procedure During Subcooled Nucleate Boiling in Non-Empirical Boiling and Condensation Model

Kurihara, A.

Numerical Investigation of Self-Wastage Phenomena in Steam Generator of Sodium-Cooled Fast Reactor

Kurul, Necdet

Reactor Core Isolation Cooling TRACG Model

Kuznetsov, Mike

Three Dimensional Scalable All-Speed CFD Code Gasflow-MPI: Applications to Turbulent Combustion of Premixed Hydrogen-Air Mixtures with Heat and Mass Transfer

Kuznetsova, M. E.

SOCRAT-BN Simulation of Siena Loss-of-Flow Experiments

Kwiatkowski, T.

Calibration of High Fidelity Bare Rod Bundle Simulations for Various Prandtl Fluids

Kwon, Hyuk

A Consideration of Experimental Uncertainties for Predicting CHF in Rod Bundles

Kyrki-Rajamäki, Riitta

CFD Modelling of Chugging Condensation Regime of BWR Suppression Pool Experiments

L

Laborde, L.

Capability of ASTEC V2.1 to Simulate a Severe Accident in a Nuclear Power Plant —Application to a TMI-2-Like Accident Scenario

LaBrier, Daniel P.

Overview of the Flume Integral Effects and Separate Effects Testing and Analysis (FIESTA) Facility for Investigating Containment Debris Transport and Sump Strainer Head Loss

Laffi, Lorenzo

Experimental Fuel Pin Bundle Characterization in the NACIE-UP HLM Facility

LaFleur, Brandon

CFD Analyses of Main Flow Penetration Depth in Isolated Branch Lines

Lafountain, Sam

Reactor Core Isolation Cooling TRACG Model

Lafountain, Samuel

DNS of Turbulent Convective Flow Boiling in a Channel

Lakehal, D.

Near-Wall Turbulence-Bubbles Interactions in a Channel Flow at Reτ=400: A DNS/LES investigation

CATHARE-TransAT Coupling for the Prediction of Boron Dilution in the Rocom Test Facility

Nuclear Safety and Thermal Hydraulics: Personal Thoughts and Some Recent Progress

Lance, Blake W.

Transient Convection from Forced to Natural with Flow Reversal for CFD Validation

Landfried, D. Tyler

An Experimental Investigation of Thermal Loading on a Plate from Parallel Triple Jet

Design of a Unit Cell Facility for Studies of the Prismatic VHTR Lower Plenum

Lane, J. W.

Development of a Multiple Liquid Component Capability in GOTHIC to Better Support Boric Acid, Radiological, and GSI-191 Analyses

Momentum Convection within the Staggered Grid Formulation

Lane, Jeffrey W.

Large Open Region Interfacial Drag Modeling Package in COBRA-IE

Lang, Minggang

Analysis on Anticipated Transient Without SCRAMS (ATWS) Accidents of the HTR-10GT

Lang, Xuemei

Comparison Analysis of CHF Parametric Trends in Vertical Tube and 5x5 Bundle

Research on Critical Heat Flux of PWR Fuel Assembly in NPIC

Langrock, Gert

Severe Accident Facilities for European Safety Targets,

Lappalainen, Jari

Development of TALL-3D Test Matrix for APROS Code Validation

LaPresti, Michael Anthony

A Dynamic Model of Hydrostatic Reactor Coolant Pump Seals for RELAP5/MOD3.3

Lassauce, Arelia

Experimental and Theoretical Study of Iron Concentration on Clogging Phenomenon in Secondary Circuit of Pressurized Nuclear Power Plant

Laurien, E.

Experimental Investigations on the Coolability of Debris Beds under Variation of Inflow Conditions

Unsteady Void Measurements Within Debris Beds using High Speed X-Ray Tomography

Laurien, Eckart

Numerical Analysis of Influence of Branch Flow on Thermal Mixing in a T-Junction Piping System

Laurien, Eckhart

Mesh Sensor for High Temperature High Pressure Applications

LaVastre, Romain

Numerical Analysis of Core Thermal-Hydraulic for Sodium-Cooled Fast Reactors

Laviéville, J.

Verification, Validation and Application of Neptune _ CFD to Two-Phase Pressurized Thermal Shocks

Lavieville, J.

Combined Evaluation of Bubble Dynamics, Polydispersion Model and Turbulence Modeling for Adiabatic Two-Phase Flows

Assessment of RANS at Low PRANDTL Number and Simulation of Sodium Boiling Flows with a CMFD Code

Lavieville, Jerome

Progress on Computation of Boiling Flow in Fuel Assemblies with NEPTUNE_CFD

Laviéville, Jérôme

Numerical Investigations of a Spent Fuel Storage Pool in Abnormal Conditions

Lavieville, Jerome

A Generalized Turbulent Dispersion Model for Bubbly Flow Numerical Simulation in NEPTUNE_CFD

Le Bars, Michael

On the Use of Hybrid RANS/LES Methods for the Simulation of the Erosion of a Stratified Layer by a Turbulent Buoyant Jet

Le Belguet, A.

Simulation of FARO L-28 and L-31 Tests to Assess Molten Jet Fragmentation Modeling in MAAP

Le Corre, J.-M.

A CFD Approach to Spacer Grid Optimization for Improved Dryout Performance in BWR Fuel Bundle

Validation and Cross-Verification of Three Mechanistic Codes for Annular Two-Phase Flow Simulation and Dryout Prediction

Le Corre, Jean-Marie

Detailed Measurements of Local Parameters in Annular Two-Phase Flow in Fuel Bundle under BWR Operating Conditions

A Validation of Westinghouse Mechanistic and Empirical Dryout Prediction Methods Under Realistic BWR Transient Conditions

Evaluation of 1-D Void and Pressure Drop Models over a Wide Range of Fuel Bundle Geometries and Operating Conditions

Tomographic Reconstructions and Predictions of Radial Void Distribution in BWR Fuel Bundle with Part-Length Rods

High Resolution Thermal Mixing at Westinghouse ODEN Loop

Le Coupanec, E.

Software Quality Assurance and V&V Procedure During the Development Stages of EdF CFD Tool Code_SATURNE: Focus on Verification Tests

Le Moigne, Y.

A CFD Approach to Spacer Grid Optimization for Improved Dryout Performance in BWR Fuel Bundle

Lee, Dan

Boiled-Up Pool Heat Transfer for a Horizontal Tube Bundle

Lee, Dong-Hyuk

Development of a Coupled Code System Based on SPACE Safety Analysis Code and RAST-K Three-Dimensional Neutronics Code

Lee, Dong-Won

Flow Mixing Characteristics in Subchannels of a Wire-Wrapped 61-Pin Rod Assembly for a Sodium-Cooled Fast Reactor

Measurements of the Flow Distribution in Subchannels of a Wire Wrapped 37-Pin Rod Assembly

Lee, Eunki

Development of a Coupled Code System Based on SPACE Safety Analysis Code and RAST-K Three-Dimensional Neutronics Code

Lee, Hyeong-Yeon

Flow Mixing Characteristics in Subchannels of a Wire-Wrapped 61-Pin Rod Assembly for a Sodium-Cooled Fast Reactor

Measurements of the Flow Distribution in Subchannels of a Wire Wrapped 37-Pin Rod Assembly

Lee, J. H.

Comparison of MARS-KS to COBRA-TF for Models and Correlations in Pre-CHF Regime

Lee, Jeong Ik

Numerical Studies of O₂ Leak Modeling in Sodium-CO₂ Heat Exchanger in the SFR Coupled with the S-CO₂ Brayton Cycle

Printed Circuit Heat Exchanger Design, Analysis and Experiment

Experimental Study on the CO₂ to Water Heat Exchanger Performance Near the CO₂ Critical Point

Lee, Jewhan

Experimental Evaluation on Sodium-to-Air Heat Exchanger Performance for PGSFR Design Code Validation

Lee, Jin-Der

The Impact of Vertical Acceleration on the Nonlinear Behaviors of Multiple Parallel Boiling Channels

Lee, John C.

Preliminary Design of the I²S-LWR Containment System

Lee, Jong Hyuk

Modifications of Critical Heat Flux Models on Horizontal Surfaces in Pool Boiling Using Interfacial Instabilities of Viscous Potential Flows

Lee, Juhyung

Onset of Flow Instability Due to the Mergence of Facing Bubble Layers in a Vertical Narrow Rectangular Channel

Lee, Jun Ho

Modeling of Interfacial Momentum Exchange for Wall-Bounded Bubbly Flows

Lee, Naugab E.

A Dynamic Model of Hydrostatic Reactor Coolant Pump Seals for RELAP5/MOD3.3

Lee, S. W.

Experimental Observations of Boric Acid Precipitation Scenarios

Lee, Saya

The Effect of Electric Potential on Fibrous Debris Bypass Through a Containment Sump Strainer

Lee, Seung Jun

Experimental Evaluation of Local Bubble Parameters of Subcooled Boiling Flow in a Pressurized Vertical Annulus Channel

Lee, Seung Tae

Condensation Heat Transfer Coefficient Correlation based on Slip Ratio Model in a Horizontal Heat Exchanger

Lee, Seungtae

Visualization of Turbulent Thermal Mixing Structures in a Horizontal Stratified Condensing Flow

Lee, Si Young

Thermal Hydraulics Analysis for Cooling Tower Performance

Lee, Sung J.

Lee, Sung Jin

The Present State-of-the-Art Thermal Striping Studies for Sodium Cooled Fast Reactors

Lee, Tae-Ho

Lee, Wonwoong

Comparison of MARS-KS to COBRA-TF for Models and Correlations in Pre-CHF Regime

Lee, Y. T.

The Analysis of TRACE/FRAPTRAN in Ultimate Response Guideline for Lungmen ABWR Nuclear Power Plant

Lee, Yeon-Gun

Experimental Study of Condensation Heat Transfer in the Presence of Noncondensable Gas on the Vertical Tube

Lee, Youho

Heat Transfer Origin of Thermal Shock Fracture and Its Application for LWR Fuel during Reflood

Lei, Xianliang

An Experimental Study on Flow Characteristics of Homogeneous and Stratified Debris Beds

Leininger, S.

Experimental Investigations on the Coolability of Debris Beds under Variation of Inflow Conditions

Lemons, Andrea

Computational Fluid Dynamics Assessment of Emergency Core Cooling System Check Valves at Comanche Peak

Lenci, Giancarlo

Structure-Based Resolution of Turbulence for Sodium Fast Reactor Thermal Striping Applications

A Structure-Based Approach for Topological Resolution of Coherent Turbulence: Overview and Demonstration

Leskovar, M.

Uncertainty Evaluation of CFD Simulation using Optimal Statistical Estimator

Leskovar, Matjaž

Influence of Oxidation on Fuel Coolant Interaction

Letellier, Bruce

RoverD: Use of Test Data in GSI-191 Risk Assessment

Viscous Inertial Shear-Transition-Adaptive (VISTA) Porous Media Head-Loss Formulation

Leyer, Stephan

Large Scale BWR Containment LOCA Response Test at the INKA Test Facility

Experimental and Numerical Investigation of Flow Structure and Heat Transfer During High Pressure Condensation in a Declined Pipe at COSMEA Facility

Li, Cheng

Experimental Methods of the PCCS Containment Wall Condensation with Non-Condensable Gas

Li, Feng

Simulation of Esprit of Hualong Secondary Passive Residual Heat Removal System by Using RELAP5

Li, G.

Experimental and Numerical Study on Heat Transfer of Supercritical Water Flowing Upward in 2x2 Rod Bundles

Li, H. B.

Li, Hongsen

Experimental Methods of the PCCS Containment Wall Condensation with Non-Condensable Gas

Li, Huixiong

An Experimental Study on Flow Characteristics of Homogeneous and Stratified Debris Beds

Li, J. G.

Verification and Validation of a Fuel-Rod Temperature Analysis Code-BIRCH

Li, Jing

Turbulent Convection Experiment to Support IVR Strategy

Li, Liangxing

An Experimental Study on Flow Characteristics of Homogeneous and Stratified Debris Beds

Li, Longze

Development of an In-Vessel Severe Accident Analysis Code MIDAC

Li, Ma

Turbulent Convection Experiment to Support IVR Strategy

Li, Minghai

Disturbed Transient Analysis with Stable Operation Mode of TMSR-SF1

Li, Qiming

Preliminary Analysis of the Afterheat Removal in Pebble Bed Fluoride Salt Cooled High Temperature Reactors Under Accident Conditions

Li, W.

A Natural Circulation Experiment of Passive Residual Heat Removal Heat Exchanger for AP1000

Li, Wei

An Experimental Study of Air-Water Pool Entrainment in High Gas Flux Region

Li, Xin

Numerical Simulation of Anisotropic Ablation of Siliceous Concrete—Analysis of CCI-3 MCCI Experiment by MPS Method

Li, Yanheng

Thermal Analysis of Pebble-Bed Reactors based on a Tightly Coupled Mechanical-Thermal Model

Liang, Hui

Effect of End Plate on the Flow Crossing a Yawed Circular Cylinder

Liang, Zhe

Hydrogen Management Strategies and Analysis Codes Implemented by the OECD Member Countries

Liao, Jun

A Top-Down Scaling Analysis for the ROSA-IV/LSTF Integral Effects Test Facility to Support Applying the WCOBRA/TRAC-TF2 System Code to a Three-Loop Small Break LOCA

Liao, Y.

Status and Challenges of CFD-Modelling for Poly-Disperse Bubbly Flows

Lietwiler, Clayton D.

Assessment of RELAP5/MOD3.3 for Subcooled Boiling, Flashing and Condensation in a Vertical Annulus

Lillberg, Eric

Tailored Experiments for Validation of CFD with FSI for Nuclear Applications

Lim, Jean

The Effect of Electric Potential on Fibrous Debris Bypass Through a Containment Sump Strainer

Lim, Kukhee

Analysis of APR1400 Core Degradation under Cavity-Flooded Condition using MELCOR

Lin, H. C.

Experimental Study of DRACS Thermal Performance in a Low-Temperature Test Facility

Lin, H. T.

The Analysis of TRACE/FRAPTRAN in Ultimate Response Guideline for Lungmen ABWR Nuclear Power Plant

Lin, Hao-Tzu

Assessment of Station Blackout Mitigation Strategy Applying the Ultimate Response Guideline to MAANSHAN PWR

Methodology using MELCOR2.1/SNAP to Establish an SBO Model of Chinshan BWR/4 Nuclear Power Plant

Lin, Qian

Numerical Simulation of Air Natural Circulation and Thermal Radiation in Passive Containment System

Lin, Yuchen

Experimental Stability Maps for a BWR-Type Small Modular Reactor

Lindley, Benjamin A.

Hot Channel Analysis of a 333 MWth Civil Nuclear Marine Core using the COBRA-EN Code

Linthicum, Roy

Reactor Safety Gap Evaluation of Accident Tolerant Components and Severe Accident Analysis

Lisowski, D. D.

Experimental Investigation of a Scaled Reactor Cavity Cooling System with Air for the VHTR

Lisowski, Darius D.

Thermal Cycling Testing of Distributed Fiber Optic Temperature Sensors for High-Temperature Applications

Distributed Temperature Sensor Testing in Liquid Sodium

Liu, A. Q.

Numerical Calculation of the Heat Transfer Characteristics of Fuel Cladding with Dirt at Low Coolant Speed

Liu, Aiguo

Heat Loss Simulation and Uncertainty Analysis in Fuel Bundle CHF and Other Large Scale Thermal-Hydraulic Experiments

Liu, Chia-Chuan

Assessment of Station Blackout Mitigation Strategy Applying the Ultimate Response Guideline to MAANSHAN PWR

Liu, Di Lin

Experimental and Numerical Investigation of Heat Transfer and Pressure Drop in Staggered Arrangement Helically Finned-Tube Bundle

Liu, Guangxu

Development Heat Transfer Correlations for Supercritial CO2 in Natural Circulation Loop

Liu, Guimin

Preliminary Steady State and Transient Analysis of a Molten Salt Based Reactor using RELAP/SCDAPSIM/MOD4.0

Liu, Hanwen

Thermal Effects of Material Discontinuities and Oxidation on Graphite Matrix in HTGRs

Liu, Jing

Requirements Analysis and Research of Severe Accident Process Simulation Based on COS-SA Code and Emergency Decision Support

Liu, Li

Interfacial Stability in Vertical Swirling Annular Two-Phase Flow

Liu, Qiusheng

Numerical Solution of Heat Transfer Process in a Prismatic VHTR Considering Core Bypass Flow and Cross Flow

Liu, Shuji

Development of a Societal-Risk Goal for Nuclear Power Safety

Liu, Shuyong

Thermal-Hydraulic Design and CFD Analysis of Fuel Assembly for China Lead-Based Research Reactor

Liu, Wei

Research of the Bundle CHF Prediction Based on the Minimum DNBR Point and the BO Point Methods

Liu, Wenxing

Study on Critical Heat Flux with Non-Uniform Axial Heat Flux Distributions During Lifetime in Reactor Core

Research on Critical Heat Flux of PWR Fuel Assembly in NPIC

Liu, X. J.

Development and Validation of a Scaling Method for Supercritical Fluid Heat Transfer

Liu, Xirui

Trend Analysis for Low Pressure Low Flow Tube CHF

Liu, Y.

Turbulence-Induced Bubble Collision Force Model Development and Assessment for Adiabatic Dispersed Air-Water Two-Phase Flow with the Two-Fluid Model

Derivation of a Generic Multi-Field Two-Fluid Model

Liu, Yang

Treatment of Nucleation and Bubble Dynamics in High Heat Flux Boiling

Lloyd, L. J.

Multiphase RANS Simulations of Turbulent Bubbly Flows

Lo, S.

Loebig, Thomas

Computational Fluid Dynamics Assessment of Emergency Core Cooling System Check Valves at Comanche Peak

Lombard, V.

Lomperski, Stephen W.

Thermal Cycling Testing of Distributed Fiber Optic Temperature Sensors for High-Temperature Applications

Distributed Temperature Sensor Testing in Liquid Sodium

Lomperski, Steve

Key Findings and Remaining Questions in the Areas of Core-Concrete Interaction and Debris Coolability

Lou, Jiaojiao

An Experimental Study on Flow Characteristics of Homogeneous and Stratified Debris Beds

Lowe, Kirk T.

Experimental Characterization of Interchannel Mixing Through a Narrow Gap

Lowry Kee, Ernie John

Experimental Observations of Boric Acid Precipitation Scenarios

Lu, Daogang

Experimental Investigation on Transient Heat Transfer Characteristics of C-Shape Heating Rod Bundle used in PRHR HX

Lu, J.

DNS Assisted Modeling of Bubbly Flows in Vertical Channels

Lu, Qing

Development of a Thermal-Mechanical-Material Behavior Analysis Code for the Dispersion-Plate-Type Fuel

Lu, Tianyu

Typical Accidents Analysis on the Loss of Flow and External Neutron Source Changing Accidents for a 800 MWth ADS

Lu, Wei

CHF Experiment of RPV Lower Head with Real Surface Material for ERVC-IVR Strategy

Luangdilok, Wison

Calculation of the Probability of DDT during Severe Accidents

Lubchenko, N.

Modeling of the Groundwater Transport Around a Deep Borehole Nuclear Waste Repository

Lucas, D.

Direct Condensation and Entrainment Steam Experiments at the TOPFLOW-DENISE Facility

Analysis and Applications of a Generalized Multi-Field Two Fluid Approach for Plunging Jet Configuration

Evaluating Performance of Two Group Interfacial Area Transport Equation for Large Diameter Pipes

Lucas, Dirk

Status and Challenges of CFD-Modelling for Poly-Disperse Bubbly Flows

Implementation and Validation of a Surface Tension Model for the Multi-Scale Approach GENTOP

Application of CFD Towards the Thermo-Hydraulic Analysis of Spent Fuel Pool Accidents

Uncertainty Analysis of an Interfacial Area Reconstruction Algorithm

Luitjens, Jeffrey

Development of a Mechanistic Critical Heat Flux Correlation

Lundqvist, Gustav

Tailored Experiments for Validation of CFD with FSI for Nuclear Applications

Lutsanych, Sergii

Validation of CATHARE TH-SYS Code Against Experimental Reflood Tests

Development and Assessment of a Method for Evaluating Uncertainty of Input Parameters

Lux, M.

On the Liquid Metal Heat Transfer in Annular Channels: Review, Proposal and Validation of Empirical Models

Luxat, David L.

Single-Phase and Two-Phase Natural Convection in the McMaster Nuclear Reactor

Luxat, J. C.

lv, Kefeng

Experimental Study on Natural Circulation and Gas Injection Enhanced Circulation in KYLIN-II Mixed Circulation Loop

Lv, Q.

Thermal Hydraulic Benchmarking Exercises to Support Fluoride-Salt-Cooled, High-Temperature Reactor (FHR) Licensing

Experimental Study of DRACS Thermal Performance in a Low-Temperature Test Facility

Lv, Y.

A Natural Circulation Experiment of Passive Residual Heat Removal Heat Exchanger for AP1000

Lymperea, Niki

An Experimental Study on the Quench Front Velocity and Temperature during Rewetting of a Hot Vertical Rod

M

A Simple and Efficient Steam Generator Design for Integral SMRs

Ma, M.

DNS Assisted Modeling of Bubbly Flows in Vertical Channels

Ma, T.

Status and Challenges of CFD-Modelling for Poly-Disperse Bubbly Flows

Ma, Weimin

Investigation of Operational Charactistics of Passive Containment Cooling System for an Advanced PWR

Validation of the MEWA Code Against POMECO-HT Experiments and Coolability Analysis of Stratified Debris Beds

Melcor Analysis of Early Containment Venting Risk in a Severe Accident Scenario of Boiling Water Reactor

An Experimental Study on Void Generation Around Hot Metal Particle Quenched into Water Pool

An Experimental Study on the Dynamics of a Liquid Film Under Shearing Force and Thermal Influence

Maalouf, Wadih James

Wall Resolved Large Eddy Simulation of a Flow Through a Square-Edged Orifice in a Round Pipe at RE=25000

Maas, L.

EBR-II Passive Safety Demonstration Tests Benchmark Analyses—Phase 2

Macali, Mark

Viscous Inertial Shear-Transition-Adaptive (VISTA) Porous Media Head-Loss Formulation

Macek, Jiri

CFD Simulation of the Departure from Nucleate Boiling

Macian-Juan, Raphael

Experimental Investigation and Flow Visualization of Steam Condensation in a Scaled IRWST-ADS Simulator

Madeleine, S.

Experimental and Numerical Activities in Support of the Design of ASTRID Sodium-Gas Heat Exchanger

Magolan, Benjamin Lawrence

Non-Linear Eddy Viscosity Turbulence Modeling in Hydra-TH for Fuel Related Applications

Mahaffy, J.

Development, Validation and Assessment of the TRACE Thermal-Hydraulics Systems Code

Maheshwari, Naresh Kumar

CFD and Experimental Analysis of Single Phase Buoyancy Driven Counter-Current Flow in a Pipe

Makiharju, Simo A.

Experimental Characterization of Interchannel Mixing Through a Narrow Gap

Malakyan, Tsolak

CFD Modeling of Mixing Phenomena for Pressurized Thermal Shock Analysis on the DOWNCOMER of WWER-440

Malin, Michael

CFD Analysis of Turbulent Mixed Convection Upward Flow of Supercritical Water in a Vertical Tube

Malon, A.

Experimental and Analytic Study of the Damped Rocking Movement of a Cylindrical Shell in a Flowing Annular Channel

Manara, Dario

Severe Accident Facilities for European Safety Targets,

Mandy, C.

Thermal-Hydraulic Study of Siphon Breaking Phenomenon on a Two-Phase Gas/Liquid Flow

Manera, A.

Evaluating Performance of Two Group Interfacial Area Transport Equation for Large Diameter Pipes

Manera, Annalisa

Comparison of Overlapping and Separate Domain Coupling Methods

Passive Decay Heat Removal System Design for the Integral Inherent Safety Light Water Reactor (I²S-LWR)

Preliminary Design of the I²S-LWR Containment System

A Control Theory Approach to Adaptive Stepsize Selection for Coupled CFD and CRUD Chemistry Simulations

Uncertainty Analysis of an Interfacial Area Reconstruction Algorithm

CFD Analyses of Main Flow Penetration Depth in Isolated Branch Lines

A Separate-Effect Test Facility for CFD-Grade Measurements of the RCCS Upper Plenum

High Resolution Experiments of Velocity and Concentration Fluctuations in a Jet Flow

A Physical Mechanism for Rotating Lines of Symmetry in BWR Out-of-Phase Limit Cycle Oscillations

Manickam, Louis

An Experimental Study on Void Generation Around Hot Metal Particle Quenched into Water Pool

Mankosa, M. G.

Anisotropic Azimuthal Power and Temperature Distribution as a Driving Force for Hydrogen Redistribution

Manzari, Majid T.

Surrogate Spacer Grid Design for Fluid-Structure Interactions Studies in Fuel Bundles

Manzini, Giovanni

Hydrogen Combustion Benchmark Using Experiment in Double-Compartment Experimental Vessel

Mao, Hu

Improvement of Mixing Vane Crossflow Model in Subchannel Analysis

March-Leuba, Jose

A Physical Mechanism for Rotating Lines of Symmetry in BWR Out-of-Phase Limit Cycle Oscillations

March, P.

First Experimental Results of Large Scale Debris Bed Reflood Tests in the PEARL Facility

Marcum, W. R.

Comprehensive Characterization of Motion of a Helical Structure Due to Flow Induced Vibration

Marcum, Wade R.

Applying Uncertainty and Sensitivity on Thermal Hydraulic Subchannel Analysis for the Multi-Application Small Light Water Reactor

Margulis, Marat

Analysis of Protected RIA and LOFA in Plate Type Research Reactor Using Coupled Neutronics Thermal-Hydraulics System Code

Marie, N.

Comparison of an Advanced Analytical Tool with the SIMMER Code to Support Astrid Severe Accident Mitigation Studies

Marie, Nathalie

Analytical Modelling of the Primary Phase of an Unprotected Loss of Flow

Marin, Oana

Modeling of Two-Phase Flow in a BWR Fuel Assembly with a Highly-Scalable CFD Code

Verification and Validation of Nek5000 for T-Junction, Matis, SIBERIA, and Max Experiments

Marinari, R.

CFD Benchmark for a Heavy Liquid Metal Fuel Assembly

Marinari, Ranieri

CFD Pre-Test Analysis of the Fuel Pin Bundle Simulator Experiment in the NACIE-UP HLM Facility

Marking, John

NRELAP5 Predictions of KAIST High Pressure Condensation Data Using Existing and Extended Shah Condensation Correlation

Marquie, Christophe

Core Coolability in Loss of Coolant Accident: The COAL Experiments

Marshall, M.

Containment Analysis of Fukushima Daiichi Unit 1 Power Station using GOTHIC

Martelli, Daniele

Fuel Pin Bundle Experimental Characterization in HLM Large Pool System

Martelli, E.

Qualification of a RELAP5-3D© System Code Nodalization of EBR-II

Martin, J.

A Review of AREVA’s Experimental Validation of State-of-the-Art Single-Phase CFD Methods with Application to PWR Fuel Analysis and Design

Martin, M.

Martin, Mathieu G.

Validation of AREVA’s Best Practices in the Round Robin CFD Benchmark

Martin, R. P.

Heat Transfer Regime Calibration for Phase-Change Heat Exchangers in RELAP5-3D

Martineau, Richard C.

A Strongly Coupled Reactor Core Isolation Cooling System Model for Extended Station Blackout Analyses

Martinez-Cuenca, R.

Local Parameters of Air-Water Two-Phase Flow at a Vertical T-Junction

Martínez-Quiroga, Víctor

Core Exit Temperature Response during an SBLOCA Event in the Ascó NPP

Martinie, Olivier

ORFEOTM—A CHF Correlation Form Applied to GAIA, AREVA’s Advanced PWR Fuel Assembly Design

Martorell, Sebastián

Comparison of Some Approaches for the Estimation of Tolerance Limits in the Context of LBLOCA Uncertainty Analysis

Maruyama, Yu

Analysis for Progression of Accident at Fukushima Dai-ichi Nuclear Power Station with THALES2 Code

Mascari, Fulvio

Scaling Issues for the Experimental Characterization of Reactor Coolant System in Integral Test Facilities and Role of System Code as Extrapolation Pool

Masumura, Daisuke

Analysis of Metal Vessel Wall Ablation Experiment with High Temperature Liquid by MPS Method

Masuzaki, S.

Influence of Boiling Initiation Surface Superheat on Subcooled Water Flow Boiling Critical Heat Flux in a SUS304 Circular Tube at High Liquid Reynolds Number

Matsumoto, Toshinori

Analysis for Progression of Accident at Fukushima Dai-ichi Nuclear Power Station with THALES2 Code

Matteo, L.

Scaling Considerations About LWR Core Thermal Hydraulics

Matteo, Laura

Computational Thermal Hydraulics Schemes for SFR Transients Studies

Mauger, G.

Description of an Improved Turbomachinery Model to be Developed in the CATHARE3 Code for Astrid Power Conversion System Application

Transient Analysis of the ASTRID Demonstrator Including a Gas Nitrogen Power Conversion System with the CATHARE2 Code

Mayer, G.

Critical Heat Flux Experiment in Internally Heated Vertical Annulus at Low Flow and Low Pressure Conditions

Mazzoccoli, J. P.

CFD Modeling of Sodium-Oxide Deposition in Sodium-Cooled Fast Reactor Compact Heat Exchangers

McCleney, Amy B.

Initial Condition Effects on Kelvin-Helmholtz Instabilities and Development of a Round Jet

McElroy, C.

TRACG Analysis of Boiling Water Reactor Control Rod Drop Accident to Optimize Analysis Methodology

Mckrell, T. J.

Experimental Study of Heat Transfer Mechanisms Under Exponential Power Excursion in Plate-Type Fuel

McKrell, Thomas

Effects of Porous Superhydrophilic Surfaces on Flow Boiling Critical Heat Flux in IVR Accident Scenarios

Synthesis of CRUD and its Effects on Pool and Subcooled Flow Boiling

McLean, Jeffrey

Using NASA’s GFSSP Code for Steady State and Transient Modeling of Gas Cooled Reactor Passive Safety Systems

McMinn, P.

Calculation of the Probability of DDT during Severe Accidents

McMinn, Paul B.

Enhancements in MAAP5.03+ MCCI and Corium Coolability Models and Benchmarks against OECD CCI Tests

McMinn, Paul

Combined Evaluation of Bubble Dynamics, Polydispersion Model and Turbulence Modeling for Adiabatic Two-Phase Flows

Mechitoua, N.

Assessment of RANS at Low PRANDTL Number and Simulation of Sodium Boiling Flows with a CMFD Code

Medeiros, J. A. C. Canedo

Simulation of the Inadvertent Rod Cluster Control Assembly Bank Withdrawal at Power for ANGRA I NPP using an LQR Digital Controller

Meholic, M. J.

Fundamental Experiments of Condensation Heat Transfer on Water Jets in the Presence of Noncondensable Gas

A Discussion of Uncertainty Quantification for CHF as Performed in COBRA-IE

Meholic, Michael J.

An Assessment of Void Fraction Data with COBRA-IE

Mei, Yong

A Two-Scale Approach for Modeling the Corium Melt Fragmentation during Fuel-Coolant Interaction

Meignen, R.

Melia, Carles Mesado

Control Rod Drop Transient: Uncertainty and Sensitivity Analysis of Thermal-Hydraulic Variables using a 3D Model with TRACE V5.0P3/PARCS 3.0

Memmott, Matthew J.

Passive Decay Heat Removal System Design for the Integral Inherent Safety Light Water Reactor (I²S-LWR)

Preliminary Design of the I²S-LWR Containment System

Mena, Daniel

Inlet Effects on Vertical-Downward Air-Water Two-Phase Flow

Mérigoux, N.

Verification, Validation and Application of Neptune _ CFD to Two-Phase Pressurized Thermal Shocks

Combined Evaluation of Bubble Dynamics, Polydispersion Model and Turbulence Modeling for Adiabatic Two-Phase Flows

Assessment of RANS at Low PRANDTL Number and Simulation of Sodium Boiling Flows with a CMFD Code

Merigoux, Nicolas

Progress on Computation of Boiling Flow in Fuel Assemblies with NEPTUNE_CFD

A Generalized Turbulent Dispersion Model for Bubbly Flow Numerical Simulation in NEPTUNE_CFD

Merle-Lucotte, Elsa

Analytical Modelling of the Primary Phase of an Unprotected Loss of Flow

Merzari, E.

CFD Benchmark for a Heavy Liquid Metal Fuel Assembly

Calibration and Optimization of Pressurized Thermal Shock for Benchmarking Direct Numerical Simulation

Steady and Unsteady Calculations on Thermal Striping Phenomena in Triple-Parallel Jet

CFD Investigation of Wire-Wrapped Fuel Rod Bundles and Flow Sensitivity to Bundle Size

Erosion of a Large-Scale Gaseous Stratified Layer by a Turbulent Round Jet S—Simulations with URANS and LES Approaches

Merzari, Elia

Modeling of Two-Phase Flow in a BWR Fuel Assembly with a Highly-Scalable CFD Code

Large-Scale Simulation of Nuclear Reactors: Issues and Perspectives

Verification and Validation of Nek5000 for T-Junction, Matis, SIBERIA, and Max Experiments

Metrailler, D.

DNS of Turbulent Convective Flow Boiling in a Channel

Near-Wall Turbulence-Bubbles Interactions in a Channel Flow at Reτ=400: A DNS/LES investigation

Meyer, Gregory A.

Computational Fluid Dynamics Benchmark using AP1000^®1/4-Scale Upper Head Test Data

Meyer, Stefan

Phase-Field Modeling of Binary Eutectic Alloy Solidification With Convection

Meynet, N.

Hydrogen Safety: Laminar and Turbulent Flame Speed of Spherical Flame in a Fan-Stirred Closed Vessel

Miassoedov, Alexei

Severe Accident Facilities for European Safety Targets,

Live Experiments on the In-Vessel Melt Pool Behaviour with Different External Cooling Conditions and the Simulation Results with a Coupled MELCOR-PECM Approach

Core Melt Stabilization Concepts for Existing and Future LWRs and Associated R&D Needs

Mickus, Ignas

Development of TALL-3D Test Matrix for APROS Code Validation

Mignot, G.

Combined Effects of Cooler and Spray Activation on the Hydrogen Distribution in the Presence of a Jet Flow

Mignot, Guillaume

Parametric Study on Density Stratification Erosion Caused by a Horizontal Steam Jet Interacting with a Vertical Plate Obstruction

Performance of Hydrogen Mitigation Systems for a Scaled Accident Scenario: Overview of Ercosam Project Experimental Results for the Panda Facility

Migot, Benoit

Experimental and Analytic Study of the Damped Rocking Movement of a Cylindrical Shell in a Flowing Annular Channel

Mikami, Satoshi

Source Term Estimation for the Fukushima Daiichi Nuclear Power Station Accident by Combined Analysis of Environmental Monitoring and Plant Data Through Atmospheric Dispersion Simulation

Mimouni, S.

Verification, Validation and Application of Neptune _ CFD to Two-Phase Pressurized Thermal Shocks

Computational Multi-Fluid Dynamics Predictions of DNB

Mimouni, Stephane

Progress on Computation of Boiling Flow in Fuel Assemblies with NEPTUNE_CFD

Combined Evaluation of Bubble Dynamics, Polydispersion Model and Turbulence Modeling for Adiabatic Two-Phase Flows

Assessment of RANS at Low PRANDTL Number and Simulation of Sodium Boiling Flows with a CMFD Code

A Generalized Turbulent Dispersion Model for Bubbly Flow Numerical Simulation in NEPTUNE_CFD

Minelli, Paolo

Balance of Plant and Power Transmission for the Offshore Floating Nuclear Plant

Miranda, D.

Film-Droplet Split Correlation at the Onset of Annular-Mist Flow

Miranda, Dana C.

TRACG Analysis of Boiling Water Reactor Control Rod Drop Accident to Optimize Analysis Methodology

Miranda, Dana

TRACG Analysis and Results of Phase 1 of the OECD/NEA Oskarshamn-2 BWR Stability Benchmark

Mirelli, F.

Pre-Test Computational Fluid Dynamics and System Thermal Hydraulics Calculations of The E-SCAPE Scaled LBE Pool Facility

Mirelli, Fabio

Experimental Results from a Water Scale Model for the Thermal-Hydraulic Analysis of a HLM Reactor

Miró, R.

Assessment of TRACE/PARCS Benchmark Against Leibstadt Plant Data During the Turbine Trip Test

Miwa, Shuichiro

Experimental Investigation of the High Performance Steam Injector Operation

Mizokami, S.

Recent Findings on the Damaged Reactors and Containment Vessels of Fukushima Dai-ichi NPS

Mizouchi, H.

The Findings Obtained During the OECD/NEA BSAF Activity with the Employment of the SAMPSON Code

Mochizuki, H.

EBR-II Passive Safety Demonstration Tests Benchmark Analyses—Phase 2

Mochizuki, Hiroyasu

Liquid Metal Heat Transfer Under Low Peclet Number Conditions

Mohamed, Hmza

The Energetics of Coolant-Bubble-Covergas Interactions Associated with LMR Out-Of-Reactor Source Term Experiments

Mohammed, Nicholas

Effects of Steam-Water vs. Air-Water Fluid Pairs and Pressure on Flooding in Large Diameter Tubes

Mohanta, L.

Enhancement of Downward Facing Boiling Heat Transfer by the Cold Spray Technique

Mohanta, Lokanath

Experimental Study of Laminar Mixed Convection in a Rod Bundle with Mixing Vane Spacer Grids

Moharana, Avinash

Development of a Computational Model to Determine Performance of a Self-Priming Venturi Scrubber for Thorium Reactor

Moiseytseva, Vera

RoverD: Use of Test Data in GSI-191 Risk Assessment

Moisseytsev, A.

Simulations of the EBR-II Tests SHRT-17 and SHRT-45R

Möller, Sergio Viçosa

Symbolic Dynamics Applied in the Identification of Flow Patterns Inside Tube Banks

Monero-Mayorga, Javier

Experimental Investigation and Flow Visualization of Steam Condensation in a Scaled IRWST-ADS Simulator

Monrós-Andreu, G.

Local Parameters of Air-Water Two-Phase Flow at a Vertical T-Junction

Monti, Lanfranco

Application and Validation of AREVA’s Advanced Thermal-Hydraulic Methods and Codes for PWR Level III Crud Risk Assessment

Monti, S.

EBR-II Passive Safety Demonstration Tests Benchmark Analyses—Phase 2

Montoya, Gustavo A.

Implementation and Validation of a Surface Tension Model for the Multi-Scale Approach GENTOP

Moody, William L.

Computational Fluid Dynamics Benchmark using AP1000^®1/4-Scale Upper Head Test Data

Moon, Kang Hoon

Evaluation of Thales Subchannel Code Behavior for Loss of Flow and RCP ROTOR Seizure Scenarios

Moon, S. K.

MARS Code Evaluation of Reflood Phenomena in a Partially-Deformed 5x5 Rod Bundle

Moon, Sang-Ki

Effect of a Blockage Length on the Coolability during Reflood in a 2x2 Rod Bundle with a 90% Partially Blocked Region

Experimental Study for Effects of Ballooning and Power Peak on a Coolability of Fuel Rod Bundle

Moon, Sung Bo

Thermal-Hydraulic Analysis of a 7-Pin Sodium Fast Reactor Fuel Bundle with a New Pattern of Helical Wire-Wrap Spacer

Moore, T.

GOTHIC 8.1 Benchmark to THAI Facility Experiment with Steam-Helium Stratification

Moreau, V.

Numerical Analysis of MYRRHA Control Rod System Dynamics

Moreau, Vincent

Morenius, Boel

Detailed Measurements of Local Parameters in Annular Two-Phase Flow in Fuel Bundle under BWR Operating Conditions

Moretti, Fabio

Validation of CATHARE TH-SYS Code Against Experimental Reflood Tests

Development and Assessment of a Method for Evaluating Uncertainty of Input Parameters

Morfin, Frank

A First Orienting Investigation of the Interaction of Cable Fire Products with Passive Auto-Catalytic Recombiners (PARs)

Mori, Michitsugu

Experimental Investigation of the High Performance Steam Injector Operation

Mori, Takero

Safety Margins after Failure of Fuel Cladding during Protected Loss-of-Heat-Sink Accidents in a Sodium-Cooled Fast Reactor

Analysis of Natural Circulation Tests in the Experimental Fast Reactor JOYO

Morita, K.

EBR-II Passive Safety Demonstration Tests Benchmark Analyses—Phase 2

Moriyama, Kiyofumi

Simulation of Ex-Vessel Melt Jet Breakup and Sensitivity on Model Parameters and Accident Conditions

Motta, A. T.

Anisotropic Azimuthal Power and Temperature Distribution as a Driving Force for Hydrogen Redistribution

Moudjed, Brahim

Experimental Study of Gas Entrainment from Surface Swirl

Mourgues, Alejandro Carlos

Experimental and Theoretical Study of Iron Concentration on Clogging Phenomenon in Secondary Circuit of Pressurized Nuclear Power Plant

Mousseau, Vince

CTF Residual Formulation Solid Liquid Coupling

Moutin, Frederic

The CATHARE Code Condensation Modelling Confronted to the TOPFLOW-PTS Steady-State Experiments

Muci, M. A.

Experimental Investigation of a Scaled Reactor Cavity Cooling System with Air for the VHTR

Muci, M.

Analytical Modeling of a Scaled Reactor Cavity Cooling System (RCCS) with Air

Mueller, P.

RELAP5 BWR-4 Model Development and Validation for NPP Mühleberg (KKM)

Muftuoglu, K.

Muftuoglu, Kurshad

Blind and Aftermath Numerical Analyses of Supercritical Water Flow and Heat Transfer in 1/12 of 7-Rod Bundle with Spacers

Mühlbauer, P.

Muller, Thierry

Experimental and Theoretical Study of Iron Concentration on Clogging Phenomenon in Secondary Circuit of Pressurized Nuclear Power Plant

Murallidharan, J.

Simulations of High-Pressure Subcooled Boiling Flows in Rectangular Channels

Interface Tracking Based Evaluation of Bubble Growth Rates in High Pressure Pool Boiling Conditions

Murallidharan, Janani Sree

Numerical Study of Heat Diffusion Controlled Bubble Growth in a Pressurised Liquid

Murray, C.

Development, Validation and Assessment of the TRACE Thermal-Hydraulics Systems Code

Mychkovsky, Alexander G.

Experimental Characterization of Interchannel Mixing Through a Narrow Gap

Myrillas, Konstantinos

CFD and Experimental Investigation of Sloshing Parameters for the Safety Assessment of HLM Reactors

N

FCI Test Results Under Conditions of the Partially Flooded Cavity and the Flooded Reactor in the TROI

Nabeshima, Kunihiko

Analysis of Natural Circulation Tests in the Experimental Fast Reactor JOYO

Nagai, Haruyasu

Source Term Estimation for the Fukushima Daiichi Nuclear Power Station Accident by Combined Analysis of Environmental Monitoring and Plant Data Through Atmospheric Dispersion Simulation

Nagasawa, Kazuyoshi

Benchmark Analysis of Thermal Striping Phenomena in Planar Triple Parallel Jets Tests for Fundamental Validation of Fluid-Structure Thermal Interaction Code for Sodium-Cooled FastReactor

Nagase, Fumihisa

Overview and Outcomes of Benchmark Study of the Accident at the Fukushima Daiichi NPS (OECD/NEA BSAF Project)

Nagy, I.

Critical Heat Flux Experiment in Internally Heated Vertical Annulus at Low Flow and Low Pressure Conditions

Nagy, Imre

Extended Study of Coolability of VVER Bundle with Ballooned Region

Nagy, R.

Critical Heat Flux Experiment in Internally Heated Vertical Annulus at Low Flow and Low Pressure Conditions

Naito, Masanori

Overview and Outcomes of Benchmark Study of the Accident at the Fukushima Daiichi NPS (OECD/NEA BSAF Project)

Naitoh, M.

The Findings Obtained During the OECD/NEA BSAF Activity with the Employment of the SAMPSON Code

Naitoh, Masanori

Modeling of Rayleigh-Taylor Instability for Steam Direct Contact Condensation

An Approach Toward Evaluation of FP Behaviors in NPPs Under Severe Accidents

Molten Core Relocation Analysis of CORA-17 and CORA-18 for SAMPSON/MCRA Validation

Nakamura, Hideo

New AESJ Thermo-Hydraulics Roadmap for LWR Safety Improvement and Development after Fukushima-Daiichi Accident

Scaling Issues for the Experimental Characterization of Reactor Coolant System in Integral Test Facilities and Role of System Code as Extrapolation Pool

Nalbandyan, Ashkhen

CFD Modeling of Mixing Phenomena for Pressurized Thermal Shock Analysis on the DOWNCOMER of WWER-440

Narayanan, Chidu

Microlayer Models for Nucleate Boiling Simulations: The Significance of Conjugate Heat Transfer

Nayak, A. K.

Quenching of a Heated Rod: Physical Phenomena and Heat Transfer

Development of a Computational Model to Determine Performance of a Self-Priming Venturi Scrubber for Thorium Reactor

Modeling of Ex-Vessel Melt Pool Coolability Under Bottom Flooding with Decay Heat Simulation

Nayak, Arun K.

Neyret-Duperray, Hugues

OSCARD Coupling Software for Main Steam Line Break Fault Analysis—Assessment of the Mixing Phenomena in the Vessel

Nguyen, Thien Duy

High Resolution Experiments of Velocity and Concentration Fluctuations in a Jet Flow

Nguyen, Thien

A Separate-Effect Test Facility for CFD-Grade Measurements of the RCCS Upper Plenum

Nguyen, V. T.

CFD Prediction of Subcooled Boiling with Advanced Mechanistic Models of Interfacial Area Transport Equation

Nguyen, Viet-Hung

A Study on Transient Heat Transfer of the EU-ABWR External Core Catcher using the Phase-Change Effective Convectivity Model

Ničeno, B.

Simulation of Hydrogen Distribution in the Containment during a Severe Accident with Fast Hydrogen-Steam Release

Interface Tracking Based Evaluation of Bubble Growth Rates in High Pressure Pool Boiling Conditions

Niceno, Bojan

Turbulent Gas Mixing in Strong Density Stratified Shear and Non-Shear Flows

Numerical Study of Heat Diffusion Controlled Bubble Growth in a Pressurised Liquid

Nikitin, K.

RELAP5 BWR-4 Model Development and Validation for NPP Mühleberg (KKM)

Nikitin, Konstantin

Statistical Characteristics of Free Falling Water Film

Nikoglou, A. A.

Nikoglou, Andreas

An Experimental Study on the Quench Front Velocity and Temperature during Rewetting of a Hot Vertical Rod

Nikonov, S.

Uncertainty and Sensitivity Analysis of the OECD/NEA KALININ-3 Benchmark

Ninokata, Hisashi

Molten Core Relocation Analysis of CORA-17 and CORA-18 for SAMPSON/MCRA Validation

Nishi, Yoshihisa

Boiled-Up Level and Boiling Two-Phase Flow Dynamics in 5x5 Heated Rod Bundle during Boil-Off Process under Atmospheric Pressure Conditions

Nishimura, Masahiro

Safety Margins after Failure of Fuel Cladding during Protected Loss-of-Heat-Sink Accidents in a Sodium-Cooled Fast Reactor

No, Hee C.

Development of CHF Mapping Method for Fin Structured Surface

No, Hee Cheon

Optimization Methodology for Large Scale Fin Geometry on the Steel Containment of a Public Acceptable Simple SMR (PASS)

Heat Transfer Origin of Thermal Shock Fracture and Its Application for LWR Fuel during Reflood

Experimental Study and Validation of MARS Code for CCFL in Passive Emergency Core Cooling System (PECCS) of Public Acceptable Simple SMR (PASS) System

Noel, B.

Wall Superheat Prediction in Narrow Rectangular Channels Under Fully Developed Boiling of Water at Low Pressures

Noh, Hyunwoo

Experimental Study of Boiling Initiation on a Smooth Heating Surface

Nosek, A.

Experimental Investigation of Thermal Hydraulic Limits of BWR RCIC System Operation under Long-Term Operation

Novotny, Tamás

Extended Study of Coolability of VVER Bundle with Ballooned Region

Nowack, H.

Re-Evaluation of PAR Concept in German PWR with Revised PAR Model

Nunez, Daniel

High Resolution Experiments of Velocity and Concentration Fluctuations in a Jet Flow

O

Obabko, A.

CFD Benchmark for a Heavy Liquid Metal Fuel Assembly

Calibration and Optimization of Pressurized Thermal Shock for Benchmarking Direct Numerical Simulation

Erosion of a Large-Scale Gaseous Stratified Layer by a Turbulent Round Jet S—Simulations with URANS and LES Approaches

Obabko, A

Steady and Unsteady Calculations on Thermal Striping Phenomena in Triple-Parallel Jet

Obabko, Aleks

Modeling of Two-Phase Flow in a BWR Fuel Assembly with a Highly-Scalable CFD Code

Obabko, Aleksandr

Verification and Validation of Nek5000 for T-Junction, Matis, SIBERIA, and Max Experiments

Oertel, Ronald

Application of CFD Towards the Thermo-Hydraulic Analysis of Spent Fuel Pool Accidents

Oh, S.

Film-Droplet Split Correlation at the Onset of Annular-Mist Flow

Oh, Seung J.

Evaluation of Thales Subchannel Code Behavior for Loss of Flow and RCP ROTOR Seizure Scenarios

Oh, Sun Ryung

Suppression of Chemical Reactivity of Sodium-Titanium Nano Fluid in Sodium-Water Vapor Reaction

Ohira, H.

EBR-II Passive Safety Demonstration Tests Benchmark Analyses—Phase 2

Ohira, Hiroaki

Analysis of Natural Circulation Tests in the Experimental Fast Reactor JOYO

Ohira, Koji

Study on Flow Boiling Heat Transfer in Horizontal-Rectangular-Narrow-Flat Flow Channel

Ohkawa, Katsuhiro

A Top-Down Scaling Analysis for the ROSA-IV/LSTF Integral Effects Test Facility to Support Applying the WCOBRA/TRAC-TF2 System Code to a Three-Loop Small Break LOCA

Ohno, S.

Proposal of Benchmark Problem of Thermal Striping Phenomena in Planar Triple Parallel Jets Tests for Fundamental Code Validation in Sodium-Cooled Fast Reactor Development

Ohshima, H.

Proposal of Benchmark Problem of Thermal Striping Phenomena in Planar Triple Parallel Jets Tests for Fundamental Code Validation in Sodium-Cooled Fast Reactor Development

Numerical Investigation of Self-Wastage Phenomena in Steam Generator of Sodium-Cooled Fast Reactor

Progress of Thermal Hydraulic Evaluation Methods and Experimental Studies on a Sodium-Cooled Fast Reactor and Its Safety

Ohshima, Hiroyuki

Development of a Mechanistic Evaluation Method for Wastage Environment Under Sodium-Water Reaction Accident

Analysis of Natural Circulation Tests in the Experimental Fast Reactor JOYO

Verification of Interface-Tracking Method with Manufactured Solution

Oikawa, Hirohide

New AESJ Thermo-Hydraulics Roadmap for LWR Safety Improvement and Development after Fukushima-Daiichi Accident

Oka, Yoshiaki

Analysis of Metal Vessel Wall Ablation Experiment with High Temperature Liquid by MPS Method

Okada, Hidetoshi

An Approach Toward Evaluation of FP Behaviors in NPPs Under Severe Accidents

Okagaki, Yuria

Thermal Hydraulic Safety Research at JAEA after the Fukushima Dai-Ichi Nuclear Power Station Accident

Okamoto, Koji

Passive Decay Heat Removal Capability of Fixed Bed Nuclear Reactor Fuel Chamber

Analysis of Panda Spray Experiments Performed in Two Interconnected Vessels with OpenFOAM

Heat Transfer from Finned Surface in Downward-Facing Subcooled Flow Boiling

Investigation of MCCI Phenomena with Multi-Physics MPS Simulation

Oliva, J. J. Rivero

Simulation of the Inadvertent Rod Cluster Control Assembly Bank Withdrawal at Power for ANGRA I NPP using an LQR Digital Controller

Olympio, P.

Experimental and Numerical Activities in Support of the Design of ASTRID Sodium-Gas Heat Exchanger

Onder, Nihan

Assessment of Subchannel Code ASSERT-PV for Supercritical Applications

Osakabe, Masahiro

An Approach Toward Evaluation of FP Behaviors in NPPs Under Severe Accidents

Ose, Yasuo

Improvement of Wall Surface Temperature Evaluation Procedure During Subcooled Nucleate Boiling in Non-Empirical Boiling and Condensation Model

Otgonbaatar, U.

A Methodology for Characterizing Representativeness in Power Plant Performance Indicator Measurements with CFD Simulations

Otic, Ivan

Phase-Field Modeling of Binary Eutectic Alloy Solidification With Convection

Owoeye, Eyitayo James

Computational Analysis of Bubble Micro-Layer in Sub-Cooled Boiling

Owoeye, Eyitayo

Numerical Study of Bubble Coalescence in Sub-Cooled Flow Boiling

Ozar, Basar

Evaluation of Thales Subchannel Code Behavior for Loss of Flow and RCP ROTOR Seizure Scenarios

Ozdemir, Erdal

Ozdemir, O. E.

Containment Analysis of Fukushima Daiichi Unit 1 Power Station using GOTHIC

A Lumped Parameter Modeling for Mixing and Stratification in a BWR Mark I Pressure Suppression Pool

P

Paci, Sandro

Analyses of LOCAs in the Primary Heat Transfer System of the Helium Cooled Pebble Bed Blanket Concept

Pacio, J.

Thermal-Hydraulic Study of the LBE-Cooled Fuel Assembly in the MYRRHA Reactor: Experiments and Simulations

Pacio, Julio

Pagan, N.

CATHARE-TransAT Coupling for the Prediction of Boron Dilution in the Rocom Test Facility

Paik, Chan Y.

Enhancements in MAAP5.03+ MCCI and Corium Coolability Models and Benchmarks against OECD CCI Tests

Reactor Safety Gap Evaluation of Accident Tolerant Components and Severe Accident Analysis

Paik, Chan

Paladino, D.

Combined Effects of Cooler and Spray Activation on the Hydrogen Distribution in the Presence of a Jet Flow

Paladino, Domenico

Parametric Study on Density Stratification Erosion Caused by a Horizontal Steam Jet Interacting with a Vertical Plate Obstruction

Performance of Hydrogen Mitigation Systems for a Scaled Accident Scenario: Overview of Ercosam Project Experimental Results for the Panda Facility

Palmtag, Scott

Validation and Application of the 3D Neutron Transport MPACT within CASL VERA-CS

Palomino, Luis

SLIMM Decay Heat Removal by Natural Circulation of Ambient Air

Palzewicz, Stephen

Application and Validation of AREVA’s Advanced Thermal-Hydraulic Methods and Codes for PWR Level III Crud Risk Assessment

Pan, C.

Development of a Post-Dryout Heat Transfer Model

Pan, Chin

The Impact of Vertical Acceleration on the Nonlinear Behaviors of Multiple Parallel Boiling Channels

Pan, Liang-ming

Experimental Study of Pressure Drop and Modelling of Interfacial Shear for Vertical Annular Flow

Pandazis, P.

Investigation of Multidimensional Flow Mixing Phenomena in the Reactor Pressure Vessel with the System Code ATHLET

Papadolos, P.

Assessment of TRACE/PARCS Benchmark Against Leibstadt Plant Data During the Turbine Trip Test

Papini, D.

Simulation of Hydrogen Distribution in the Containment during a Severe Accident with Fast Hydrogen-Steam Release

Pappone, Dan

Validation of ANSYS CFX for Gas and Liquid Metal Flows with Conjugate Heat Transfer Within the European Project THINS

Papukchiev, A. Aleksandrov

Papukchiev, A.

Multiscale Analysis of Forced and Natural Convection Including Heat Transfer Phenomena in the TALL-3D Experimental Facility

Paranajpe, S.

Combined Effects of Cooler and Spray Activation on the Hydrogen Distribution in the Presence of a Jet Flow

Paranjape, Sidharth

Parametric Study on Density Stratification Erosion Caused by a Horizontal Steam Jet Interacting with a Vertical Plate Obstruction

Performance of Hydrogen Mitigation Systems for a Scaled Accident Scenario: Overview of Ercosam Project Experimental Results for the Panda Facility

Parisi, Carlo

Single and Two-Phase Sodium Flow Analysis for two TUCOP CABRI Tests Using the ASTEC-Na Code

Park, Goon-Cherl

Assessment of Multi-Dimensional Component of Mars with Air-Water Cross Flow Experiment

Heat Transfer Analysis of Horizontal U-Shaped Heat Exchanger Submerged in a Pool using MARS Code

Park, Gunyeop

Suppression of Chemical Reactivity of Sodium-Titanium Nano Fluid in Sodium-Water Vapor Reaction

Park, Hae Min

Effect of Wettability and Two-Phase Flow Conditions on Flow Boiling CHF Enhancement for Slug Flow

CHF Measurement for Downward Facing SUS 304 and Carbon Steel Plates under Atmospheric and Pool Boiling Conditions

Park, Hyun Sun

Roles of Boiling Surface Characterized by Micro-Structures on Boiling Heat Transfer and Critical Heat Flux

Experimental Study of Boiling Initiation on a Smooth Heating Surface

Flow Structure in Core Catcher Cooling Loop Through an Inclined-to-Vertical Elbow Bend

Suppression of Chemical Reactivity of Sodium-Titanium Nano Fluid in Sodium-Water Vapor Reaction

Simulation of Ex-Vessel Melt Jet Breakup and Sensitivity on Model Parameters and Accident Conditions

Park, Hyun-Sik

An SBLOCA Test of Pressurizer Safety Valve Line Break with the SMART-ITL Facility and its MARS-KS Code Simulation

Park, Hyungmin

Modeling of Interfacial Momentum Exchange for Wall-Bounded Bubbly Flows

Park, Ik Kyu

Multi-Scale Thermal-Hydraulic Analysis of Safety Systems of Advanced PWRs using the CUPID Code

Park, Jong Kuk

Experimental Evaluation of Local Bubble Parameters of Subcooled Boiling Flow in a Pressurized Vertical Annulus Channel

Park, Jong-Hwa

Analysis of Fukushima Unit 2 Accident by Considering the Operating Condition of RCIC System and Torus Room Flooding

Park, Jongrok-Kuk

Experimental Study for Effects of Ballooning and Power Peak on a Coolability of Fuel Rod Bundle

Park, Min Young

Development and Verification of Behavior of Tritium Analytic Code (BOTANIC)

Park, R.

Detailed Analysis of Geometry Effect on Two Phase Natural Circulation Flow under IVR-ERVC

Park, Rae-Joon

Flow Structure in Core Catcher Cooling Loop Through an Inclined-to-Vertical Elbow Bend

Park, Seong Dae

Heat Removal Characteristics of IVR-ERVC Cooling System Using Gallium Liquid Metal

Thermal-Hydraulic Analysis of a 7-Pin Sodium Fast Reactor Fuel Bundle with a New Pattern of Helical Wire-Wrap Spacer

A Visual Study of Molten Metal Fuel Coolant Interactions Under an Initial Phase of SFR Severe Accident using Gallium Metal vs Water or R123

Park, Shane

Assessment of the Best Estimate Thermal Design Method using THALES Subchannel Code

Park, So Hyun

Computational Fluid Dynamics Modeling and Validation of Swirling Flow in a Pipe with Classic Twisted Tape

Park, Y. S.

Experimental Investigation on Thermal-Hydraulics Behavior during a Station Blackout Transient in a Pressurized Water Reactor

Parks, Geoffrey T.

Hot Channel Analysis of a 333 MWth Civil Nuclear Marine Core using the COBRA-EN Code

Partmann, C.

Spatially-Resolved Measurement of Gas Phase Temperature and Velocity in the Subchannels of a Fuel Element during Dry-Out

Pasichnyk, I.

Uncertainty and Sensitivity Analysis of the OECD/NEA KALININ-3 Benchmark

Patel, G.

Numerical Study of Direct Contact Condensation of Steam on Stable Interface in a BWR Supression Pool Test Facility

Patel, Giteshkumar

CFD Modelling of Chugging Condensation Regime of BWR Suppression Pool Experiments

Pautz, A.

Computational Fluid Dynamics Analysis of the Fluid Flow and Heat Transfer in the Core Bypass Region of a PWR

Pautz, Andreas

A Methodology for Global Sensitivity Analysis of Transient Code Output Applied to a Reflood Experiment Model using TRACE

Assessment of OpenFOAM CFD Toolbox for Gravity driven Turbulent Mixing Flows in a Reactor Pressure Vessel

Pedler, Florian

Experimental and Theoretical Study of Iron Concentration on Clogging Phenomenon in Secondary Circuit of Pressurized Nuclear Power Plant

Pegonen, Reijo

Hot Fuel Element Thermal-Hydraulic Modeling in the Jules Horowitz Reactor Nominal and LOFA Conditions

Peko, D.

U.S. DOE Severe Accident Research Following the Fukushima Daiichi Accidents

Pelissier, Simon

OSCARD Coupling Software for Main Steam Line Break Fault Analysis—Assessment of the Mixing Phenomena in the Vessel

Pellegrini, M.

The Findings Obtained During the OECD/NEA BSAF Activity with the Employment of the SAMPSON Code

Pellegrini, Marco

Modeling of Rayleigh-Taylor Instability for Steam Direct Contact Condensation

An Approach Toward Evaluation of FP Behaviors in NPPs Under Severe Accidents

Benchmark Study of the Accident at the Fukushima Daiichi NPS: Best Estimate Case Comparison

Molten Core Relocation Analysis of CORA-17 and CORA-18 for SAMPSON/MCRA Validation

Peng, Tianji

Concept Design and Thermal-Hydraulic Analysis for Helium-Cooled ADS

Perez-Ferragut, M.

Revisiting ISP-13 with RELAP/SCDAPSIM/MOD3.5 using Core SCDAP Components

Perez-Martin, Sara

Single and Two-Phase Sodium Flow Analysis for two TUCOP CABRI Tests Using the ASTEC-Na Code

Perez, Jorge

Simulation of GR19 Sodium Boiling Experiments with CATHARE 2 System Code and TRIO_U MC Subchannel Code

Perez, M.

RELAP/SCDAPSIM/MOD4.0 Modification for Transient Accident Scenario of Test Blanket Modules Involving Helium Flows into Heavy Liquid Metal

Perrais, Christophe

Numerical Modeling of the Two-Phase Underexpanded Reactive CO₂-into-Sodium Jets in the Frame of Sodium Nuclear Fast Reactors

Perzon, S.

A CFD Approach to Spacer Grid Optimization for Improved Dryout Performance in BWR Fuel Bundle

Pesetti, A.

Experimental and Numerical Investigations of Interaction Between Heavy Liquid Metal and Water for Supporting the Safety of LFR GEN. IV Reator Design

Peter, E.

Developments on High Pressure Two Phase Flow Measurement Techniques

Peterson, P. F.

Thermal Hydraulic Benchmarking Exercises to Support Fluoride-Salt-Cooled, High-Temperature Reactor (FHR) Licensing

Development of the FHR Advanced Natural Circulation Analysis (FANCY) Code

Experimental Strategy for the Determination of Heat Transfer Coefficients in Pebble-Beds Cooled by Fluoride Salts

Design, Fabrication and Startup Testing in the Compact Integral Effects Test Facility in Support of Fluoride-Salt-Cooled, High-Temperature Reactor Technology

Validation of Best Estimate Models for Fluoride-Salt-Cooled, High-Temperature Reactors Using Data from the Compact Integral Effects Test (CIET 1.0) Facility

Peterson, Per F.

Thermal Hydraulics in FHRS: Key Similarities and Differences with LWRS

Petrov, Victor

A Control Theory Approach to Adaptive Stepsize Selection for Coupled CFD and CRUD Chemistry Simulations

CFD Analyses of Main Flow Penetration Depth in Isolated Branch Lines

A Separate-Effect Test Facility for CFD-Grade Measurements of the RCCS Upper Plenum

High Resolution Experiments of Velocity and Concentration Fluctuations in a Jet Flow

Petrovic, B.

Pseudo-3D Steady State Thermal-Hydraulic Modeling of the Advanced High Temperature Reactor Fuel Assembly

Petruzzi, A.

EBR-II Passive Safety Demonstration Tests Benchmark Analyses—Phase 2

Petruzzi, Alessandro

Benchmark Analysis of EBR-II Protected Loss-of-Flow Transient

Development and Assessment of a Method for Evaluating Uncertainty of Input Parameters

Petrykowski, John C.

The Energetics of Coolant-Bubble-Covergas Interactions Associated with LMR Out-Of-Reactor Source Term Experiments

Peturaud, Pierre

Overview of CFD Round Robin Benchmark of the High Fidelity Fuel Rod Bundle NESTOR Experimental Data

Pfeffer, Scott

TRACG Analysis and Results of Phase 1 of the OECD/NEA Oskarshamn-2 BWR Stability Benchmark

Pfrang, Werner

Single and Two-Phase Sodium Flow Analysis for two TUCOP CABRI Tests Using the ASTEC-Na Code

Pham, Binh T.

Uncertainty Quantification of Calculated Temperatures for Advanced Gas Reactor Fuel Irradiation Experiments

Pham, Son H.

Experimental Study of Annular Two-Phase Flow on Rod-Bundle Geometry with Spacer

Pi/uso, Pascal

Needs for Large Mass Phototype Corium Experiments: The PLINIUS-2 Platform

Piar, L.

Capability of ASTEC V2.1 to Simulate a Severe Accident in a Nuclear Power Plant —Application to a TMI-2-Like Accident Scenario

Picchi, S.

A Two-Scale Approach for Modeling the Corium Melt Fragmentation during Fuel-Coolant Interaction

Pilkhwal, D. S.

A Supercritical Pressure Parallel Channel Natural Circulation Loop

Piluso, Pascal

Plinius Prototypic Corium Experimental Platform: Major Results and Future Works

Pioro, Igor

CFD Analysis of Turbulent Mixed Convection Upward Flow of Supercritical Water in a Vertical Tube

Piotrowski, C. J.

Anisotropic Azimuthal Power and Temperature Distribution as a Driving Force for Hydrogen Redistribution

Piqueira, J. R. C.

An Initial Uncertainty Analysis on the Critical Heat Flux Evaluation for a Small-Scale Pressurized Nuclear Reactor using the COBRA Code

Planquart, P.

Tracking of Fuel Particles After Pin Failure in Nominal, Loss-of-Flow and Shutdown Conditions in the MYRRHA Reactor

Planquart, Philippe

Experimental Results from a Water Scale Model for the Thermal-Hydraulic Analysis of a HLM Reactor

CFD and Experimental Investigation of Sloshing Parameters for the Safety Assessment of HLM Reactors

Plys, Martin

Reactor Safety Gap Evaluation of Accident Tolerant Components and Severe Accident Analysis

Podgorney, R.

Modeling of the Groundwater Transport Around a Deep Borehole Nuclear Waste Repository

Podila, K.

CFD Simulation of Supercritical Flow and Heat Transfer in a Three Rod Wire Wrapped Bundle

Podila, Krishna

Assessment of Subchannel Code ASSERT-PV for Supercritical Applications

Podowski, M. Z.

Mechanistic Modeling of Two-Phase Flow Around Spacer Grids with Mixing Vanes

Podowski, Michael Z.

Modeling and Validation of Forced Convection Subcooled Boiling,

Pointer, Dave

Verification and Validation of Nek5000 for T-Junction, Matis, SIBERIA, and Max Experiments

Polazzi, Giuseppe

Experimental Fuel Pin Bundle Characterization in the NACIE-UP HLM Facility

Porter, Nathan W.

Uncertainty and Sensitivity Analysis of COBRA-TF for the OECD LWR UAM Benchmark using DAKOTA

Poss, Gerhard

Passive Autocatalytic Recombiners (PAR) Induced Ignition and the Resulting Hydrogen Deflagration Behaviour in LWR Containments

Potter, J.

Enhancement of Downward Facing Boiling Heat Transfer by the Cold Spray Technique

Povilaitis, Mantas

Hydrogen Combustion Benchmark Using Experiment in Double-Compartment Experimental Vessel

Prasser, H.-M.

Simulation of Hydrogen Distribution in the Containment during a Severe Accident with Fast Hydrogen-Steam Release

Interfacial Area Density Measurement using a Three-Layer Wire-Mesh Sensor

Pulsed Injection Tracer Mixing in Annular Liquid Films

Prasser, Horst-Michael

Experimental and Numerical Investigation of Flow Structure and Heat Transfer During High Pressure Condensation in a Declined Pipe at COSMEA Facility

Turbulent Gas Mixing in Strong Density Stratified Shear and Non-Shear Flows

Mesh Sensor for High Temperature High Pressure Applications

Prasser, M.

Uncertainty Analysis of an Interfacial Area Reconstruction Algorithm

Prelewicz, D.

Commercial Grade Dedication of RELAP5-3D^©

Prestigiacomo, Andrea

Molten Core Relocation Analysis of CORA-17 and CORA-18 for SAMPSON/MCRA Validation

Profir, Maria Manuela

Numerical Analysis of MYRRHA Control Rod System Dynamics

Prosek, A.

Uncertainty Evaluation of CFD Simulation using Optimal Statistical Estimator

Prosek, Andrej

Sources and Effects of Non-Condensable Gases in Reactor Coolant System of LWR

Puragliesi, Riccardo

Assessment of OpenFOAM CFD Toolbox for Gravity driven Turbulent Mixing Flows in a Reactor Pressure Vessel

Puustinen, Markku

CFD Modelling of Chugging Condensation Regime of BWR Suppression Pool Experiments

Q

Q, Y.

Steady and Unsteady Calculations on Thermal Striping Phenomena in Triple-Parallel Jet

Qiao, L.

CFD Analysis of Flowing Field in 5x5 Rod Bundle with Multi-Grids

Qiao, Shouxu

Inlet Effects on Vertical-Downward Air-Water Two-Phase Flow

Qin, Shengjie

Research on Critical Heat Flux of PWR Fuel Assembly in NPIC

Qiu, S. Z.

Experimental and Numerical Investigation of Heat Transfer and Pressure Drop in Staggered Arrangement Helically Finned-Tube Bundle

Experimental Investigation of CCFL in Pressurizer Surge Line with Air-Water

Qiu, S.

Development of the FHR Advanced Natural Circulation Analysis (FANCY) Code

Qiu, S.Z.

Experimental and Theoretical Research on Liquid Entrainment in AP1000 ADS Blow-Down Phase of SBLOCA

Experiment of Condensation in T-Junction: Steam-Water Flow in Water-Injected Condition

Qiu, Suizheng

COPRA Experiments on Natural Convection Heat Transfer with High RAYLEIGH Numbers

Development of an In-Vessel Severe Accident Analysis Code MIDAC

Simulations of ECC Safety Injection for Single Phase and Stratified Phase Flow

Application of RPI Model: Prediction of Subcooled Boiling and DNB in Vertical Pipes

Theoretical Analysis of the Characteristics of Critical Heat Flux in Vertical Narrow Rectangular Channels Under Motion Conditions

Development of a Thermal-Mechanical-Material Behavior Analysis Code for the Dispersion-Plate-Type Fuel

Passive Decay Heat Removal System Design for the Integral Inherent Safety Light Water Reactor (I²S-LWR)

Preliminary Design of the I²S-LWR Containment System

Study on the Improvement of TOPAZ-II System by using a Heat Pipe Radiator

Qiu

Three-Dimensional Thermal Hydraulic Analysis of a Transportable Fluoride-Salt-Cooled High-Temperature Reactor

Queral, Cesar

Experimental Investigation and Flow Visualization of Steam Condensation in a Scaled IRWST-ADS Simulator

Quintard, M.

Experimental Study of Pressure Drops in Coarse Particle Beds,

R

Rabiti, Cristian

Reactor Safety Gap Evaluation of Accident Tolerant Components and Severe Accident Analysis

Rahimi-Abkenar, Morteza

Surrogate Spacer Grid Design for Fluid-Structure Interactions Studies in Fuel Bundles

Rahman, Saidur

Ranking of Uncertain Parameters for Dynamic Event Tree Analysis: A Case Study based on a Station Blackout Scenario

Ramsden, Kevin

Boiled-Up Pool Heat Transfer for a Horizontal Tube Bundle

Rao, Y. F.

CFD Simulation of Supercritical Flow and Heat Transfer in a Three Rod Wire Wrapped Bundle

Rao, Yanfei

Assessment of Subchannel Code ASSERT-PV for Supercritical Applications

Rashkovan, A.

Nuclear Reactor Containment Flows—Modelling of Stably Stratified Layer Erosion by a Turbulent Jet

Rasquin, Michel

Interface Tracking Simulations of Bubbly Flows in the PWR Relevant Geometries

Reboux, S.

DNS of Turbulent Convective Flow Boiling in a Channel

Near-Wall Turbulence-Bubbles Interactions in a Channel Flow at Reτ=400: A DNS/LES investigation

CATHARE-TransAT Coupling for the Prediction of Boron Dilution in the Rocom Test Facility

Reboux, Sylvain

Microlayer Models for Nucleate Boiling Simulations: The Significance of Conjugate Heat Transfer

Redlinger, Reinhard

Three Dimensional Scalable All-Speed CFD Code Gasflow-MPI: Applications to Turbulent Combustion of Premixed Hydrogen-Air Mixtures with Heat and Mass Transfer

Rehm, M.

Developments on High Pressure Two Phase Flow Measurement Techniques

Reihani, Seyed

RoverD: Use of Test Data in GSI-191 Risk Assessment

Reinecke, Ernst-Arndt

Validation and Application of the REKO-DIREKT Code for the Simulation of Passive Auto-Catalytic Recombiners (PARs) Operational Behavior

A First Orienting Investigation of the Interaction of Cable Fire Products with Passive Auto-Catalytic Recombiners (PARs)

Reister, R.

U.S. DOE Severe Accident Research Following the Fukushima Daiichi Accidents

Rempe, J.

U.S. DOE Severe Accident Research Following the Fukushima Daiichi Accidents

Rempe, Joy

Reactor Safety Gap Evaluation of Accident Tolerant Components and Severe Accident Analysis

Ren, W. Y.

Experiment of Condensation in T-Junction: Steam-Water Flow in Water-Injected Condition

Ren, Wuyue

Simulations of ECC Safety Injection for Single Phase and Stratified Phase Flow

Renaud, Meignen

Past and Future R&D at IRSN on Corium Progression and Related Mitigation Strategies in a Severe Accident

Renger, Stefan

Investigation of the Release of Zinc in the Reactor Sump and the Behavior of Dissolved Zinc at Hotspots in the Reactor Core after a Loss of Coolant Accident

Repetto, Georges

The R&D PERFROI Project on Thermal Mechanical and Thermal Hydraulics Behaviors of a Fuel Rod Assembly during a Loss of Coolant Accident

Core Coolability in Loss of Coolant Accident: The COAL Experiments

Revankar, Shripad T.

Experimental and Analytical Study of Flashing Flow Through Steam Generator Tube Cracks

Flow Structure in Core Catcher Cooling Loop Through an Inclined-to-Vertical Elbow Bend

Reventos, F.

Revisiting ISP-13 with RELAP/SCDAPSIM/MOD3.5 using Core SCDAP Components

Reventós, Francesc

Core Exit Temperature Response during an SBLOCA Event in the Ascó NPP

Reyes, Jose N., Jr.

The Dynamical System Scaling Methodology: Comparing Dimensionless Governing Equations with the H2TS and FSA Methodologies

The Dynamical System Scaling Methodology

Reyes, Jose N.

Experimental Test Facility Data Synthesis with the Dynamical System Scaling Methodology

Demonstration of Test Facility Design Optimization with the Dynamical System Scaling Methodology

Rhee, Bo W.

Validation Test Plan of a CANDU-6 Moderator Tank Scaled-Down Test Facility

Flow Structure in Core Catcher Cooling Loop Through an Inclined-to-Vertical Elbow Bend

Ricciardi, Guillaume

Modeling of Fluctuating Fluid Forces Exerted on the Walls of a Concentric Annular Pipe Using Large Eddy Simulation

Richter, S.

The Development of Surface Vortices in Strongly Rotating Flow in a Cylindrical Vessel: Numerical Simulation

Riikonen, V.

Analysis of Reverse Flow in Low-Rise Inverted U-Tube Steam Generator of PWR Factel Facility

Rimbert, N.

A Two-Scale Approach for Modeling the Corium Melt Fragmentation during Fuel-Coolant Interaction

Rineiski, Andrei

A New Lumped Thermal Resistance Heat Transfer Model for Fuel Pin Structure

Rintala, V.

Numerical Study of Direct Contact Condensation of Steam on Stable Interface in a BWR Supression Pool Test Facility

Riva, Roland

Experimental Study of Gas Entrainment from Surface Swirl

Rizaal, Muhammad

Passive Decay Heat Removal Capability of Fixed Bed Nuclear Reactor Fuel Chamber

Riznic, Jovica R.

Experimental and Analytical Study of Flashing Flow Through Steam Generator Tube Cracks

Robb, K. R.

Fukushima Daiichi Unit 1 Ex-Vessel Prediction: Core Melt Spreading

Robb, Kevin R.

Fukushima Daiichi Unit 1 Ex-Vessel Prediction: Core-Concrete Interaction

Analysis of the FeCrAl Accident Tolerant Fuel Concept Benefits during BWR Station Blackout Accidents

Robb, Kevin

Reactor Safety Gap Evaluation of Accident Tolerant Components and Severe Accident Analysis

Robb, R.

Thermal-Hydraulic Analysis of a 7-Pin Sodium Fast Reactor Fuel Bundle with a New Pattern of Helical Wire-Wrap Spacer

Rodriguez-Buño, M.

Modeling of the Groundwater Transport Around a Deep Borehole Nuclear Waste Repository

Roelofs, F.

Heat and Dust Transport in a Pebble Bed HTR

CFD Benchmark for a Heavy Liquid Metal Fuel Assembly

Calibration of High Fidelity Bare Rod Bundle Simulations for Various Prandtl Fluids

High-Fidelity Numerical Reference Simulation of the Flow Through an Infinite Wire-Wrapped Assembly

Roelofs, Ferry

Thermal-Hydraulic Study of the LBE-Cooled Fuel Assembly in the MYRRHA Reactor: Experiments and Simulations

Turbulent Gas Mixing in Strong Density Stratified Shear and Non-Shear Flows

CFD Simulations to Determine the Effects of Deformations on Liquid Metal Cooled Wire Wrapped Fuel Assemblies

Roh, Caleb

Development of a Societal-Risk Goal for Nuclear Power Safety

Rohde, M.

Natural Convection Driven Heat Transfer in Fluids with Strongly Variable Properties: A Particle Image Velocimetry Study

Rommel, John

Impact of Flow Induced Vibration Acoustic Loads on the Design of the Peach Bottom Replacement Steam Dryer

Rosa, D.

Calibration and Optimization of Pressurized Thermal Shock for Benchmarking Direct Numerical Simulation

Ross, Kyle

RCIC Governing Equation Scoping Studies for Severe Accidents

Rossi, L.

Measurements of the Vertical Distribution of the Void Fraction using X-ray Attenuation for Different Flow Regimes in a Horizontal Pipe

Rossi, Lionel

Experimental Study of Gas Entrainment from Surface Swirl

Roth, Glenn

Six-Field Governing Equation Development for Advanced System Codes

Rozzia, D.

Experimental and Numerical Investigation of Double Wall Bayonet Tubes Performances in Pool Type Integral Test Facility

Ruan, J. L.

Verification and Validation of a Fuel-Rod Temperature Analysis Code-BIRCH

Ruyer, Pierre

Transient Convective Boiling: Analysis of Experimental Results

Rydl, A.

Analysis of the Fukushima Daiichi NPP Unit 3 with MELCOR_2.1

Rydl, Adolf

Melt-Concrete Interface Heat Transfer Models and Coolability Models: KWU PWR Analyses with MELCOR/CORCON and CORQUENCH

Rydström, S.

Instrumentation for Temperature and Heat Flux Measurement on a Solid Surface under BWR Operating Conditions

Rydstrom, Stefan

Measurement of Wall Temperature Fluctuations During Thermal Mixing of Non-Isothermal Water Streams

Ryu, Sung Uk

Condensation Heat Transfer Coefficient Correlation based on Slip Ratio Model in a Horizontal Heat Exchanger

An SBLOCA Test of Pressurizer Safety Valve Line Break with the SMART-ITL Facility and its MARS-KS Code Simulation

Ryzhov, N. I.

SOCRAT-BN Simulation of Siena Loss-of-Flow Experiments

Rzehak, R.

Status and Challenges of CFD-Modelling for Poly-Disperse Bubbly Flows

S

S, Y.

FCI Test Results Under Conditions of the Partially Flooded Cavity and the Flooded Reactor in the TROI

S. Kazimi, Mujid

An Updated Approach to the Prediction of Dryout and Void Fraction for RBWR Bundles

Sabharwall, P.

Experimental Study of DRACS Thermal Performance in a Low-Temperature Test Facility

Sabharwall, Piyush

Fabrication and Testing of a High-Temperature Printed Circuit Heat Exchanger

Conceptual Design of Tritium Removal Facility for FHRs

Steam Condensation in Packed Beds—An Experimental Study

Saha, P.

Film-Droplet Split Correlation at the Onset of Annular-Mist Flow

Said, I. A.

Investigation of Plenum-to-Plenum Heat Transfer and Gas Dynamics under Natural Circulation in a Scaled Down Dual Channel Module Mimicking Prismatic VHTR Core with using CFD

Saito, Kimiaki

Source Term Estimation for the Fukushima Daiichi Nuclear Power Station Accident by Combined Analysis of Environmental Monitoring and Plant Data Through Atmospheric Dispersion Simulation

Saito, Yasushi

Natural Convection Heat Transfer Characteristics of KUR Fuel Assembly during Loss of Coolant Accident

Sakai, T.

Progress of Thermal Hydraulic Evaluation Methods and Experimental Studies on a Sodium-Cooled Fast Reactor and Its Safety

Salkhordeh, Sasan

Large Eddy Simulation of Non-Isothermal Turbulent Flow Past a Circular Cylinder

Salko, R.

CTF Application to BWR Modeling and Simulations

CTF Void Drift Validation

COBRA-TF Evaluation and Application for PWR Steamline Break DNB Analysis

Salko, Robert Keith

Comparison of COBRA-TF and VIPRE-01 Against Low Flow Code Assessment Problems

Sánchez-Sáez, Francisco

Comparison of Some Approaches for the Estimation of Tolerance Limits in the Context of LBLOCA Uncertainty Analysis

Sánchez, Ana Isabel

Comparison of Some Approaches for the Estimation of Tolerance Limits in the Context of LBLOCA Uncertainty Analysis

Sandeep, T.

RELAP/SCDAPSIM/MOD4.0 Modification for Transient Accident Scenario of Test Blanket Modules Involving Helium Flows into Heavy Liquid Metal

Sangiorgi, Marco

Hydrogen Management Strategies and Analysis Codes Implemented by the OECD Member Countries

Sansone, Anthony A.

Intensification of Chemically Assisted Melt-Water Explosive Interactions

Sarathy, U. Partha

EBR-II Passive Safety Demonstration Tests Benchmark Analyses—Phase 2

Sarikaya, Baris

CFD Investigation of Wire-Wrapped Fuel Rod Bundles and Flow Sensitivity to Bundle Size

Sarikurt, F. S.

Sato, Akira

Thermal Hydraulic Safety Research at JAEA after the Fukushima Dai-Ichi Nuclear Power Station Accident

Sato, Y.

Qualification of CHF Test Facility at Stern Laboratories using Mitsubishi PWR Fuel

Interface Tracking Based Evaluation of Bubble Growth Rates in High Pressure Pool Boiling Conditions

Sato, Yohei

Numerical Study of Heat Diffusion Controlled Bubble Growth in a Pressurised Liquid

Sawant, Pravin

NRELAP5 Predictions of KAIST High Pressure Condensation Data Using Existing and Extended Shah Condensation Correlation

Saxena, A.

Pulsed Injection Tracer Mixing in Annular Liquid Films

Scammell, Alex

A Study of Heat Transfer Mechanisms and Flow Characteristics for Single Rising Taylor Bubbles

Scarlat, R. O.

Experimental Strategy for the Determination of Heat Transfer Coefficients in Pebble-Beds Cooled by Fluoride Salts

Experimental and Modeling Studies of Over-Cooling Transients in Fluoride-Salt Cooled High-Temperature Reactors

Scarlat, Raluca O.

Characterization of Tritium Transport in the FLibe-Graphite System, for In-Situ Tritium Absorption by the Fuel Elements of the Fluoride-Salt-Cooled High-Temperature Reactor (FHR)

Schäfer, Thomas

Investigations on Centrifugal Pumps under Air Entrainment Conditions

Schaffrath, A.

Study of Safety and International Development of Small Modular Reactors (SMR)

Scheveneels, Guy

Influence of the 3-D Phenomena on the Safety Parameters during a ULOF Accident in the MYRRHA Reactor

Schlegel, J. P.

Turbulence-Induced Bubble Collision Force Model Development and Assessment for Adiabatic Dispersed Air-Water Two-Phase Flow with the Two-Fluid Model

Assessment of an Interfacial Shear Term for Adiabatic Dispersed Air-Water Two-Phase Flow with the Two-Fluid Model

Evaluation of Interfacial Area Transport Equation in Coupled Two-Fluid Model Computation

Schleicher, E.

Spatially-Resolved Measurement of Gas Phase Temperature and Velocity in the Subchannels of a Fuel Element during Dry-Out

Schlueter, M.

The Development of Surface Vortices in Strongly Rotating Flow in a Cylindrical Vessel: Numerical Simulation

Schmidt, H.

Developments on High Pressure Two Phase Flow Measurement Techniques

Schneider, A. S.

Single-Phase and Two-Phase Natural Convection in the McMaster Nuclear Reactor

Schnieders, Gerhard H.

Experimental Investigation of Flat Plate Deflection Under Variable Velocity Parallel Flow

Schoeffel, P. J.

Investigation of Multidimensional Flow Mixing Phenomena in the Reactor Pressure Vessel with the System Code ATHLET

Schoen, B.

Conclusions on Boron Precipitation following a Large Break Loss of Coolant Accident

Schollenberger, S. P.

Conclusions on Boron Precipitation following a Large Break Loss of Coolant Accident

Schramm, Berthold

Validation of CFD-Codes for Natural Convection and Condensation Phenomena in Containments with German THAI-Experiments

Schriener, Timothy M.

Convection Heat Transfer Analysis and Correlation for Alkali Liquid Metals in Uniformly Heated Tubes

Schubring, D.

Comparison of Thermal Hydraulic Analysis Methods (Codes) for the University of Florida Training Reactor (UFTR)

Schubring, DuWayne L.

Numerical Study of Bubble Coalescence in Sub-Cooled Flow Boiling

Schubring, DuWayne

Computational Analysis of Bubble Micro-Layer in Sub-Cooled Boiling

Schulenberg, Thomas

A Novel Approach for Turbulence Modeling of Wavy Stratified Two-Phase Flow

Schulze, Anni

Towards a Coupled Simulation of Thermal Hydraulics and Neutronics in a Simplified PWR with a 3x3 Pin Assembly

Schwarz, S.

Re-Evaluation of PAR Concept in German PWR with Revised PAR Model

Schyns, Marc

CFD and Experimental Investigation of Sloshing Parameters for the Safety Assessment of HLM Reactors

Sebilleau, F.

URANS Simulations of Thermal Stratification in a Large Enclosure for Severe Accident Scenarios

Sebilleau, Frederic

CFD and Experimental Analysis of Single Phase Buoyancy Driven Counter-Current Flow in a Pipe

Sebilleau, Julien

Transient Convective Boiling: Analysis of Experimental Results

Seeliger, Andre

Investigation of the Release of Zinc in the Reactor Sump and the Behavior of Dissolved Zinc at Hotspots in the Reactor Core after a Loss of Coolant Accident

Segall, A. E.

Enhancement of Downward Facing Boiling Heat Transfer by the Cold Spray Technique

Segrue, R.

A Reevaluation of the Lift Force in Eulerian Multiphase CFD

Sehgal, B. R.

Severe Accident Progression in the BWR Lower Plenum and the Modes of Vessel Failure

Seidel, T.

Direct Condensation and Entrainment Steam Experiments at the TOPFLOW-DENISE Facility

Seidl, Marcus

Determination of the Pressure Loss Coefficient at the Control-Rod Guide Tube Flow-Hole for a PWR Nuclear Fuel Assembly by using CFD and Bernoulli Solutions

Towards the Development of a Full-Scale Transient CFD Model to Simulate the Static and Dynamic in-Core Mass Flux Distribution in a Classical German PWR

Seiler, Jean-Marie

Simulation of GR19 Sodium Boiling Experiments with CATHARE 2 System Code and TRIO_U MC Subchannel Code

Sekhri, A.

Assessment of TRACE/PARCS Benchmark Against Leibstadt Plant Data During the Turbine Trip Test

Selvam, Karthick

Numerical Analysis of Influence of Branch Flow on Thermal Mixing in a T-Junction Piping System

Mesh Sensor for High Temperature High Pressure Applications

Semenov, V. N.

SOCRAT-BN Simulation of Siena Loss-of-Flow Experiments

Seo, Gwang Hyeok

Effects of Various Thin Film Coating Techniques on Pool Boiling Heat Transfer

Effect of Oxide Layer Thickness on the Pool Boiling Critical Heat Flux of Pre-Oxidized RPV Material

Seo, Han

Critical Heat Flux Enhancement Mechanism by Surface Modification based on Hydrodynamic Instability Mode

Seo, Kyong-Won

A Consideration of Experimental Uncertainties for Predicting CHF in Rod Bundles

Seo, Phil-Won

Operational Experience of Ceramic Honeycomb Passive Autocatalytic Recombiner as a Hydrogen Mitigation System

Seo, Seok Bin

Effects of Coating Structure by Al₂O₃ Nanoparticles Deposition on Critical Heat Flux of R123 in Flow Boiling

Thermal-Hydraulic Analysis of a 7-Pin Sodium Fast Reactor Fuel Bundle with a New Pattern of Helical Wire-Wrap Spacer

Sermenghi, Valerio

Experimental Fuel Pin Bundle Characterization in the NACIE-UP HLM Facility

Seubert, A.

Modeling of the Thermal Hydraulics of Very-High-Temperature Reactors with the System Code ATHLET

Seynhaeve, Jean-Marie Alexandre

Implementation and Assessment of the Delayed Equilibrium Model for Computing Flashing Choked Flows into a Multi-Field CFD Code

Seynhaeve, Jean-Marie

Uncertainty Analysis of Delayed Equilibrium Model (DEM) using the CIRCE Methodology

Sha, Huie

Requirements Analysis and Research of Severe Accident Process Simulation Based on COS-SA Code and Emergency Decision Support

Shams, A.

Heat and Dust Transport in a Pebble Bed HTR

CFD Benchmark for a Heavy Liquid Metal Fuel Assembly

Calibration of High Fidelity Bare Rod Bundle Simulations for Various Prandtl Fluids

Fluid-Structure Interaction in a Wire-Wrapped Rod Bundle Cooled with Supercritical Water

High-Fidelity Numerical Reference Simulation of the Flow Through an Infinite Wire-Wrapped Assembly

Numerical Prediction of Flow Induced Vibrations in Nuclear Reactor Applications

Shams, Afaque

Calibration and Optimization of Pressurized Thermal Shock for Benchmarking Direct Numerical Simulation

Turbulent Gas Mixing in Strong Density Stratified Shear and Non-Shear Flows

Shan, Jianqiang

Research of the Bundle CHF Prediction Based on the Minimum DNBR Point and the BO Point Methods

Thermal-Hydraulic Design and Transient Analysis of Passive Air Cooling System for CPR1000 Spent Fuel Storage Pool

Analysis of the SBLOCA on the Improved CPR1000 with Passive Systems

Comparison Analysis of CHF Parametric Trends in Vertical Tubes and 5x5 Bundle

Improvement and Validation of the Wall Heat Transfer Package of RELAP5/MOD3.3

Study on Startup Characteristics of Heat Pipe Cooled Space Reactor

Typical Accidents Analysis on the Loss of Flow and External Neutron Source Changing Accidents for a 800 MWth ADS

Implementation of Strong Implicit Procedure for the Energy Equations in Subchannel Code ATHAS

Accident Analysis of Heat Pipe Cooled Space Reactor

Improvement of Mixing Vane Crossflow Model in Subchannel Analysis

Shao, Ge

Assessment of Molten Pool Cooling Characteristics During LBLOCA for Advanced Passive PWR,

Shao, M.

Development of the FHR Advanced Natural Circulation Analysis (FANCY) Code

Sharabi, Medhat

Turbulent Gas Mixing in Strong Density Stratified Shear and Non-Shear Flows

Sharma, Manish

A Supercritical Pressure Parallel Channel Natural Circulation Loop

Sharma, S. L.

Turbulence-Induced Bubble Collision Force Model Development and Assessment for Adiabatic Dispersed Air-Water Two-Phase Flow with the Two-Fluid Model

Assessment of an Interfacial Shear Term for Adiabatic Dispersed Air-Water Two-Phase Flow with the Two-Fluid Model

Sharpe, P.

Sharpe, Phil

Mechanistic Modeling of Two-Phase Flow Around Spacer Grids with Mixing Vanes

Shaver, D. R.

Shaver, Dillon R.

Modeling and Validation of Forced Convection Subcooled Boiling,

Shen, X.

Evaluation of Interfacial Area Transport Equation in Coupled Two-Fluid Model Computation

Sheng, D. Y.

A CFD Approach to Spacer Grid Optimization for Improved Dryout Performance in BWR Fuel Bundle

Sheng, Dong-Yuan

Determination of the Pressure Loss Coefficient at the Control-Rod Guide Tube Flow-Hole for a PWR Nuclear Fuel Assembly by using CFD and Bernoulli Solutions

Towards the Development of a Full-Scale Transient CFD Model to Simulate the Static and Dynamic in-Core Mass Flux Distribution in a Classical German PWR

Sheng, Xuanyu

Concept Design and Thermal-Hydraulic Analysis for Helium-Cooled ADS

Sheng, Yang

Effects of Additives on CHF Behaviors for ERVC-IVR Strategy with FIRM Facility

Shi, Shanbin

Experimental Stability Maps for a BWR-Type Small Modular Reactor

Shih, C.

The Analysis of TRACE/FRAPTRAN in Ultimate Response Guideline for Lungmen ABWR Nuclear Power Plant

Shih, Chunkuan

Assessment of Station Blackout Mitigation Strategy Applying the Ultimate Response Guideline to MAANSHAN PWR

Methodology using MELCOR2.1/SNAP to Establish an SBO Model of Chinshan BWR/4 Nuclear Power Plant

Shin, Chunkuan

Developments and Applications of TRACE/CFD Model of Maanshan PWR Pressure Vessel

Shinian, Peng

Model Development of UO2-ZR Plate Fuel Behavior at Early Phase of Severe Accident and Molten Fuel Meat Relocation

Shirakawa, Kenetsu

Boiled-Up Level and Boiling Two-Phase Flow Dynamics in 5x5 Heated Rod Bundle during Boil-Off Process under Atmospheric Pressure Conditions

Shirvan, K.

Compact Steam Generator for Nuclear Application

Simulation of Orientation Effects on Critical Heat Flux in Downward-Facing Channel for IVR

Shirvan, Koroush

An Updated Approach to the Prediction of Dryout and Void Fraction for RBWR Bundles

Shockling, M. A.

Non-Parametric Order Statistics: Providing Assurance of Nuclear Safety

Sibamoto, Yasuteru

Thermal Hydraulic Safety Research at JAEA after the Fukushima Dai-Ichi Nuclear Power Station Accident

Siccama, N. B.

Hydrogen Risk Assessment—CFD Model Validation and Reactor Scale Application

Sieber, Galina

Application and Validation of AREVA’s Advanced Thermal-Hydraulic Methods and Codes for PWR Level III Crud Risk Assessment

Siegel, Andrew

Large-Scale Simulation of Nuclear Reactors: Issues and Perspectives

Simon, L. I.

Computational Thermal Hydraulics Schemes for SFR Transients Studies

Simoneau, J.-P.

Numerical Investigations of a Spent Fuel Storage Pool in Abnormal Conditions

Simopoulos, S. E.

Statistical Characteristics of Free Falling Water Film

Sinan Sarikurt, Fatih

CFD Simulations of Erosion of a Stratified Layer by a Buoyant Jet in a Large Vessel

Singh, Nitendra

Modeling of Ex-Vessel Melt Pool Coolability Under Bottom Flooding with Decay Heat Simulation

Skavdahl, Isaac

Fabrication and Testing of a High-Temperature Printed Circuit Heat Exchanger

Skilone, D. J.

Fundamental Experiments of Condensation Heat Transfer on Water Jets in the Presence of Noncondensable Gas

Smith, B.

Synthesis of the OECD/NEA-PSI CFD Benchmark Exercise

Smith, Barton L.

Transient Convection from Forced to Natural with Flow Reversal for CFD Validation

CFD Validation Experiments: What’s the Difference?

Smith, Curtis L.

10 CFR 50.46c Rulemaking: A Novel Approach in Restating the LOCA Problem for PWRs

Smith, Jeffry

Application of CD-ADAPCO Best Practices to NESTOR OMEGA MVG Benchmark Exercises Using STAR-CCM+

Smith, L. David, III

High Resolution Thermal Mixing at Westinghouse ODEN Loop

Use of CFD to Predict Critical Heat Flux in Rod Bundles

Smith, Thomas M.

Non-Linear Eddy Viscosity Turbulence Modeling in Hydra-TH for Fuel Related Applications

Sohag, Faruk Ahmed

Enhancement of Downward Facing Boiling Heat Transfer by the Cold Spray Technique

Sokolowski, Lukasz

Recommendations of Two-Phase Critical Non-Flashing Flow Mixture Calculations in One-Dimensional System Code RELAP5

Solbrekken, G. L.

Fluid-Structure Interaction (FSI) Modeling of Thin Plates

Solbrekken, Gary L.

Experimental Investigation of Flat Plate Deflection Under Variable Velocity Parallel Flow

Solom, M.

Experimental Investigation of Thermal Hydraulic Limits of BWR RCIC System Operation under Long-Term Operation

Son, Hong Hyun

Effects of Various Thin Film Coating Techniques on Pool Boiling Heat Transfer

Effect of Oxide Layer Thickness on the Pool Boiling Critical Heat Flux of Pre-Oxidized RPV Material

Son, Seongmin

Printed Circuit Heat Exchanger Design, Analysis and Experiment

Song, C. H.

On the Application of Wall Boiling Models to Prediction of Subcooled Flow Boiling using EAGLE Code

Song, C.-H.

CFD Prediction of Subcooled Boiling with Advanced Mechanistic Models of Interfacial Area Transport Equation

Experimental Evaluation of Local Bubble Parameters of Subcooled Boiling Flow in a Pressurized Vertical Annulus Channel

MARS Code Evaluation of Reflood Phenomena in a Partially-Deformed 5x5 Rod Bundle

Song, Chul-Hwa

Condensation Heat Transfer Coefficient Correlation based on Slip Ratio Model in a Horizontal Heat Exchanger

Effect of a Blockage Length on the Coolability during Reflood in a 2x2 Rod Bundle with a 90% Partially Blocked Region

Experimental Study for Effects of Ballooning and Power Peak on a Coolability of Fuel Rod Bundle

Observation of CHF Phenomena Based on a Visualization of Near Wall Boiling Structure in Vertical Narrow Channel Submerged in a Pool

Multi-Scale Thermal-Hydraulic Analysis of Safety Systems of Advanced PWRs using the CUPID Code

Issues and Challenges on Advanced Thermal-Hydraulic Safety Research

Song, Dong Soo

Reactor Core Analysis at Low Flow Condition Using THALES Subchannel Code

Song, J. H.

FCI Test Results Under Conditions of the Partially Flooded Cavity and the Flooded Reactor in the TROI

Song, Jin Ho

Flow Structure in Core Catcher Cooling Loop Through an Inclined-to-Vertical Elbow Bend

VESTA Test Facility for Severe Accident Researches at KAERI

Song, Jinho

Thermal Hydraulic and Core Relocation Analysis on Fukushima Daiichi Unit 1

Effect of External Water Injection on Core Degradation and Fission Product Release in Fukushima Unit 1 Accident

Analysis of Fukushima Unit 2 Accident by Considering the Operating Condition of RCIC System and Torus Room Flooding

Song, Ki-Won

Flow Structure in Core Catcher Cooling Loop Through an Inclined-to-Vertical Elbow Bend

Song, Mingliang

Experimental and Numerical Investigation on Single Air Bubble Rising in Narrow Rectangular Channel

Song, Minseop

Computational Fluid Dynamics Modeling and Validation of Swirling Flow in a Pipe with Classic Twisted Tape

Song, Mun Won

Experimental Study and Validation of MARS Code for CCFL in Passive Emergency Core Cooling System (PECCS) of Public Acceptable Simple SMR (PASS) System

Song, Shixiong

A Specialized Thermal-Hydraulic Code with Porous Media Model and SIMPLEC Algorithm for PB-FHRs

Song, Yong

Unprotected Transient Analyses of Natural Circulation LBE-Cooled Accelerator Driven Sub-Critical System

Thermal-Hydraulic Design and CFD Analysis of Fuel Assembly for China Lead-Based Research Reactor

Sonnenkalb, M.

Re-Evaluation of PAR Concept in German PWR with Revised PAR Model

ATHLET-CD/COCOSYS Analyses of Severe Accidents in Fukushima (Units 2 and 3) within the OECD/NEA BSAF Project, Phase 1

Sonnenkalb, Martin

Validation of CFD-Codes for Natural Convection and Condensation Phenomena in Containments with German THAI-Experiments

Hydrogen Management Strategies and Analysis Codes Implemented by the OECD Member Countries

Soo, Eung

Development and Verification of Behavior of Tritium Analytic Code (BOTANIC)

Sosnovsky, Eugeny

CFD Simulations to Determine the Effects of Deformations on Liquid Metal Cooled Wire Wrapped Fuel Assemblies

Spaccapaniccia, Chiara

Experimental Results from a Water Scale Model for the Thermal-Hydraulic Analysis of a HLM Reactor

Splawski, A.

Multiphase RANS Simulations of Turbulent Bubbly Flows

Spore, J.

Development, Validation and Assessment of the TRACE Thermal-Hydraulics Systems Code

Springfels, D.

Comparison of Thermal Hydraulic Analysis Methods (Codes) for the University of Florida Training Reactor (UFTR)

Stafford, S.

Anisotropic Azimuthal Power and Temperature Distribution as a Driving Force for Hydrogen Redistribution

Staudenmeier, J.

Development, Validation and Assessment of the TRACE Thermal-Hydraulics Systems Code

Steffen, P.-M.

Validation and Application of the REKO-DIREKT Code for the Simulation of Passive Auto-Catalytic Recombiners (PARs) Operational Behavior

Steffen, Paul-Martin

Development and Qualification of an Aerosol Generator for Investigations Under Thermal-Hydraulic Severe Accident Boundary Conditions

Steiner, P.

Simulation of Hydrogen Distribution in the Containment during a Severe Accident with Fast Hydrogen-Steam Release

Steiner, Pascal

Melt-Concrete Interface Heat Transfer Models and Coolability Models: KWU PWR Analyses with MELCOR/CORCON and CORQUENCH

Stewering, Joern

Validation of CFD-Codes for Natural Convection and Condensation Phenomena in Containments with German THAI-Experiments

Stimpson, Shane

Validation and Application of the 3D Neutron Transport MPACT within CASL VERA-CS

Strömgren, T.

A CFD Approach to Spacer Grid Optimization for Improved Dryout Performance in BWR Fuel Bundle

Stucki,, S.

Interfacial Area Density Measurement using a Three-Layer Wire-Mesh Sensor

Stürzel, T.

Unsteady Void Measurements Within Debris Beds using High Speed X-Ray Tomography

Su, G. H.

Development of an In-Vessel Severe Accident Analysis Code MIDAC

Application of RPI Model: Prediction of Subcooled Boiling and DNB in Vertical Pipes

Experimental and Numerical Investigation of Heat Transfer and Pressure Drop in Staggered Arrangement Helically Finned-Tube Bundle

EBR-II Passive Safety Demonstration Tests Benchmark Analyses—Phase 2

Experimental Investigation of CCFL in Pressurizer Surge Line with Air-Water

Su, G.

Experimental Study of Heat Transfer Mechanisms Under Exponential Power Excursion in Plate-Type Fuel

Su, G.H.

Experimental and Theoretical Research on Liquid Entrainment in AP1000 ADS Blow-Down Phase of SBLOCA

Simulations of ECC Safety Injection for Single Phase and Stratified Phase Flow

Experiment of Condensation in T-Junction: Steam-Water Flow in Water-Injected Condition

Su, Guanghui

COPRA Experiments on Natural Convection Heat Transfer with High RAYLEIGH Numbers

Theoretical Analysis of the Characteristics of Critical Heat Flux in Vertical Narrow Rectangular Channels Under Motion Conditions

Development of a Thermal-Mechanical-Material Behavior Analysis Code for the Dispersion-Plate-Type Fuel

Study on the Improvement of TOPAZ-II System by using a Heat Pipe Radiator

Subramani, H.

Evaluation of Interfacial Area Transport Equation in Coupled Two-Fluid Model Computation

Suddaby, David A.

Impact of Flow Induced Vibration Acoustic Loads on the Design of the Peach Bottom Replacement Steam Dryer

Sugimoto, Jun

New AESJ Thermo-Hydraulics Roadmap for LWR Safety Improvement and Development after Fukushima-Daiichi Accident

Severe Accident Research in Japan After Accident at Fukushima Daiichi NPS

Suh, Jae-Seung

An SBLOCA Test of Pressurizer Safety Valve Line Break with the SMART-ITL Facility and its MARS-KS Code Simulation

Sui, D.

EBR-II Passive Safety Demonstration Tests Benchmark Analyses—Phase 2

Suizheng

Three-Dimensional Thermal Hydraulic Analysis of a Transportable Fluoride-Salt-Cooled High-Temperature Reactor

Sumner, T.

Simulations of the EBR-II Tests SHRT-17 and SHRT-45R

Recent Developments for the SAS4A/SASSYS-1 Safety Analysis Code

Sun, D.C.

Experimental and Theoretical Research on Liquid Entrainment in AP1000 ADS Blow-Down Phase of SBLOCA

Sun, HaoMin

Thermal Hydraulic Safety Research at JAEA after the Fukushima Dai-Ichi Nuclear Power Station Accident

Sun, Kaichao

Three-Dimensional Thermal Hydraulic Analysis of a Transportable Fluoride-Salt-Cooled High-Temperature Reactor

Sun, Qaing

Loss of Coolant Flow Accident Analysis for Fluoride Salt Cooled High Temperature Reactor

Sun, Qiang

Preliminary Analysis of the Afterheat Removal in Pebble Bed Fluoride Salt Cooled High Temperature Reactors Under Accident Conditions

Sun, Shende

Sun, X.

Thermal Hydraulic Benchmarking Exercises to Support Fluoride-Salt-Cooled, High-Temperature Reactor (FHR) Licensing

Experimental Study of DRACS Thermal Performance in a Low-Temperature Test Facility

Preliminary Structural Assessment of a Printed Circuit Heat Exchanger with S-Shaped Fins

Sun, Xiaodong

Fabrication and Testing of a High-Temperature Printed Circuit Heat Exchanger

Conceptual Design of Tritium Removal Facility for FHRs

Modeling the Mechanical Integrity of Airfoil Printed Circuit Heat Exchangers

Sung, Je-Joong

Operational Experience of Ceramic Honeycomb Passive Autocatalytic Recombiner as a Hydrogen Mitigation System

Sung, Y.

Use of CFD to Predict Critical Heat Flux in Rod Bundles

Sung, Yixing

COBRA-TF Evaluation and Application for PWR Steamline Break DNB Analysis

CFD Evaluation of OECD PSBT Geometry Effects Based on Fluid Temperature Measurements

Sutton, Todd

Analysis of the AP1000® Passive Containment Cooling System Air Flow Path Using Computational Fluid Dynamics

Suzuki, H.

The Findings Obtained During the OECD/NEA BSAF Activity with the Employment of the SAMPSON Code

Svishchev, Anatoly

Three Dimensional Scalable All-Speed CFD Code Gasflow-MPI: Applications to Turbulent Combustion of Premixed Hydrogen-Air Mixtures with Heat and Mass Transfer

Swanson, Ryan

Application and Validation of AREVA’s Advanced Thermal-Hydraulic Methods and Codes for PWR Level III Crud Risk Assessment

Swartele, G. W.

Experimental and Numerical Investigation of Flow Structure and Heat Transfer During High Pressure Condensation in a Declined Pipe at COSMEA Facility

Szijarto, Rita

Szilard, Ronaldo H.

10 CFR 50.46c Rulemaking: A Novel Approach in Restating the LOCA Problem for PWRs

T

Taha, M. M.

Investigation of Plenum-to-Plenum Heat Transfer and Gas Dynamics under Natural Circulation in a Scaled Down Dual Channel Module Mimicking Prismatic VHTR Core with using CFD

Tahara, Mika

A Study on Transient Heat Transfer of the EU-ABWR External Core Catcher using the Phase-Change Effective Convectivity Model

Takahashi, A.

The Findings Obtained During the OECD/NEA BSAF Activity with the Employment of the SAMPSON Code

Takano, Kenji

Subcooled Boiling-Induced Vibration of a Single Heater Rod Confined with Metallic Walls

Takata, T.

Numerical Study on Modeling of Liquid Film Flow under Countercurrent Flow Limitation in Volume of Fluid Method

Numerical Investigation of Self-Wastage Phenomena in Steam Generator of Sodium-Cooled Fast Reactor

Takeda, Takeshi

Thermal Hydraulic Safety Research at JAEA after the Fukushima Dai-Ichi Nuclear Power Station Accident

Takeuchi, J.

Qualification of CHF Test Facility at Stern Laboratories using Mitsubishi PWR Fuel

Takeya, Yuto

Experimental Investigation of the High Performance Steam Injector Operation

Taleyarkhan, Rusi P.

Intensification of Chemically Assisted Melt-Water Explosive Interactions

Talley, J. D.

Derivation of a Generic Multi-Field Two-Fluid Model

Tanaka, M.

Proposal of Benchmark Problem of Thermal Striping Phenomena in Planar Triple Parallel Jets Tests for Fundamental Code Validation in Sodium-Cooled Fast Reactor Development

Progress of Thermal Hydraulic Evaluation Methods and Experimental Studies on a Sodium-Cooled Fast Reactor and Its Safety

Tanaka, Masaaki

Benchmark Analysis of Thermal Striping Phenomena in Planar Triple Parallel Jets Tests for Fundamental Validation of Fluid-Structure Thermal Interaction Code for Sodium-Cooled FastReactor

Tang, Zhongfeng

Numerical Prediction of Turbulent Convective Heat Transfer with Molten Salt in Circular Pipe

Tanskanen, V.

Numerical Study of Direct Contact Condensation of Steam on Stable Interface in a BWR Supression Pool Test Facility

Tanskanen, Vesa

CFD Modelling of Chugging Condensation Regime of BWR Suppression Pool Experiments

Tarantino, M.

Experimental and Numerical Investigation of Double Wall Bayonet Tubes Performances in Pool Type Integral Test Facility

Tarantino, Mariano

Experimental Study on Natural Circulation and Gas Injection Enhanced Circulation in KYLIN-II Mixed Circulation Loop

Fuel Pin Bundle Experimental Characterization in HLM Large Pool System

Experimental Fuel Pin Bundle Characterization in the NACIE-UP HLM Facility

Tardif, Nicolas

The R&D PERFROI Project on Thermal Mechanical and Thermal Hydraulics Behaviors of a Fuel Rod Assembly during a Loss of Coolant Accident

Tatli, E.

CFD Modeling of Sodium-Oxide Deposition in Sodium-Cooled Fast Reactor Compact Heat Exchangers

Tatli, Emre

CFD Evaluation of OECD PSBT Geometry Effects Based on Fluid Temperature Measurements

Tatu, Alin

Scaling Analysis for DVI Line Break Accident of APR1400 based on ATLAS Experiment

Tauveron, N.

Description of an Improved Turbomachinery Model to be Developed in the CATHARE3 Code for Astrid Power Conversion System Application

te Lintelo, J. G. T.

Hydrogen Risk Assessment—CFD Model Validation and Reactor Scale Application

Tejne, Henrik

High Resolution Thermal Mixing at Westinghouse ODEN Loop

Tejne, Henryk

Detailed Measurements of Local Parameters in Annular Two-Phase Flow in Fuel Bundle under BWR Operating Conditions

Tekavčič, M.

Three-Dimensional Simulation of Flooding Waves in a Vertical Pipe

Teng, Hu

Effects of Additives on CHF Behaviors for ERVC-IVR Strategy with FIRM Facility

Tentner, Adrian

Modeling of Two-Phase Flow in a BWR Fuel Assembly with a Highly-Scalable CFD Code

ter Hofstede, E.

Numerical Prediction of Flow Induced Vibrations in Nuclear Reactor Applications

Terada, Hiroaki

Source Term Estimation for the Fukushima Daiichi Nuclear Power Station Accident by Combined Analysis of Environmental Monitoring and Plant Data Through Atmospheric Dispersion Simulation

Thakrar, R.

Simulations of High-Pressure Subcooled Boiling Flows in Rectangular Channels

Thakre, Sachin

Validation of the MEWA Code Against POMECO-HT Experiments and Coolability Analysis of Stratified Debris Beds

An Experimental Study on Void Generation Around Hot Metal Particle Quenched into Water Pool

Theuret, Robert C.

Impact of Flow Induced Vibration Acoustic Loads on the Design of the Peach Bottom Replacement Steam Dryer

Thomas, J. W.

Steady and Unsteady Calculations on Thermal Striping Phenomena in Triple-Parallel Jet

Recent Developments for the SAS4A/SASSYS-1 Safety Analysis Code

Thomas, Justin W.

Coupled Calculations of SAS4A/SASSYS-1 and STAR-CCM+ for the SHRT-45R Test in EBR-II

Thurgood, M.

Development, Validation and Assessment of the TRACE Thermal-Hydraulics Systems Code

Tian, W. X.

Experimental Investigation of CCFL in Pressurizer Surge Line with Air-Water

Tian, W.

Experimental and Theoretical Research on Liquid Entrainment in AP1000 ADS Blow-Down Phase of SBLOCA

Tian, W.X.

Experiment of Condensation in T-Junction: Steam-Water Flow in Water-Injected Condition

Tian, Wenxi

COPRA Experiments on Natural Convection Heat Transfer with High RAYLEIGH Numbers

Development of an In-Vessel Severe Accident Analysis Code MIDAC

Simulations of ECC Safety Injection for Single Phase and Stratified Phase Flow

Application of RPI Model: Prediction of Subcooled Boiling and DNB in Vertical Pipes

Theoretical Analysis of the Characteristics of Critical Heat Flux in Vertical Narrow Rectangular Channels Under Motion Conditions

Experimental and Numerical Investigation of Heat Transfer and Pressure Drop in Staggered Arrangement Helically Finned-Tube Bundle

Development of a Thermal-Mechanical-Material Behavior Analysis Code for the Dispersion-Plate-Type Fuel

Study on the Improvement of TOPAZ-II System by using a Heat Pipe Radiator

Tian, Z. F.

Research on Flow Characteristics for the Optimal Design of Experiment for the Typical Pressured Water Reactor

Tien, K.

Development, Validation and Assessment of the TRACE Thermal-Hydraulics Systems Code

Tien, Kirk

Experimental Study of Laminar Mixed Convection in a Rod Bundle with Mixing Vane Spacer Grids

Tkatschenko, I.

Plateau Facility in Support to ASTRID and the SFR Program: An Overview of the First Mock-Up of the ASTRID Upper Plenum MICAS

Tochio, Daisuke

Thermal Hydraulic Safety Research at JAEA after the Fukushima Dai-Ichi Nuclear Power Station Accident

Todd, Donald R.

Analytical Stability Analogue for a Single-Phase Natural Circulation Loop

Todreas, N.

Balance of Plant and Power Transmission for the Offshore Floating Nuclear Plant

Ocean-Based Passive Decay Heat Removal in the Offshore Floating Nuclear Plant (OFNP)

A Methodology for Characterizing Representativeness in Power Plant Performance Indicator Measurements with CFD Simulations

Tomboulides, A.

Erosion of a Large-Scale Gaseous Stratified Layer by a Turbulent Round Jet S—Simulations with URANS and LES Approaches

Tompkins, C.

Analytical Modeling of a Scaled Reactor Cavity Cooling System (RCCS) with Air

Temperature Profiles and Mixing in a Natural Circulation Cooling Facility via Distributed Optical Sensors

Tong, Lili

Assessment of Molten Pool Cooling Characteristics During LBLOCA for Advanced Passive PWR,

Torige, Toshihide

Development and Validation of A New Drift Flux Model in Rod Bundle Geometries

Torkhani, M.

Simulation of FARO L-28 and L-31 Tests to Assess Molten Jet Fragmentation Modeling in MAAP

Torró, S.

Local Parameters of Air-Water Two-Phase Flow at a Vertical T-Junction

Touazi, Ouardia

OSCARD Coupling Software for Main Steam Line Break Fault Analysis—Assessment of the Mixing Phenomena in the Vessel

Tran, C. T.

CFD Prediction of Subcooled Boiling with Advanced Mechanistic Models of Interfacial Area Transport Equation

Tran, Chi-Thanh

A Study on Transient Heat Transfer of the EU-ABWR External Core Catcher using the Phase-Change Effective Convectivity Model

Travis, John R.

Three Dimensional Scalable All-Speed CFD Code Gasflow-MPI: Applications to Turbulent Combustion of Premixed Hydrogen-Air Mixtures with Heat and Mass Transfer

Tryggvason, G.

DNS Assisted Modeling of Bubbly Flows in Vertical Channels

Tseng, Yung-Shin

Developments and Applications of TRACE/CFD Model of Maanshan PWR Pressure Vessel

Tummers, M. J.

Natural Convection Driven Heat Transfer in Fluids with Strongly Variable Properties: A Particle Image Velocimetry Study

U

Uchibori, A.

Numerical Investigation of Self-Wastage Phenomena in Steam Generator of Sodium-Cooled Fast Reactor

Uchibori, Akihiro

Development of a Mechanistic Evaluation Method for Wastage Environment Under Sodium-Water Reaction Accident

Uchida, Shunsuke

An Approach Toward Evaluation of FP Behaviors in NPPs Under Severe Accidents

Uddin, Rizwan

Investigation of Plenum-to-Plenum Heat Transfer and Gas Dynamics under Natural Circulation in a Scaled Down Dual Channel Module Mimicking Prismatic VHTR Core with using CFD

Umezawa, Shigemitsu

New AESJ Thermo-Hydraulics Roadmap for LWR Safety Improvement and Development after Fukushima-Daiichi Accident

Umminger, K.

Developments on High Pressure Two Phase Flow Measurement Techniques

Conclusions on Boron Precipitation following a Large Break Loss of Coolant Accident

Umminger, Klaus

Scaling Issues for the Experimental Characterization of Reactor Coolant System in Integral Test Facilities and Role of System Code as Extrapolation Pool

Uno, Y.

Qualification of CHF Test Facility at Stern Laboratories using Mitsubishi PWR Fuel

Usman, S.

Investigation of Plenum-to-Plenum Heat Transfer and Gas Dynamics under Natural Circulation in a Scaled Down Dual Channel Module Mimicking Prismatic VHTR Core with using CFD

Usov, E. V.

SOCRAT-BN Simulation of Siena Loss-of-Flow Experiments

Uspuras, E.

Integrated Assessment of Thermal Hydraulic Processes in W7-X Fusion Experimental Facility

Utgikar, Vivek P.

Fabrication and Testing of a High-Temperature Printed Circuit Heat Exchanger

V

Vaghetto, R.

MELCOR and GOTHIC Analyses of a Large Dry Pressurized Water Reactor Containment to Support Resolution of GSI-191

A Sensitivity Study Supporting Comparative Analysis of MELCOR and GOTHIC Large Dry Pressurized Water Reactor Containment Models

Vaghetto, Rodolfo

Experimental Observations of Boric Acid Precipitation Scenarios

The Effect of Electric Potential on Fibrous Debris Bypass Through a Containment Sump Strainer

Vaidheeswarn, A.

On Well-Posedness and Stability of the Two-Fluid Model for Vertical Bubbly Flows

Valentin, Francisco I.

Study of Abnormal Heat Transfer during Forced and Natural Convection Scenarios in a Prismatic Core of a VHTR: Numerical and Experimental Results

Valentin, Francisco Ivan

Role of Radiation Heat Transfer in Cooling of a Scaled Model of a Prismatic Graphite Core in a VHTR

Valori, V.

Natural Convection Driven Heat Transfer in Fluids with Strongly Variable Properties: A Particle Image Velocimetry Study

Van den Eynde, Gert

Natural Convection Driven Heat Transfer in Fluids with Strongly Variable Properties: A Particle Image Velocimetry Study

van der Hagen, T. H. J. J.

van Doesburg, W.

RELAP5 BWR-4 Model Development and Validation for NPP Mühleberg (KKM)

van Doesburg, Willem

Calculation of the Probability of DDT during Severe Accidents

van Heerden, E.

van Tichelen, K.

CFD Benchmark for a Heavy Liquid Metal Fuel Assembly

Tracking of Fuel Particles After Pin Failure in Nominal, Loss-of-Flow and Shutdown Conditions in the MYRRHA Reactor

Pre-Test Computational Fluid Dynamics and System Thermal Hydraulics Calculations of The E-SCAPE Scaled LBE Pool Facility

Van Tichelen, Katrien

Thermal-Hydraulic Study of the LBE-Cooled Fuel Assembly in the MYRRHA Reactor: Experiments and Simulations

Experimental Results from a Water Scale Model for the Thermal-Hydraulic Analysis of a HLM Reactor

Experimental Investigation of the Pressure Loss Characteristics of the Full-Scale MYRRHA Fuel Bundle in the COMPLOT LBE Facility

Influence of the 3-D Phenomena on the Safety Parameters during a ULOF Accident in the MYRRHA Reactor

CFD Simulations to Determine the Effects of Deformations on Liquid Metal Cooled Wire Wrapped Fuel Assemblies

Numerical Prediction of Flow Induced Vibrations in Nuclear Reactor Applications

van Zuijlen, A. H.

Vasiliev, A.

Computational Fluid Dynamics Analysis of the Fluid Flow and Heat Transfer in the Core Bypass Region of a PWR

Vedovi, J.

TRACG Analysis of Boiling Water Reactor Control Rod Drop Accident to Optimize Analysis Methodology

Vedovi, Juswald

TRACG Analysis and Results of Phase 1 of the OECD/NEA Oskarshamn-2 BWR Stability Benchmark

Vegendla, Prasad

Modeling of Two-Phase Flow in a BWR Fuel Assembly with a Highly-Scalable CFD Code

Velkov, K.

Uncertainty and Sensitivity Analysis of the OECD/NEA KALININ-3 Benchmark

Verdú, G.

Assessment of TRACE/PARCS Benchmark Against Leibstadt Plant Data During the Turbine Trip Test

Verdu, Gumersindo

Analysis of Kv in Power-to-Volume Scaling. Application to a SBLOCA Transient

Control Rod Drop Transient: Uncertainty and Sensitivity Analysis of Thermal-Hydraulic Variables using a 3D Model with TRACE V5.0P3/PARCS 3.0

Vezzoni, B.

EBR-II Passive Safety Demonstration Tests Benchmark Analyses—Phase 2

Viazzo, Stephane

Modeling of Fluctuating Fluid Forces Exerted on the Walls of a Concentric Annular Pipe Using Large Eddy Simulation

Vierendeels, J.

CFD Benchmark for a Heavy Liquid Metal Fuel Assembly

Vierow, K.

Experimental Investigation of Thermal Hydraulic Limits of BWR RCIC System Operation under Long-Term Operation

MELCOR and GOTHIC Analyses of a Large Dry Pressurized Water Reactor Containment to Support Resolution of GSI-191

A Sensitivity Study Supporting Comparative Analysis of MELCOR and GOTHIC Large Dry Pressurized Water Reactor Containment Models

Vierow, Karen

Effects of Steam-Water vs. Air-Water Fluid Pairs and Pressure on Flooding in Large Diameter Tubes

Vijayan, P. K.

A Supercritical Pressure Parallel Channel Natural Circulation Loop

Quenching of a Heated Rod: Physical Phenomena and Heat Transfer

Design of High Power Density Annular Fuel Rod Core for Advanced Heavy Water Reactor

Vijayan, Pallipatu Krishnan

Villanueva, Jose Felipe

Comparison of Some Approaches for the Estimation of Tolerance Limits in the Context of LBLOCA Uncertainty Analysis

Vimi, András

Extended Study of Coolability of VVER Bundle with Ballooned Region

Vinai, P.

Wall Superheat Prediction in Narrow Rectangular Channels Under Fully Developed Boiling of Water at Low Pressures

Vinogradova, Y. Y.

SOCRAT-BN Simulation of Siena Loss-of-Flow Experiments

Vishnoi, Alok Kumar

Design of High Power Density Annular Fuel Rod Core for Advanced Heavy Water Reactor

Visser, D. C.

Fluid-Structure Interaction in a Wire-Wrapped Rod Bundle Cooled with Supercritical Water

Hydrogen Risk Assessment—CFD Model Validation and Reactor Scale Application

Vitillo, F.

Experimental and Numerical Activities in Support of the Design of ASTRID Sodium-Gas Heat Exchanger

Vivaldi, Daniele

Numerical Modeling of the Two-Phase Underexpanded Reactive CO₂-into-Sodium Jets in the Frame of Sodium Nuclear Fast Reactors

Vives, Andrea Querol

Analysis of Kv in Power-to-Volume Scaling. Application to a SBLOCA Transient

Vogel, Klaus

Validation of AREVA’s Best Practices in the Round Robin CFD Benchmark

Volodzko, Michael

A Dynamic Model of Hydrostatic Reactor Coolant Pump Seals for RELAP5/MOD3.3

Volpenhein, Eric

Application of CD-ADAPCO Best Practices to NESTOR OMEGA MVG Benchmark Exercises Using STAR-CCM+

von der Cron, D.

Modeling of the Thermal Hydraulics of Very-High-Temperature Reactors with the System Code ATHLET

Vreeland, D. G.

TRACG Analysis of Boiling Water Reactor Control Rod Drop Accident to Optimize Analysis Methodology

Vreeland, David

TRACG Analysis and Results of Phase 1 of the OECD/NEA Oskarshamn-2 BWR Stability Benchmark

Vyskocil, Ladislav

CFD Simulation of the Departure from Nucleate Boiling

W

Wachowiak, Richard M.

Reactor Safety Gap Evaluation of Accident Tolerant Components and Severe Accident Analysis

Wachowiak, Richard

Wagner, Thomas

Large Scale BWR Containment LOCA Response Test at the INKA Test Facility

Waite, B. M.

Mechanistic Modeling of Two-Phase Flow Around Spacer Grids with Mixing Vanes

Waldemarsson, Fredrik

Detailed Measurements of Local Parameters in Annular Two-Phase Flow in Fuel Bundle under BWR Operating Conditions

High Resolution Thermal Mixing at Westinghouse ODEN Loop

Walker, Justin

Large-Scale Simulation of Nuclear Reactors: Issues and Perspectives

Walker, S. P.

Simulations of High-Pressure Subcooled Boiling Flows in Rectangular Channels

URANS Simulations of Thermal Stratification in a Large Enclosure for Severe Accident Scenarios

Validation and Cross-Verification of Three Mechanistic Codes for Annular Two-Phase Flow Simulation and Dryout Prediction

Interface Tracking Based Evaluation of Bubble Growth Rates in High Pressure Pool Boiling Conditions

Quenching of a Heated Rod: Physical Phenomena and Heat Transfer

CFD and Experimental Analysis of Single Phase Buoyancy Driven Counter-Current Flow in a Pipe

Walker, Simon P.

Walker, Simon Peter

Microlayer Models for Nucleate Boiling Simulations: The Significance of Conjugate Heat Transfer

Walker, Simon

Numerical Study of Heat Diffusion Controlled Bubble Growth in a Pressurised Liquid

Walter, Daniel J.

A Control Theory Approach to Adaptive Stepsize Selection for Coupled CFD and CRUD Chemistry Simulations

Walther, Markus

Experimental and Numerical Investigation of Flow Structure and Heat Transfer During High Pressure Condensation in a Declined Pipe at COSMEA Facility

Wang, Chenglong

Three-Dimensional Thermal Hydraulic Analysis of a Transportable Fluoride-Salt-Cooled High-Temperature Reactor

Wang, Chi

Unprotected Transient Analyses of Natural Circulation LBE-Cooled Accelerator Driven Sub-Critical System

Wang, Gang

Wang, Haidan

Requirements Analysis and Research of Severe Accident Process Simulation Based on COS-SA Code and Emergency Decision Support

Wang, Han

ADS-IRWST Transient Evaluation Model for AP1000 SBLOCA Analysis

Wang, Hong-Yan

Numerical Simulation on Melting and Solidification Based on Lagrangian Approach

Wang, J. R.

The Analysis of TRACE/FRAPTRAN in Ultimate Response Guideline for Lungmen ABWR Nuclear Power Plant

Wang, Jong-Rong

Assessment of Station Blackout Mitigation Strategy Applying the Ultimate Response Guideline to MAANSHAN PWR

Methodology using MELCOR2.1/SNAP to Establish an SBO Model of Chinshan BWR/4 Nuclear Power Plant

Developments and Applications of TRACE/CFD Model of Maanshan PWR Pressure Vessel

Wang, Jun

PHEBUS FPT-1 Simulation, using MELCOR: Blockage Model Analysis

Wang, Junfeng

Experimental and Numerical Investigation on Single Air Bubble Rising in Narrow Rectangular Channel

Development Heat Transfer Correlations for Supercritial CO2 in Natural Circulation Loop

Wang, Kai

Simulations of ECC Safety Injection for Single Phase and Stratified Phase Flow

Wang, Ke

An Experimental Study on the Dynamics of a Liquid Film Under Shearing Force and Thermal Influence

Wang, Li

Numerical Solution of Heat Transfer Process in a Prismatic VHTR Considering Core Bypass Flow and Cross Flow

Wang, Mingjun

Passive Decay Heat Removal System Design for the Integral Inherent Safety Light Water Reactor (I²S-LWR)

Preliminary Design of the I²S-LWR Containment System

Wang, N.X.

Flow Characterization within a Sphere-Packed Bed using PIV Measurement

Wang, Naxiu

Preliminary Analysis of the Afterheat Removal in Pebble Bed Fluoride Salt Cooled High Temperature Reactors Under Accident Conditions

Numerical Prediction of Turbulent Convective Heat Transfer with Molten Salt in Circular Pipe

Wang, Shisheng

A New Lumped Thermal Resistance Heat Transfer Model for Fuel Pin Structure

Wang, Sipeng

Heat Loss Simulation and Uncertainty Analysis in Fuel Bundle CHF and Other Large Scale Thermal-Hydraulic Experiments

Wang, Steven Keijers

MyrrhaFoam: A CFD Model for the Study of the Thermal Hydraulic Behavior of MYRRHA

Wang, Shumiao

Comparison Analysis of CHF Parametric Trends in Vertical Tubes and 5x5 Bundle

Wang, W.

A Natural Circulation Experiment of Passive Residual Heat Removal Heat Exchanger for AP1000

Wang, W

Direct Numerical Simulation of Fluid Flow at Supercritical Pressure in a Vertical Channel

Wang, Xianmao

Analysis of Wave Influence on Steam Condensation with Non-Condensable Gases Using CFD

Wang, Y.-J.

Development of a Post-Dryout Heat Transfer Model

Wang, Yan

Study of the Influence of the Design Parameters and Initial Condition of Passive Containment Cooling System

Wang, Yanlin

Experimental and Numerical Investigation on Single Air Bubble Rising in Narrow Rectangular Channel

Wang, Z.W.

Experimental Investigation of CCFL in Pressurizer Surge Line with Air-Water

Wang, Zhen

Unprotected Transient Analyses of Natural Circulation LBE-Cooled Accelerator Driven Sub-Critical System

Watanabe, T.

Numerical Study on Modeling of Liquid Film Flow under Countercurrent Flow Limitation in Volume of Fluid Method

Watanabe, Tadashi

Effects of ECCS on the Cold-Leg Fluid Temperature during SGTR Accidents

Weathered, T.

Development of Optical Fiber Instrumentation for use in Sodium Cooled Fast Reactors Matthew

Weaver, W. L.

Heat Transfer Regime Calibration for Phase-Change Heat Exchangers in RELAP5-3D

Wei, Lu

Effects of Additives on CHF Behaviors for ERVC-IVR Strategy with FIRM Facility

Weichselbaum, Noah A.

Surrogate Spacer Grid Design for Fluid-Structure Interactions Studies in Fuel Bundles

Wells, Daniel M.

Overview of CFD Round Robin Benchmark of the High Fidelity Fuel Rod Bundle NESTOR Experimental Data

Wellstein, Leslie F.

Impact of Flow Induced Vibration Acoustic Loads on the Design of the Peach Bottom Replacement Steam Dryer

Westerweel, J.

Natural Convection Driven Heat Transfer in Fluids with Strongly Variable Properties: A Particle Image Velocimetry Study

Wetzel, Thomas

Thermal-Hydraulic Study of the LBE-Cooled Fuel Assembly in the MYRRHA Reactor: Experiments and Simulations

Whitman, J.

Development, Validation and Assessment of the TRACE Thermal-Hydraulics Systems Code

Wi, Myung-Hwan

Numerical Studies of O₂ Leak Modeling in Sodium-CO₂ Heat Exchanger in the SFR Coupled with the S-CO₂ Brayton Cycle

Wicaksono, Damar Canggih

A Methodology for Global Sensitivity Analysis of Transient Code Output Applied to a Reflood Experiment Model using TRACE

Widenfeld, G.

The Effect of Thermal Conditions and Jet Properties on Steam Explosion

Wieckhorst, Ole

ORFEOTM—A CHF Correlation Form Applied to GAIA, AREVA’s Advanced PWR Fuel Assembly Design

Willermoz, Guy

Needs for Large Mass Phototype Corium Experiments: The PLINIUS-2 Platform

Williams, Cody

Overview of the Flume Integral Effects and Separate Effects Testing and Analysis (FIESTA) Facility for Investigating Containment Debris Transport and Sump Strainer Head Loss

Williams, Wesley C.

Using NASA’s GFSSP Code for Steady State and Transient Modeling of Gas Cooled Reactor Passive Safety Systems

Williamson, R. L.

Anisotropic Azimuthal Power and Temperature Distribution as a Driving Force for Hydrogen Redistribution

Wilson, D.

Experimental Study of DRACS Thermal Performance in a Low-Temperature Test Facility

Windberg, Péter

Extended Study of Coolability of VVER Bundle with Ballooned Region

Wolf, B.

Woo, Hyeon Seok

Flow Mixing Characteristics in Subchannels of a Wire-Wrapped 61-Pin Rod Assembly for a Sodium-Cooled Fast Reactor

Woods, Brian

Graphite Oxidation Rates in Comparison to Regimes with Application to the Oregon State Over University High Temperature Test Facility

Wright, Richard F.

Analysis of the AP1000® Passive Containment Cooling System Air Flow Path Using Computational Fluid Dynamics

Wu, Guanghao

Experimental Investigation on Transient Heat Transfer Characteristics of C-Shape Heating Rod Bundle used in PRHR HX

Wu, Huali

Characterization of Tritium Transport in the FLibe-Graphite System, for In-Situ Tritium Absorption by the Fuel Elements of the Fluoride-Salt-Cooled High-Temperature Reactor (FHR)

Wu, Qiao

Development of a Mechanistic Critical Heat Flux Correlation

Wu, Xiao

Conceptual Design of Tritium Removal Facility for FHRs

Wu, Yao

Experimental Study of Pressure Drop and Modelling of Interfacial Shear for Vertical Annular Flow

Wu, Yican

Experimental Study on Natural Circulation and Gas Injection Enhanced Circulation in KYLIN-II Mixed Circulation Loop

Wu, Yingwei

Experimental and Numerical Investigation of Heat Transfer and Pressure Drop in Staggered Arrangement Helically Finned-Tube Bundle

Development of a Thermal-Mechanical-Material Behavior Analysis Code for the Dispersion-Plate-Type Fuel

An Updated Approach to the Prediction of Dryout and Void Fraction for RBWR Bundles

Wyble, James, III

Computational Fluid Dynamics Assessment of Emergency Core Cooling System Check Valves at Comanche Peak

Wysocki, Aaron

A Physical Mechanism for Rotating Lines of Symmetry in BWR Out-of-Phase Limit Cycle Oscillations

X

Xi, Mengmeng

Theoretical Analysis of the Characteristics of Critical Heat Flux in Vertical Narrow Rectangular Channels Under Motion Conditions

Xi, Zhao

Evaluation of RELAP5/MOD3.2 for ACP1000 Passive Residual Heat Removal System

Xian-Gang, Fu

Study on CHF Correlation for PWR at Low Pressure Conditions Based on Stepwise Regression Analysis

Xian, Lin

Natural Convective Heat Transfer from a Heated Slender Vertical Tube in a Cylindrical Tank

Xiang, Y.

Experimental and Theoretical Research on Liquid Entrainment in AP1000 ADS Blow-Down Phase of SBLOCA

Xiangyin, Kong

Study on CHF Correlation for PWR at Low Pressure Conditions Based on Stepwise Regression Analysis

Xiao, Jianjun

Three Dimensional Scalable All-Speed CFD Code Gasflow-MPI: Applications to Turbulent Combustion of Premixed Hydrogen-Air Mixtures with Heat and Mass Transfer

Xie, Heng

Comparison and Analysis on Integral Small Modular Reactor with Two Different ESF Designs Response to Postulated Events

Xie, Shijie

Research on Critical Heat Flux of PWR Fuel Assembly in NPIC

Xiong, Jin-Biao

Numerical Simulation on Melting and Solidification Based on Lagrangian Approach

Xiong, L.

Flow Characterization within a Sphere-Packed Bed using PIV Measurement

Xiong, Wanyu

Study on Critical Heat Flux with Non-Uniform Axial Heat Flux Distributions During Lifetime in Reactor Core

Xiong, Xiaofei

Analysis of the SBLOCA on the Improved CPR1000 with Passive Systems

Improvement and Validation of the Wall Heat Transfer Package of RELAP5/MOD3.3

Xu, Bo

Core Exit Thermocouple Response to Inadequate Core Cooling Using CFD Dynamic Mesh

Xu, Hong

Xu, Hongjie

A Specialized Thermal-Hydraulic Code with Porous Media Model and SIMPLEC Algorithm for PB-FHRs

Xu, Y.

Use of CFD to Predict Critical Heat Flux in Rod Bundles

Xu, Yiban

Computational Fluid Dynamics Benchmark using AP1000^®1/4-Scale Upper Head Test Data

Westinghouse CFD Modeling and Results for EPRI NESTOR CFD Round Robin Exercise of PWR Rod Bundle Testing

CFD Evaluation of OECD PSBT Geometry Effects Based on Fluid Temperature Measurements

Y

Yadigaroglu, George

Nuclear Safety and Thermal Hydraulics: Personal Thoughts and Some Recent Progress

Yagnik, Suresh Kumar

Overview of CFD Round Robin Benchmark of the High Fidelity Fuel Rod Bundle NESTOR Experimental Data

Yakush, S E.

Experimental Investigation of Debris Bed Agglomeration and Particle Size Distribution using WO3-ZRO2 Melt

Yakush, S. E.

Effect of Particle Spreading on Coolability of Ex-Vessel Debris Bed

Yamada, D.

Recent Findings on the Damaged Reactors and Containment Vessels of Fukushima Dai-ichi NPS

Yamada, Fumiaki

Safety Margins after Failure of Fuel Cladding during Protected Loss-of-Heat-Sink Accidents in a Sodium-Cooled Fast Reactor

Yamada, Minoru

Development and Validation of A New Drift Flux Model in Rod Bundle Geometries

Yamaguchi, A.

Numerical Study on Modeling of Liquid Film Flow under Countercurrent Flow Limitation in Volume of Fluid Method

Numerical Investigation of Self-Wastage Phenomena in Steam Generator of Sodium-Cooled Fast Reactor

Yamaguchi, Akira

New AESJ Thermo-Hydraulics Roadmap for LWR Safety Improvement and Development after Fukushima-Daiichi Accident

Yamaji, Akifumi

Numerical Simulation of Anisotropic Ablation of Siliceous Concrete—Analysis of CCI-3 MCCI Experiment by MPS Method

Analysis of Metal Vessel Wall Ablation Experiment with High Temperature Liquid by MPS Method

Yamanaka, Y.

Recent Findings on the Damaged Reactors and Containment Vessels of Fukushima Dai-ichi NPS

Yamauchi, D.

Recent Findings on the Damaged Reactors and Containment Vessels of Fukushima Dai-ichi NPS

Yan, Xiao

Numerical Simulations of Turbulent Mixing Factor in 2x2 Rod Bundles at Supercritical Pressures

Yang, Bao-Wen

Heat Loss Simulation and Uncertainty Analysis in Fuel Bundle CHF and Other Large Scale Thermal-Hydraulic Experiments

Trend Analysis for Low Pressure Low Flow Tube CHF

Improvement of Mixing Vane Crossflow Model in Subchannel Analysis

Numerical Study on the Effects of Vane Angle and Dimple on the Thermal Hydraulic Performance of a PWR Fuel Assembly

Yang, Baowen

Heat Loss Evaluation in Large Scale Rod Bundle CHF Experiments

Yang, C.

Critical Heat Flux with Subcooled Flowing Water in Tubes for Pressures from Atmosphere to Near-Critical Point

Yang, J.

TRACG Analysis of Boiling Water Reactor Control Rod Drop Accident to Optimize Analysis Methodology

Yang, Jin-Hwa

Assessment of Multi-Dimensional Component of Mars with Air-Water Cross Flow Experiment

Yang, Jung-Hua

Developments and Applications of TRACE/CFD Model of Maanshan PWR Pressure Vessel

Yang, Lin

Experimental Methods of the PCCS Containment Wall Condensation with Non-Condensable Gas

Yang, Liu

Experimental Research on Non-Condensable Gases Effects in Passive Decay Heat Removal System

Yang, Q. R.

Experimental and Numerical Study on Heat Transfer of Supercritical Water Flowing Upward in 2x2 Rod Bundles

Yang, Rosa L.

Experimental Stability Maps for a BWR-Type Small Modular Reactor

Yang, Won Sik

Yang, Y. H.

Status and Challenges of Nuclear Thermal-Hydraulics Research in China

Yang, Yan-Hua

Numerical Simulation on Melting and Solidification Based on Lagrangian Approach

Yang, Yang

Loss of Coolant Flow Accident Analysis for Fluoride Salt Cooled High Temperature Reactor

Disturbed Transient Analysis with Stable Operation Mode of TMSR-SF1

Yang, Yanning

Study of the Influence of the Design Parameters and Initial Condition of Passive Containment Cooling System

Yang, Zijiang

Thermal-Hydraulic Design and Transient Analysis of Passive Air Cooling System for CPR1000 Spent Fuel Storage Pool

Analysis of the SBLOCA on the Improved CPR1000 with Passive Systems

Typical Accidents Analysis on the Loss of Flow and External Neutron Source Changing Accidents for a 800 MWth ADS

Yang, Zumao

Study on Critical Heat Flux with Non-Uniform Axial Heat Flux Distributions During Lifetime in Reactor Core

Yarsky, Peter

TRACE/PARCS Analysis of ATWS with Instability for a MELLLA+ BWR/5

Use of White Noise in TRACE/PARCS Analysis of ATWS with Instability

Axial Conduction Nodalization for TRACE/PARCS Analysis of ATWS with Instability Peter Yarsky, Matthew Hardgrove (NRC)

Sensitivity to T_MIN in TRACE/PARCS Analysis of ATWS with Instability

Yeom, Sujin

Experimental Evaluation on Sodium-to-Air Heat Exchanger Performance for PGSFR Design Code Validation

Yi, Kunwoo

Thermal Hydraulic Analysis in Reactor Vessel Internals Considering Irradiation Heat

Yi, Sung-Jae

An SBLOCA Test of Pressurizer Safety Valve Line Break with the SMART-ITL Facility and its MARS-KS Code Simulation

Yilmaz, Fatma

RoverD: Use of Test Data in GSI-191 Risk Assessment

Yilmaz, Mine Ozdemir

Development of Burnup Dependent Fuel Rod Model in CTF

Yilmaz, Mine

Analysis of Improved Fuel Rod Modeling in Coupled Thermal-Hydraulics/Neutronics Calculations

Yin, S. H.

Numerical Calculation of the Heat Transfer Characteristics of Fuel Cladding with Dirt at Low Coolant Speed

Yiqiang, Xiong

Requirements Analysis and Research of Severe Accident Process Simulation Based on COS-SA Code and Emergency Decision Support

Ylonen, Arto

Study of Two-Phase Pipe Flow using the Axial Wire-Mesh Sensor

Yoder, G.

Thermal Hydraulic Benchmarking Exercises to Support Fluoride-Salt-Cooled, High-Temperature Reactor (FHR) Licensing

Experimental Study of DRACS Thermal Performance in a Low-Temperature Test Facility

Yokomine, Takehiko

Experimental Study of Annular Two-Phase Flow on Rod-Bundle Geometry with Spacer

Subcooled Boiling-Induced Vibration of a Single Heater Rod Confined with Metallic Walls

Yonomoto, Taisuke

Thermal Hydraulic Safety Research at JAEA after the Fukushima Dai-Ichi Nuclear Power Station Accident

Yoon, Dhongik

Assessment of the MELCOR and RELAP5-3D Code for Condensation in the Presence of Noncondensable Gas

Yoon, Han Young

Multi-Scale Thermal-Hydraulic Analysis of Safety Systems of Advanced PWRs using the CUPID Code

You, Byung-Hyun

RANS Simulation of Turbulent Swept Flow over a Wire in a Channel for Core Thermal Hydraulic Design

Youn, Young Jung

Experimental Evaluation of Local Bubble Parameters of Subcooled Boiling Flow in a Pressurized Vertical Annulus Channel

Young, Michael Charles

Characterization of Tritium Transport in the FLibe-Graphite System, for In-Situ Tritium Absorption by the Fuel Elements of the Fluoride-Salt-Cooled High-Temperature Reactor (FHR)

Youngblood, Robert

10 CFR 50.46c Rulemaking: A Novel Approach in Restating the LOCA Problem for PWRs

Development of a Societal-Risk Goal for Nuclear Power Safety

Yu, G.J.

Experiment of Condensation in T-Junction: Steam-Water Flow in Water-Injected Condition

Yu, Hongxing

Natural Convective Heat Transfer from a Heated Slender Vertical Tube in a Cylindrical Tank

Yu, J. T.

Experimental Investigation of CCFL in Pressurizer Surge Line with Air-Water

Yu, Jiangtao

Experimental and Numerical Investigation of Heat Transfer and Pressure Drop in Staggered Arrangement Helically Finned-Tube Bundle

Yu, Xiaohan

Pseudo 3-D Full-Core Conjugate Heat Transfer Modeling of Sodium Fast Reactors

Yu, Yiqi

Large-Scale Simulation of Nuclear Reactors: Issues and Perspectives

Steady and Unsteady Calculations on Thermal Striping Phenomena in Triple-Parallel Jet

Yuan, Haomin

Experimental and Numerical Study of Valves for Supercritical Carbon Dioxide BRAYTON Cycle

Yuan, Yin

Study on CHF Correlation for PWR at Low Pressure Conditions Based on Stepwise Regression Analysis

Yuan, Yuan

Study on Startup Characteristics of Heat Pipe Cooled Space Reactor

Typical Accidents Analysis on the Loss of Flow and External Neutron Source Changing Accidents for a 800 MWth ADS

Accident Analysis of Heat Pipe Cooled Space Reactor

Yuanbing, Zhu

Study on CHF Correlation for PWR at Low Pressure Conditions Based on Stepwise Regression Analysis

Yue, Chenchong

Experimental Study on Natural Circulation and Gas Injection Enhanced Circulation in KYLIN-II Mixed Circulation Loop

Yurko, J. P.

On the Definition of a Minimum Set of Requirements to Assess the Adequacy of the RELAP5-3D Multidimensional Flow Capability with Selected Canonical Problems

On the Level of Approximation of the Multi-Dimensional Potential Flow Solution in Complex Geometries with Thermal-Hydraulic System Codes

Yurko, Joseph P.

10 CFR 50.46c Rulemaking: A Novel Approach in Restating the LOCA Problem for PWRs

Experimental Test Facility Data Synthesis with the Dynamical System Scaling Methodology

Demonstration of Test Facility Design Optimization with the Dynamical System Scaling Methodology

The Dynamical System Scaling Methodology: Comparing Dimensionless Governing Equations with the H2TS and FSA Methodologies

Z

Zaki, Tarek

Use of White Noise in TRACE/PARCS Analysis of ATWS with Instability

Zan, Yuanfeng

Experimental and Numerical Investigation on Single Air Bubble Rising in Narrow Rectangular Channel

Study on Critical Heat Flux with Non-Uniform Axial Heat Flux Distributions During Lifetime in Reactor Core

Zang, Jinguang

Numerical Simulations of Turbulent Mixing Factor in 2x2 Rod Bundles at Supercritical Pressures

Zanino, R.

EBR-II Passive Safety Demonstration Tests Benchmark Analyses—Phase 2

Zavaleta, Pascal

A First Orienting Investigation of the Interaction of Cable Fire Products with Passive Auto-Catalytic Recombiners (PARs)

Zeng, Xiaokang

Numerical Simulations of Turbulent Mixing Factor in 2x2 Rod Bundles at Supercritical Pressures

Zerkak, O.

Towards a Consolidated Approach for the Validation of Plant System Codes and Models: Case Study for a BWR Fast Depressurization Event

Ranking of Uncertain Parameters for Dynamic Event Tree Analysis: A Case Study based on a Station Blackout Scenario

Computational Fluid Dynamics Analysis of the Fluid Flow and Heat Transfer in the Core Bypass Region of a PWR

Zerkak, Omar

A Methodology for Global Sensitivity Analysis of Transient Code Output Applied to a Reflood Experiment Model using TRACE

Assessment of OpenFOAM CFD Toolbox for Gravity driven Turbulent Mixing Flows in a Reactor Pressure Vessel

TRACE/SIMULATE-3K Analysis of the NEA/OECD Oskarshamn-2 Stability Benchmark

Zha, Yudong

Heat Loss Simulation and Uncertainty Analysis in Fuel Bundle CHF and Other Large Scale Thermal-Hydraulic Experiments

Trend Analysis for Low Pressure Low Flow Tube CHF

Zhang, Bin

Thermal-Hydraulic Design and Transient Analysis of Passive Air Cooling System for CPR1000 Spent Fuel Storage Pool

Study on Startup Characteristics of Heat Pipe Cooled Space Reactor

Typical Accidents Analysis on the Loss of Flow and External Neutron Source Changing Accidents for a 800 MWth ADS

Accident Analysis of Heat Pipe Cooled Space Reactor

Numerical Study on the Effects of Vane Angle and Dimple on the Thermal Hydraulic Performance of a PWR Fuel Assembly

Zhang, Bo

Thermal-Hydraulic Design and Transient Analysis of Passive Air Cooling System for CPR1000 Spent Fuel Storage Pool

Comparison Analysis of CHF Parametric Trends in Vertical Tubes and 5x5 Bundle

Study on Startup Characteristics of Heat Pipe Cooled Space Reactor

Typical Accidents Analysis on the Loss of Flow and External Neutron Source Changing Accidents for a 800 MWth ADS

Implementation of Strong Implicit Procedure for the Energy Equations in Subchannel Code ATHAS

Heat Loss Evaluation in Large Scale Rod Bundle CHF Experiments

Accident Analysis of Heat Pipe Cooled Space Reactor

Improvement of Mixing Vane Crossflow Model in Subchannel Analysis

Zhang, D. L.

Experimental Investigation of CCFL in Pressurizer Surge Line with Air-Water

Zhang, Dalin

Three-Dimensional Thermal Hydraulic Analysis of a Transportable Fluoride-Salt-Cooled High-Temperature Reactor

Development of a Thermal-Mechanical-Material Behavior Analysis Code for the Dispersion-Plate-Type Fuel

Zhang, Guomin

Analysis of the SBLOCA on the Improved CPR1000 with Passive Systems

Zhang, Guoxu

Comparison and Analysis on Integral Small Modular Reactor with Two Different ESF Designs Response to Postulated Events

Zhang, Hongbin

A Strongly Coupled Reactor Core Isolation Cooling System Model for Extended Station Blackout Analyses

On the Analytical Solutions and Numerical Verifications of Two-Phase Water Faucet Problem

Zhang, Hui

Heat Loss Evaluation in Large Scale Rod Bundle CHF Experiments

Numerical Study on the Effects of Vane Angle and Dimple on the Thermal Hydraulic Performance of a PWR Fuel Assembly

Zhang, Huimin

Investigation of Operational Charactistics of Passive Containment Cooling System for an Advanced PWR

Melcor Analysis of Early Containment Venting Risk in a Severe Accident Scenario of Boiling Water Reactor

Zhang, J.

Ocean-Based Passive Decay Heat Removal in the Offshore Floating Nuclear Plant (OFNP)

Zhang, Jie

Loss of Coolant Flow Accident Analysis for Fluoride Salt Cooled High Temperature Reactor

Disturbed Transient Analysis with Stable Operation Mode of TMSR-SF1

A Specialized Thermal-Hydraulic Code with Porous Media Model and SIMPLEC Algorithm for PB-FHRs

Zhang, Junyi

Research on Critical Heat Flux of PWR Fuel Assembly in NPIC

Zhang, Lei

An Experimental Study of Air-Water Pool Entrainment in High Gas Flux Region

Zhang, Liqin

Experimental and Numerical Investigation on Single Air Bubble Rising in Narrow Rectangular Channel

Zhang, Luteng

COPRA Experiments on Natural Convection Heat Transfer with High RAYLEIGH Numbers

Zhang, Ming

CHF Experiment of RPV Lower Head with Real Surface Material for ERVC-IVR Strategy

Zhang, P.

Experimental and Theoretical Research on Liquid Entrainment in AP1000 ADS Blow-Down Phase of SBLOCA

Zhang, Peng

An Experimental Study of Air-Water Pool Entrainment in High Gas Flux Region

Zhang, Rui

Application of RPI Model: Prediction of Subcooled Boiling and DNB in Vertical Pipes

Zhang, Weizhong

Numerical Simulation of Air Natural Circulation and Thermal Radiation in Passive Containment System

Zhang, Wenwen

Application of RPI Model: Prediction of Subcooled Boiling and DNB in Vertical Pipes

Study on the Improvement of TOPAZ-II System by using a Heat Pipe Radiator

Zhang, X. Y.

CFD Analysis of Flowing Field in 5x5 Rod Bundle with Multi-Grids

Zhang, X. Y.

Numerical Calculation of the Heat Transfer Characteristics of Fuel Cladding with Dirt at Low Coolant Speed

Zhang, X.

Preliminary Structural Assessment of a Printed Circuit Heat Exchanger with S-Shaped Fins

Zhang, Yaoli

Study of the Influence of the Design Parameters and Initial Condition of Passive Containment Cooling System

Zhang, Yapei

COPRA Experiments on Natural Convection Heat Transfer with High RAYLEIGH Numbers

Development of an In-Vessel Severe Accident Analysis Code MIDAC

Zhang, Youjia

An Experimental Study on the Dynamics of a Liquid Film Under Shearing Force and Thermal Influence

Zhang, Yuhao

Experimental Investigation on Transient Heat Transfer Characteristics of C-Shape Heating Rod Bundle used in PRHR HX

Zhang, Z. J.

Research on Flow Characteristics for the Optimal Design of Experiment for the Typical Pressured Water Reactor

Zhao, Dawei

Study on Critical Heat Flux with Non-Uniform Axial Heat Flux Distributions During Lifetime in Reactor Core

Zhao, Haihua

A Strongly Coupled Reactor Core Isolation Cooling System Model for Extended Station Blackout Analyses

On the Analytical Solutions and Numerical Verifications of Two-Phase Water Faucet Problem

Zhao, J. B.

CFD Analysis of Flowing Field in 5x5 Rod Bundle with Multi-Grids

Zhao, M.

Experimental and Numerical Study on Heat Transfer of Supercritical Water Flowing Upward in 2x2 Rod Bundles

Critical Heat Flux with Subcooled Flowing Water in Tubes for Pressures from Atmosphere to Near-Critical Point

Zhao, Wei

Experimental Methods of the PCCS Containment Wall Condensation with Non-Condensable Gas

Zhao, Xingang

An Updated Approach to the Prediction of Dryout and Void Fraction for RBWR Bundles

Zheng, M. Y.

Experimental and Numerical Investigation of Heat Transfer and Pressure Drop in Staggered Arrangement Helically Finned-Tube Bundle

Zhezherun, A.

A CFD Approach to Spacer Grid Optimization for Improved Dryout Performance in BWR Fuel Bundle

Zhou, M.

Unsteady Void Measurements Within Debris Beds using High Speed X-Ray Tomography

Zhou, Qing

Assessment of OpenFOAM CFD Toolbox for Gravity driven Turbulent Mixing Flows in a Reactor Pressure Vessel

Zhou, Quan

Enhancements in MAAP5.03+ MCCI and Corium Coolability Models and Benchmarks against OECD CCI Tests

Experimental Methods of the PCCS Containment Wall Condensation with Non-Condensable Gas

Zhou, Shan

Zhou, Tao

Thermal-Hydraulic Design and CFD Analysis of Fuel Assembly for China Lead-Based Research Reactor

Zhou, W.

Flow Characterization within a Sphere-Packed Bed using PIV Measurement

Zhou, Wen

Preliminary Analysis of the Afterheat Removal in Pebble Bed Fluoride Salt Cooled High Temperature Reactors Under Accident Conditions

Zhou, Yukun

COPRA Experiments on Natural Convection Heat Transfer with High RAYLEIGH Numbers

Zhou, Z. W.

Assessment Study of RELAP5/SCDAP Capability to Reproduce Liquid Metal Tall Facility Thermal Hydraulic Behaviour

Zhou, Zhiwei

Study of the Influence of the Design Parameters and Initial Condition of Passive Containment Cooling System

Concept Design and Thermal-Hydraulic Analysis for Helium-Cooled ADS

Zhu, Y. B.

Verification and Validation of a Fuel-Rod Temperature Analysis Code-BIRCH

Zhuo, Wenbin

Research on Critical Heat Flux of PWR Fuel Assembly in NPIC

Zhuohua, Zhang

Model Development of UO2-ZR Plate Fuel Behavior at Early Phase of Severe Accident and Molten Fuel Meat Relocation

Zidouni, F.

Analysis and Applications of a Generalized Multi-Field Two Fluid Approach for Plunging Jet Configuration

Ziegenhein, T.

Status and Challenges of CFD-Modelling for Poly-Disperse Bubbly Flows

Ziskind, G.

Nuclear Reactor Containment Flows—Modelling of Stably Stratified Layer Erosion by a Turbulent Jet

Zolan, Alex

RoverD: Use of Test Data in GSI-191 Risk Assessment

Zou, Ling

A Strongly Coupled Reactor Core Isolation Cooling System Model for Extended Station Blackout Analyses

On the Analytical Solutions and Numerical Verifications of Two-Phase Water Faucet Problem

Zou, Xumao

An Experimental Study on Flow Characteristics of Homogeneous and Stratified Debris Beds

Zou, Yaheng

An Experimental Study of Air-Water Pool Entrainment in High Gas Flux Region

Zou, Yang

Loss of Coolant Flow Accident Analysis for Fluoride Salt Cooled High Temperature Reactor

Disturbed Transient Analysis with Stable Operation Mode of TMSR-SF1

A Specialized Thermal-Hydraulic Code with Porous Media Model and SIMPLEC Algorithm for PB-FHRs