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Journal Articles

Progress on a Preconceptual Supercritical Water-Cooled Small Modular Reactor

Open Access
A. Nava Dominguez, Xianmin Huang, Michel Gaudet, Kittima Khumsa-Ang, Alberto D'Ansi Mendoza España, Jimmy Chow, Danila Roubtsov, Hygreeva Namburi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2025, 11(3): 031301.
Paper No: NERS-24-1027
https://doi.org/10.1115/1.4068326
Published Online: May 8, 2025
View Article titled, Progress on a Preconceptual Supercritical Water-Cooled Small Modular Reactor
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Topics: Cladding systems (Building), Coolants, Design, Fuels, Loss of coolant accidents, Safety, Temperature, Water, Flow (Dynamics), Small modular reactors
Journal Articles

Effect of Variable Angular Piping Bends Geometry on Turbulent Flow of Supercritical Water in an SCWR Plant Piping Network: A Three-Dimensional Computational Fluid Dynamics Investigation

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Mohammad Khan, Jehad Haque, Saad Islam, Lubon Putul, Mehedi Hasan
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2025, 11(3): 031401.
Paper No: NERS-24-1060
https://doi.org/10.1115/1.4067628
Published Online: February 14, 2025
View Article titled, Effect of Variable Angular Piping Bends Geometry on Turbulent Flow of Supercritical Water in an SCWR Plant Piping Network: A Three-Dimensional Computational Fluid Dynamics Investigation
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Topics: Computational fluid dynamics, Flow (Dynamics), Pipe bends, Pipes, Pressure, Supercritical water reactors, Turbulence, Water, Geometry, Fluids
Journal Articles

Operation Optimization Framework for Advanced Reactors Using a Data-Driven Digital Twin

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Andy Rivas, Gregory K. Delipei, Jason Hou
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2025, 11(2): 021801.
Paper No: NERS-24-1017
https://doi.org/10.1115/1.4066777
Published Online: December 5, 2024
View Article titled, Operation Optimization Framework for Advanced Reactors Using a Data-Driven Digital Twin
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Topics: Electricity (Physics), Optimization, Probability, Maintenance, Steam, Safety, Temperature, Pumps, Uncertainty, Turbines
Journal Articles

Numerical Analysis of Gas Generation and Migration in a Radioactive Waste Disposal Cell of a Deep Geological Repository

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Lan Sun, Liyan Qiu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2025, 11(2): 021901.
Paper No: NERS-24-1023
https://doi.org/10.1115/1.4067173
Published Online: December 5, 2024
View Article titled, Numerical Analysis of Gas Generation and Migration in a Radioactive Waste Disposal Cell of a Deep Geological Repository
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Topics: Carbon dioxide, Pressure, Temperature, Rocks, Safety, Diffusion (Physics), Computer simulation
Journal Articles

Studies of the Thermalhydraulics Subchannel Code ASSERT-PV 3.2-SC for Supercritical Applications

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Armando Nava-Dominguez, Xianmin Huang, Songyu Liu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2025, 11(2): 021402.
Paper No: NERS-24-1028
https://doi.org/10.1115/1.4066523
Published Online: November 4, 2024
View Article titled, Studies of the Thermalhydraulics Subchannel Code ASSERT-PV 3.2-SC for Supercritical Applications
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Topics: Flow (Dynamics), Fluids, Fuels, Heat transfer, Manufacturing, Pressure, Supercritical water reactors, Wall temperature, Water, Wire
Journal Articles

Fabrication Aspects and Performance Characterization of α-Al 2 O 3 /AlPO 4 Based Sandwich Configuration Flow Channel Inserts and Coatings for High Temperature Liquid Metal Applications

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Abhishek Saraswat, Rajendraprasad Bhattacharyay, Paritosh Chaudhuri, Sateesh Gedupudi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2024, 10(3): 030902.
Paper No: NERS-23-1007
https://doi.org/10.1115/1.4062646
Published Online: March 8, 2024
View Article titled, Fabrication Aspects and Performance Characterization of α-Al 2 O 3 /AlPO 4 Based Sandwich Configuration Flow Channel Inserts and Coatings for High Temperature Liquid Metal Applications
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Topics: Coatings, Engineering prototypes, Flow (Dynamics), High temperature, Insulation, Liquid metals, Magnetohydrodynamics, Manufacturing, Pressure, Welding
Journal Articles

Design and Analysis of a Free-Piston Stirling Engine for Microreactor Applications

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Phat Doan, Minghui Chen
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2024, 10(3): 030907.
Paper No: NERS-23-1072
https://doi.org/10.1115/1.4064335
Published Online: March 8, 2024
View Article titled, Design and Analysis of a Free-Piston Stirling Engine for Microreactor Applications
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Topics: Design, Engines, Pistons, Pressure, Stirling engines, Temperature, Compression, Matlab
Journal Articles

Development and Testing of a System Thermal-Hydraulics Model for a 50-MW el -Class Pressurized Water Reactor–Small Modular Reactor

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Shujun Wang, Xianmin Huang, Yanfei Rao, Blair P. Bromley
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2024, 10(2): 021402.
Paper No: NERS-23-1086
https://doi.org/10.1115/1.4063240
Published Online: January 29, 2024
View Article titled, Development and Testing of a System Thermal-Hydraulics Model for a 50-MW el -Class Pressurized Water Reactor–Small Modular Reactor
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Topics: Boilers, Design, Flow (Dynamics), Pressure, Pressurized water reactors, Small modular reactors, Temperature, Thermal hydraulics, Oscillations, Junctions
Journal Articles

Computational Fluid Dynamics Calculations of Moderator Heat and Fluid Flow of Small Modular Heavy Water Reactor

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Tomas Korinek, Radek Skoda, Martin Lovecky, Ondrej Burian
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. January 2024, 10(1): 014501.
Paper No: NERS-23-1015
https://doi.org/10.1115/1.4063007
Published Online: October 20, 2023
View Article titled, Computational Fluid Dynamics Calculations of Moderator Heat and Fluid Flow of Small Modular Heavy Water Reactor
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Topics: Computational fluid dynamics, Cooling systems, Flow (Dynamics), Fluid dynamics, Heat, Heavy water reactors, Inertia (Mechanics), Pressure, Temperature, Vessels
Journal Articles

Main Parameters Influencing the Level of Labile Contamination and the Removal Factor

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Pierrick Agullo, Alban Gossard, Gilles Ranchoux, Emmanuel Porcheron, Fabrice Petitot
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041106.
Paper No: NERS-22-1160
https://doi.org/10.1115/1.4062550
Published Online: May 31, 2023
View Article titled, Main Parameters Influencing the Level of Labile Contamination and the Removal Factor
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Topics: Contamination, Surface roughness, Pressure, Temperature, Drying
Journal Articles

ATHENA Main Heat Exchanger Conceptual Design and Thermal-Hydraulic Assessment With RELAP5 Code

Available to Purchase
Tommaso Del Moro, Pierdomenico Lorusso, Fabio Giannetti, Mariano Tarantino, Marco Caramello, Daniele Mazzi, Marin Constantin
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041108.
Paper No: NERS-22-1165
https://doi.org/10.1115/1.4056973
Published Online: March 13, 2023
View Article titled, ATHENA Main Heat Exchanger Conceptual Design and Thermal-Hydraulic Assessment With RELAP5 Code
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Topics: Cycles, Heat exchangers, Sensitivity analysis, Water, Fast neutron reactors, Conceptual design, Temperature, Heat, Bathythermographs, Geometry
Journal Articles

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

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Akinori Tamura, Kenichi Katono
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2023, 9(3): 031404.
Paper No: NERS-22-1052
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
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Topics: Bubbles, Bubbly flow, Fluids, Pressure, Simulation, Plumes (Fluid dynamics), Porosity, Surface tension, Flow (Dynamics), Two-phase flow
Journal Articles

Assessment of Filtered Containment Venting Strategies for Mitigating Severe Accident Consequences at a Generic Single-Unit CANDU

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M. D. Shah, A. C. Morreale, L. S. Lebel
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2023, 9(1): 011701.
Paper No: NERS-22-1025
https://doi.org/10.1115/1.4055258
Published Online: September 2, 2022
View Article titled, Assessment of Filtered Containment Venting Strategies for Mitigating Severe Accident Consequences at a Generic Single-Unit CANDU
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Topics: Accidents, Containment, Failure, Pressure, Water
Journal Articles

Computational Fluid Dynamics Modeling of a Pressurized Water Reactor Fuel Assembly to Estimate Loss Coefficients in Support of Subchannel Thermalhydraulics Modeling of Pressurized Water Reactor Small Modular Reactors With Advanced Fuels

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Chenguang Li, Krishna Podila, Blair P. Bromley, Yanfei Rao
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2023, 9(1): 011402.
Paper No: NERS-22-1028
https://doi.org/10.1115/1.4054943
Published Online: July 19, 2022
View Article titled, Computational Fluid Dynamics Modeling of a Pressurized Water Reactor Fuel Assembly to Estimate Loss Coefficients in Support of Subchannel Thermalhydraulics Modeling of Pressurized Water Reactor Small Modular Reactors With Advanced Fuels
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Topics: Computational fluid dynamics, Fuels, Modeling, Pressure, Pressurized water reactors, Manufacturing, Flow (Dynamics), Small modular reactors
Journal Articles

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

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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
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2023, 9(2): 021402.
Paper No: NERS-21-1170
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
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Topics: Computational fluid dynamics, Cylinders, Errors, Finite element analysis, Flow (Dynamics), Pressure, Simulation, Vortex street, Engineering simulation, Physics
Journal Articles

Flash-Boiling Characterization During Ingress of Coolant Event for Dust Issue in ITER

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Benjamin Blaisot, Emmanuel Porcheron, Olivier Praud, Véronique Roig
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 032301.
Paper No: NERS-21-1149
https://doi.org/10.1115/1.4053828
Published Online: June 1, 2022
View Article titled, Flash-Boiling Characterization During Ingress of Coolant Event for Dust Issue in ITER
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Topics: Boiling, Coolants, Drops, Dust, Ejectors, Flow (Dynamics), Pressure, Sprays, Vacuum, Water
Journal Articles

Hydrogen Deflagration Analysis in THAI Experiments Using MELCOR Code

Available to Purchase
Alain Flores y Flores, Guido Mazzini
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031201.
Paper No: NERS-20-1034
https://doi.org/10.1115/1.4048006
Published Online: May 27, 2022
View Article titled, Hydrogen Deflagration Analysis in THAI Experiments Using MELCOR Code
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Topics: Explosions, Hydrogen, Aerosols, Thermal hydraulics, Pressure, Flames, Test facilities
Journal Articles

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

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S. P. Saraswat, D. Ray, G. Mishra, D. Yadav, V. S. Bhadouria, P. Munshi, C. Allison
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031403.
Paper No: NERS-21-1073
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
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Topics: Accidents, Boiling water reactors, Containment, Design, Pressure, Safety, Steam, Water, Heat, Economics
Journal Articles

Joining of Zirconium Alloys to Nickel Bearing Alloys for In-Core Components

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Michel Gaudet, Anne McLellan, Adrian Gerlich, Bruce Williams
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031106.
Paper No: NERS-21-1087
https://doi.org/10.1115/1.4054557
Published Online: May 17, 2022
View Article titled, Joining of Zirconium Alloys to Nickel Bearing Alloys for In-Core Components
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Topics: Alloys, Extruding, Friction welding, Zirconium alloys, Stainless steel, Bearings, Zirconium, Friction, Nickel, Supercritical water reactors
Journal Articles

Fuel Performance Modeling at High Burn-Up by FEMAXI-6 Code

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Jakub Lüley, Branislav Vrban, Štefan Čerba, Filip Osuský, Vladimír Nečas
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041601.
Paper No: NERS-21-1030
https://doi.org/10.1115/1.4052519
Published Online: March 22, 2022
View Article titled, Fuel Performance Modeling at High Burn-Up by FEMAXI-6 Code
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Topics: Fuels, Grain size, Irradiation (Radiation exposure), Modeling, Nuclear fission, Rods, Pressure, Cladding systems (Building), Stress