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Journal Articles

System Thermal-hydraulics Model for Fluoride Salt-Cooled Reactor Based On Small Advanced High Temperature Reactor (smAHTR) Design Concept

Shu Jun Wang, Xianmin Huang, Blair Bromley

ASME J of Nuclear Rad Sci.

Paper No: NERS-23-1011

DOI: https://doi.org/10.1115/1.4062500

Published Online: May 5, 2023

View Article titled, System Thermal-hydraulics Model for Fluoride Salt-Cooled Reactor Based On Small Advanced High Temperature Reactor (smAHTR) Design Concept

Topics: Design, High temperature, Thermal hydraulics, Fuels, Coolants, Temperature, Cycles, Engineering simulation, Flow (Dynamics), Simulation

Journal Articles

Investigation Into Hybridization of the Two-Fluid Model and Phase-Field Model for Multi-Scale Two-Phase Flow Simulations

Akinori Tamura, Kenichi Katono

ASME J of Nuclear Rad Sci. July 2023, 9(3): 031404.

Paper No: NERS-22-1052

DOI: https://doi.org/10.1115/1.4055932

Published Online: February 8, 2023

View Article titled, Investigation Into Hybridization of the Two-Fluid Model and Phase-Field Model for Multi-Scale Two-Phase Flow Simulations

Topics: Bubbles, Bubbly flow, Fluids, Pressure, Simulation, Plumes (Fluid dynamics), Porosity, Surface tension, Flow (Dynamics), Two-phase flow

Journal Articles

Introducing Passive Nuclear Safety in Water-Cooled Reactors: Numerical Simulation and Validation of Natural Convection Heat Transfer and Transport in Packed Beds of Heated Microspheres

Olugbenga O. Noah, Johan F. Slabber, Josua P. Meyer

ASME J of Nuclear Rad Sci. July 2023, 9(3): 031403.

Paper No: NERS-22-1020

DOI: https://doi.org/10.1115/1.4056239

Published Online: February 8, 2023

View Article titled, Introducing Passive Nuclear Safety in Water-Cooled Reactors: Numerical Simulation and Validation of Natural Convection Heat Transfer and Transport in Packed Beds of Heated Microspheres

Topics: Fluids, Heat transfer, Particulate matter, Simulation, Temperature, Flow (Dynamics), Design, Fuels, Safety, Natural convection

Journal Articles

Pearson Correlation and Chi-Squared Methods Applied to the Sensitivity and Uncertainty Analysis of Hydrogen Generation During a BWR STSBO Using MAAP5 and AZTUSIA

Javier Ortiz-Villafuerte, Heriberto Sanchez-Mora, Cesar Queral, Melisa Reyes-Fuentes, Edmundo del-Valle-Gallegos

ASME J of Nuclear Rad Sci.

Paper No: NERS-22-1021

DOI: https://doi.org/10.1115/1.4055011

Published Online: July 15, 2022

View Article titled, Pearson Correlation and Chi-Squared Methods Applied to the Sensitivity and Uncertainty Analysis of Hydrogen Generation During a BWR STSBO Using MAAP5 and AZTUSIA

Topics: Boiling water reactors, Hydrogen, Uncertainty analysis, Accidents, Simulation, Explosions, Cladding systems (Building), Failure, Fukushima nuclear disaster, Japan, 2011, Nuclear power stations

Journal Articles

Coupling of ASTEC V2.1 and RASCAL 4.3 Codes to Evaluate the Source Term and the Radiological Consequences of a Loss-of-Cooling Accident at a Spent Fuel Pool

Antonio Guglielmelli, Stefano Ederli, Fulvio Mascari, Federico Rocchi, Pietro Maccari

ASME J of Nuclear Rad Sci. October 2022, 8(4): 041602.

Paper No: NERS-21-1018

DOI: https://doi.org/10.1115/1.4054514

Published Online: June 24, 2022

View Article titled, Coupling of ASTEC V2.1 and RASCAL 4.3 Codes to Evaluate the Source Term and the Radiological Consequences of a Loss-of-Cooling Accident at a Spent Fuel Pool

Topics: Accidents, Cooling, Emissions, Fukushima nuclear disaster, Japan, 2011, Meteorology, Nuclear power stations, Simulation, Spent nuclear fuels, Wind, Wind velocity

Journal Articles

Characterization of the Finite Element Computational Fluid Dynamics Capabilities in the Multiphysics Object Oriented Simulation Environment

Abdullah G. Weiss, Laith J. Zaidan, Mohammad T. H. Bani Ahmad, M. Gomaa Abdoelatef, John W. Peterson, Alexander D. Lindsay, Fande Kong, Karim Ahmed, Mark L. Kimber

ASME J of Nuclear Rad Sci. April 2023, 9(2): 021402.

Paper No: NERS-21-1170

DOI: https://doi.org/10.1115/1.4054685

Published Online: June 15, 2022

View Article titled, Characterization of the Finite Element Computational Fluid Dynamics Capabilities in the Multiphysics Object Oriented Simulation Environment

Topics: Computational fluid dynamics, Cylinders, Errors, Finite element analysis, Flow (Dynamics), Pressure, Simulation, Vortex street, Engineering simulation, Physics

Journal Articles

Thermal-Hydraulic Safety Assessment of Full-Scale ESBWR Nuclear Reactor Design

S. P. Saraswat, D. Ray, G. Mishra, D. Yadav, V. S. Bhadouria, P. Munshi, C. Allison

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031403.

Paper No: NERS-21-1073

DOI: https://doi.org/10.1115/1.4052014

Published Online: May 26, 2022

View Article titled, Thermal-Hydraulic Safety Assessment of Full-Scale ESBWR Nuclear Reactor Design

Topics: Accidents, Boiling water reactors, Containment, Design, Pressure, Safety, Steam, Water, Heat, Economics

Journal Articles

Development of a Phase-Field Method for Phase Change Simulations Using a Conservative Allen–Cahn Equation

Akinori Tamura, Kenichi Katono

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031402.

Paper No: NERS-21-1068

DOI: https://doi.org/10.1115/1.4052807

Published Online: May 26, 2022

View Article titled, Development of a Phase-Field Method for Phase Change Simulations Using a Conservative Allen–Cahn Equation

Topics: Boundary-value problems, Simulation, Wetting, Vapors, Bubbles, Simulation results

Journal Articles

Theoretical Approach for the Fast Estimation of the Turbulent Kinematic Viscosity for Internal Flows

Sal Rodriguez, Nima Fathi, Mahyar Pourghasemi

ASME J of Nuclear Rad Sci. July 2022, 8(3): 034502.

Paper No: NERS-20-1213

DOI: https://doi.org/10.1115/1.4054342

Published Online: May 26, 2022

View Article titled, Theoretical Approach for the Fast Estimation of the Turbulent Kinematic Viscosity for Internal Flows

Topics: Flow (Dynamics), Internal flow, Kinematics, Turbulence, Viscosity, Simulation, Eddies (Fluid dynamics)

Journal Articles

Development and Processing of Thermal-Hydraulic Model for GFR 2400 Fast Reactor Design and NESTLE Coupled Transient Code

Filip Osuský, Branislav Vrban, Štefan Čerba, Jakub Lüley, Vladimír Nečas

ASME J of Nuclear Rad Sci. October 2022, 8(4): 041401.

Paper No: NERS-21-1012

DOI: https://doi.org/10.1115/1.4051515

Published Online: March 22, 2022

View Article titled, Development and Processing of Thermal-Hydraulic Model for GFR 2400 Fast Reactor Design and NESTLE Coupled Transient Code

Topics: Coolants, Design, Fast neutron reactors, Fuels, Heat, Temperature, Transients (Dynamics), Temperature distribution, Simulation, Cladding systems (Building)

Journal Articles

Flow and Heat Transfer Simulation in a Complete Pressurized Water Reactor Fuel Assembly Using Wall-Modeled RANS

B. Mikuž, F. Roelofs

ASME J of Nuclear Rad Sci. October 2022, 8(4): 041402.

Paper No: NERS-21-1021

DOI: https://doi.org/10.1115/1.4051446

Published Online: March 22, 2022

View Article titled, Flow and Heat Transfer Simulation in a Complete Pressurized Water Reactor Fuel Assembly Using Wall-Modeled RANS

Topics: Flow (Dynamics), Fuel rods, Fuels, Manufacturing, Pressure drop, Pressurized water reactors, Temperature, Simulation, Reynolds-averaged Navier–Stokes equations, Turbulence

Journal Articles

Neutronic and Thermal-Mechanical Coupling Schemes for Heat Pipe-Cooled Reactor Designs

Yugao Ma, Minyun Liu, Biheng Xie, Wenbin Han, Xiaoming Chai, Shanfang Huang, Hongxing Yu

ASME J of Nuclear Rad Sci. April 2022, 8(2): 021303.

Paper No: NERS-20-1207

DOI: https://doi.org/10.1115/1.4051612

Published Online: October 19, 2021

View Article titled, Neutronic and Thermal-Mechanical Coupling Schemes for Heat Pipe-Cooled Reactor Designs

Topics: Design, Displacement, Fuels, Geometry, Heat, Heat pipes, Molten salt reactors, Nuclear fission, Pipes, Temperature

Journal Articles

Molecular Dynamics of Supercritical Water for Nuclear Data Development

Katy Hartling, Gang Li, Ghaouti Bentoumi, Zahra Yamani

ASME J of Nuclear Rad Sci. April 2022, 8(2): 021301.

Paper No: NERS-20-1179

DOI: https://doi.org/10.1115/1.4051790

Published Online: October 19, 2021

View Article titled, Molecular Dynamics of Supercritical Water for Nuclear Data Development

Topics: Molecular dynamics simulation, Simulation, Statistical process control, Water, Electromagnetic scattering, Radiation scattering, Scattering (Physics)

Journal Articles

Development of a Phase-Field Method for Phase Change Simulations Using a Conservative Allen–Cahn Equation

Akinori Tamura, Kenichi Katono

ASME J of Nuclear Rad Sci. April 2022, 8(2): 021401.

Paper No: NERS-20-1182

DOI: https://doi.org/10.1115/1.4050209

Published Online: October 19, 2021

View Article titled, Development of a Phase-Field Method for Phase Change Simulations Using a Conservative Allen–Cahn Equation

Topics: Boundary-value problems, Simulation, Wetting, Vapors, Bubbles, Simulation results

Journal Articles

Optimization of the Nodalization of Nuclear System Thermal-Hydraulic Code Applied on Primary Loop Benchmark

Hong Xu, Aurelian Florin Badea, Xu Cheng

ASME J of Nuclear Rad Sci. April 2022, 8(2): 021404.

Paper No: NERS-21-1036

DOI: https://doi.org/10.1115/1.4050770

Published Online: October 19, 2021

View Article titled, Optimization of the Nodalization of Nuclear System Thermal-Hydraulic Code Applied on Primary Loop Benchmark

Topics: Accidents, Coolants, Steady state, Transients (Dynamics), Errors, Flow (Dynamics), Thermal hydraulics, Leakage, Simulation

Journal Articles

Simulation Studies of the Sodium Hydraulic Behavior to Design a Mockup for Eddy Current Flowmeter Testing

Hubert Delacroix, Frédéric Navacchia

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011317.

Paper No: NERS-20-1066

DOI: https://doi.org/10.1115/1.4052376

Published Online: October 4, 2021

View Article titled, Simulation Studies of the Sodium Hydraulic Behavior to Design a Mockup for Eddy Current Flowmeter Testing

Topics: Evacuations, Flow (Dynamics), Flowmeters, Jets, Pipes, Sodium, Eddies (Fluid dynamics), Eddy currents (Electricity), Geometry, Design

Journal Articles

Evaluation of the ESFR End of Equilibrium Cycle State: Spatial Distributions of Reactivity Coefficients

Una Baker, Marat Margulis, Eugene Shwageraus, Emil Fridman, Antonio Jiménez Carrascosa, Nuria García Herranz, Oscar Cabellos, Robert Gregg, Jiri Krepel

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011316.

Paper No: NERS-21-1053

DOI: https://doi.org/10.1115/1.4052121

Published Online: September 21, 2021

View Article titled, Evaluation of the ESFR End of Equilibrium Cycle State: Spatial Distributions of Reactivity Coefficients

Topics: Sodium, Cycles, Simulation

Journal Articles

Analysis of ESFR Decay Heat Removal Systems in Protected Station Blackout

Janos Bodi, Alexander Ponomarev, Evaldas Bubelis, Konstantin Mikityuk

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011315.

Paper No: NERS-21-1047

DOI: https://doi.org/10.1115/1.4052190

Published Online: September 20, 2021

View Article titled, Analysis of ESFR Decay Heat Removal Systems in Protected Station Blackout

Topics: Heat, Simulation, Sodium, Temperature, Design, Circuits, Flow (Dynamics)

Journal Articles

Coupled Neutronics–Mechanics Analysis Method for Evaluation of Reactivity Change Due to Core Distortion in Sodium Fast Reactor

Janos Bodi, Alexander Ponomarev, Konstantin Mikityuk

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011307.

Paper No: NERS-20-1183

DOI: https://doi.org/10.1115/1.4050417

Published Online: August 3, 2021

View Article titled, Coupled Neutronics–Mechanics Analysis Method for Evaluation of Reactivity Change Due to Core Distortion in Sodium Fast Reactor

Topics: Deformation, Displacement, Finite element analysis, Geometry, Manufacturing, Sodium fast reactors, Fuels, Simulation, Absorption

Journal Articles

Global Sensitivity Analysis for U(VI) Transport for Integrating Coupled Thermal–Hydrological–Chemical Processes Models Into Performance Assessment Model

Dinara Ermakova, Haruko Wainwright, LianGe Zheng, Ian Shirley, Hannah Lu

ASME J of Nuclear Rad Sci. October 2021, 7(4): 041902.

Paper No: NERS-20-1174

DOI: https://doi.org/10.1115/1.4050297

Published Online: May 13, 2021

View Article titled, Global Sensitivity Analysis for U(VI) Transport for Integrating Coupled Thermal–Hydrological–Chemical Processes Models Into Performance Assessment Model

Topics: Polishing equipment, Rocks, Sensitivity analysis, Simulation, Chemical processes, Minerals, Density

Journal citation

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Manuscript

System Thermal-hydraulics Model for Fluoride Salt-Cooled Reactor Based On Small Advanced High Temperature Reactor (smAHTR) Design Concept

Investigation Into Hybridization of the Two-Fluid Model and Phase-Field Model for Multi-Scale Two-Phase Flow Simulations

Introducing Passive Nuclear Safety in Water-Cooled Reactors: Numerical Simulation and Validation of Natural Convection Heat Transfer and Transport in Packed Beds of Heated Microspheres

Pearson Correlation and Chi-Squared Methods Applied to the Sensitivity and Uncertainty Analysis of Hydrogen Generation During a BWR STSBO Using MAAP5 and AZTUSIA

Coupling of ASTEC V2.1 and RASCAL 4.3 Codes to Evaluate the Source Term and the Radiological Consequences of a Loss-of-Cooling Accident at a Spent Fuel Pool

Characterization of the Finite Element Computational Fluid Dynamics Capabilities in the Multiphysics Object Oriented Simulation Environment

Thermal-Hydraulic Safety Assessment of Full-Scale ESBWR Nuclear Reactor Design

Development of a Phase-Field Method for Phase Change Simulations Using a Conservative Allen–Cahn Equation

Theoretical Approach for the Fast Estimation of the Turbulent Kinematic Viscosity for Internal Flows

Development and Processing of Thermal-Hydraulic Model for GFR 2400 Fast Reactor Design and NESTLE Coupled Transient Code

Flow and Heat Transfer Simulation in a Complete Pressurized Water Reactor Fuel Assembly Using Wall-Modeled RANS

Neutronic and Thermal-Mechanical Coupling Schemes for Heat Pipe-Cooled Reactor Designs

Molecular Dynamics of Supercritical Water for Nuclear Data Development

Development of a Phase-Field Method for Phase Change Simulations Using a Conservative Allen–Cahn Equation

Optimization of the Nodalization of Nuclear System Thermal-Hydraulic Code Applied on Primary Loop Benchmark

Simulation Studies of the Sodium Hydraulic Behavior to Design a Mockup for Eddy Current Flowmeter Testing

Evaluation of the ESFR End of Equilibrium Cycle State: Spatial Distributions of Reactivity Coefficients

Analysis of ESFR Decay Heat Removal Systems in Protected Station Blackout

Coupled Neutronics–Mechanics Analysis Method for Evaluation of Reactivity Change Due to Core Distortion in Sodium Fast Reactor

Global Sensitivity Analysis for U(VI) Transport for Integrating Coupled Thermal–Hydrological–Chemical Processes Models Into Performance Assessment Model

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