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Journal Articles

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

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

Neutronic and Thermal-Fluidic Analyses for an Additive Manufactured Reactor With SiC Matrix and TRISO Particle Fuel

Wenbin Han, Jian Deng, Qi Lu, Chong Chen, Youyou Xu, Tao Zhang, Shanfang Huang
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041104.
Paper No: NERS-22-1145
https://doi.org/10.1115/1.4062119
Published Online: April 17, 2023
View Article titled, Neutronic and Thermal-Fluidic Analyses for an Additive Manufactured Reactor With SiC Matrix and TRISO Particle Fuel
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Topics: Additive manufacturing, Computational fluid dynamics, Design, Fuels, Particulate matter, Temperature, Coolants, Neutrons, Heat transfer, Computer software
Journal Articles

Investigation on Applicability of Subchannel Analysis Code ASFRE to Thermal Hydraulics Analysis in Fuel Assembly With Inner Duct Structure of Sodium Cooled Fast Reactor

Norihiro Kikuchi, Yasutomo Imai, Ryuji Yoshikawa, Norihiro Doda, Masaaki Tanaka
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2023, 9(3): 031401.
Paper No: NERS-21-1158
https://doi.org/10.1115/1.4056463
Published Online: February 8, 2023
View Article titled, Investigation on Applicability of Subchannel Analysis Code ASFRE to Thermal Hydraulics Analysis in Fuel Assembly With Inner Duct Structure of Sodium Cooled Fast Reactor
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Topics: Ducts, Flow (Dynamics), Fuels, Manufacturing, Sodium fast reactors, Temperature, Temperature distribution, Thermal hydraulics, Wire, Fuel rods
Journal Articles

Dimensionless Profiles of Temperature and Steam Mass Fraction in Flows of Steam-Air Mixtures on a Flat Plate

Michio Murase, Tomonori Suzuki, Yoichi Utanohara, Toshiya Takaki
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2023, 9(1): 011401.
Paper No: NERS-22-1006
https://doi.org/10.1115/1.4054842
Published Online: July 19, 2022
View Article titled, Dimensionless Profiles of Temperature and Steam Mass Fraction in Flows of Steam-Air Mixtures on a Flat Plate
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Topics: Flow (Dynamics), Steam, Temperature, Turbulence, Condensation, Flat plates, Boundary layer turbulence, Computational fluid dynamics, Computation
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

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

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

Transient Analysis of Passive Autocatalytic Hydrogen Recombiners Using Computational Fluid Dynamics

Ahsan Khan, Rab Nawaz, Ajmal Shah, Kamran Rasheed Qureshi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2023, 9(1): 012001.
Paper No: NERS-21-1153
https://doi.org/10.1115/1.4054117
Published Online: June 7, 2022
View Article titled, Transient Analysis of Passive Autocatalytic Hydrogen Recombiners Using Computational Fluid Dynamics
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Topics: Computational fluid dynamics, Hydrogen, Temperature, Plates (structures)
Journal Articles

Prediction Method for Condensation Heat Transfer in the Presence of Noncondensable Gas for Computational Fluid Dynamics Applications

Michio Murase, Yoichi Utanohara, Akio Tomiyama
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031404.
Paper No: NERS-21-1097
https://doi.org/10.1115/1.4053051
Published Online: May 26, 2022
View Article titled, Prediction Method for Condensation Heat Transfer in the Presence of Noncondensable Gas for Computational Fluid Dynamics Applications
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Topics: Condensation, Heat transfer, Steam, Temperature, Temperature distribution, Computational fluid dynamics, Mass transfer, Flat plates
Journal Articles

Testing the Modified Subchannel tempa-sc Code in Comparison With Experiments and Other Computer Codes

A. M. Baisov, A. N. Churkin, V. I. Deev, V. S. Kharitonov
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031101.
Paper No: NERS-21-1101
https://doi.org/10.1115/1.4053049
Published Online: March 22, 2022
View Article titled, Testing the Modified Subchannel tempa-sc Code in Comparison With Experiments and Other Computer Codes
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Topics: Coolants, Fluids, Fuel rods, Heat transfer, Momentum, Temperature, Water, Wall temperature, Flow (Dynamics), Testing
Journal Articles

Deteriorated Heat Transfer Influence on the Stress–Strain State of Small Modular Reactors SCWR Fuel Bundles

Y. Dubyk, V. Filonov, Y. Filonova, O. Kovalenko
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031105.
Paper No: NERS-21-1082
https://doi.org/10.1115/1.4052590
Published Online: March 15, 2022
View Article titled, Deteriorated Heat Transfer Influence on the Stress–Strain State of Small Modular Reactors SCWR Fuel Bundles
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Topics: Computational fluid dynamics, Heat transfer, Stress, Supercritical water reactors, Temperature, Fuels, Small modular reactors
Journal Articles

Experiment and Codes to Support Safety Assessments for Sodium Fast Reactors (KASOLA, SOLTEC and KARIFA)

Wolfgang Hering, Joachim Fuchs, Alexandru Onea, Sara Perez-Martin, Thomas Schaub
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011324.
Paper No: NERS-21-1031
https://doi.org/10.1115/1.4052642
Published Online: December 7, 2021
View Article titled, Experiment and Codes to Support Safety Assessments for Sodium Fast Reactors (KASOLA, SOLTEC and KARIFA)
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Topics: Flow (Dynamics), Safety, Sodium, Temperature, Test facilities, Liquid metals, Boiling, Computational fluid dynamics, Fluids, Instrumentation
Journal Articles

Numerical Study of the Deposition of Radioactive Nuclide (Aerosol) in Pressurized Water Reactor Steam Generator

Muhammad Aadil, Rab Nawaz, Ajmal Shah, Kamran Rasheed Qureshi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2022, 8(2): 021801.
Paper No: NERS-20-1210
https://doi.org/10.1115/1.4051618
Published Online: October 19, 2021
View Article titled, Numerical Study of the Deposition of Radioactive Nuclide (Aerosol) in Pressurized Water Reactor Steam Generator
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Topics: Aerosols, Boilers, Decontamination, Nuclides, Particulate matter, Pressurized water reactors, Turbulence, Computational fluid dynamics, Flow (Dynamics), Particle size
Journal Articles

Severe Accidents in Sodium-Cooled Fast Reactors: Computational Fluid Dynamics Sensitivity Studies on the Thermal Ablation of Core Catcher

Olivier Czarny, Adrien Collin De L'Hortet, Nicolas Goreaud
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011318.
Paper No: NERS-20-1200
https://doi.org/10.1115/1.4052306
Published Online: October 4, 2021
View Article titled, Severe Accidents in Sodium-Cooled Fast Reactors: Computational Fluid Dynamics Sensitivity Studies on the Thermal Ablation of Core Catcher
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Topics: Ablation (Vaporization technology), Accidents, Temperature, Design, Sodium fast reactors, Computational fluid dynamics
Journal Articles

Computational Fluid Dynamic Analysis of the ESFR Reactor Pit Cooling System in Case of Sodium Leakage

Aleksander Grah, Haileyesus Tsige-Tamirat, Joel Guidez, Antoine Gerschenfeld, Konstantin Mikityuk, Janos Bodi, Enrico Girardi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011314.
Paper No: NERS-20-1204
https://doi.org/10.1115/1.4051292
Published Online: September 20, 2021
View Article titled, Computational Fluid Dynamic Analysis of the ESFR Reactor Pit Cooling System in Case of Sodium Leakage
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Topics: Computational fluid dynamics, Concretes, Cooling, Cooling systems, Design, Heat, Heat flux, Leakage, Reactor vessels, Safety
Journal Articles

Computational Fluid Dynamics Simulations of the Cold Neutron Source at the OPAL Reactor

James Spedding, Mark Ho, Weijian Lu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2021, 7(4): 041401.
Paper No: NERS-20-1126
https://doi.org/10.1115/1.4049054
Published Online: April 16, 2021
View Article titled, Computational Fluid Dynamics Simulations of the Cold Neutron Source at the OPAL Reactor
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Topics: Simulation, Helium, Computational fluid dynamics, Engineering prototypes, Heat exchangers, Flow (Dynamics)
Journal Articles

Numerical Analysis of Heat Transfer on the Shell Side of a Helically Coiled Tube Heat Exchanger for Helium Applications

Radomír Filip, Tomáš Melichar
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2021, 7(2): 021403.
Paper No: NERS-20-1187
https://doi.org/10.1115/1.4050205
Published Online: March 8, 2021
View Article titled, Numerical Analysis of Heat Transfer on the Shell Side of a Helically Coiled Tube Heat Exchanger for Helium Applications
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Topics: Computational fluid dynamics, Flow (Dynamics), Heat exchangers, Heat transfer, Heat transfer coefficients, Helium, Shells, Temperature, Pressure, Water
Journal Articles

Improved Computational Fluid Dynamics Framework for Reactor Core Baffle Swelling Assessment

Yuliia Filonova, Yaroslav Dubyk, Vladislav Filonov, Vadym Kondratjuk
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011404.
Paper No: NERS-20-1009
https://doi.org/10.1115/1.4047495
Published Online: October 5, 2020
View Article titled, Improved Computational Fluid Dynamics Framework for Reactor Core Baffle Swelling Assessment
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Topics: Boundary-value problems, Computational fluid dynamics, Coolants, Flow (Dynamics), Geometry, Temperature, Cooling, Temperature distribution, Metals
Journal Articles

Computational Fluid Dynamics Thermal Analysis of ITER Pressure Suppression Tanks

Lorenzo Basili, Rosa Lo Frano, Marco Olcese, Igor Sekachev, Donato Aquaro
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2021, 7(1): 012301.
Paper No: NERS-19-1156
https://doi.org/10.1115/1.4048007
Published Online: October 5, 2020
View Article titled, Computational Fluid Dynamics Thermal Analysis of ITER Pressure Suppression Tanks
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Topics: Accidents, Computational fluid dynamics, Design, Flanges, Insulation, Pressure, Stress, Temperature, Temperature gradient, Thermal analysis
Journal Articles

Flow Instability Investigation at Supercritical Pressures in Parallel Channels by Computational Fluid Dynamics Adopting Low- and High-Power Boundaries

Edward Shitsi, Seth Kofi Debrah, Vincent Yao Agbodemegbe, Emmanuel Ampomah-Amoako
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011401.
Paper No: NERS-19-1142
https://doi.org/10.1115/1.4046255
Published Online: October 1, 2020
View Article titled, Flow Instability Investigation at Supercritical Pressures in Parallel Channels by Computational Fluid Dynamics Adopting Low- and High-Power Boundaries
Open the PDF for Flow Instability Investigation at Supercritical Pressures in Parallel Channels by Computational Fluid Dynamics Adopting Low- and High-Power Boundaries in another window
Topics: Computational fluid dynamics, Flow (Dynamics), Flow instability, Gravity (Force), Oscillations, Pressure, Temperature, Heating, Turbulence, Coolants
Journal Articles

Analysis Methods for High Energy Line Break Jet Flows in Nuclear Power Plants

Marwan Charrouf, Storm Kauffman, Jin-Kyoo Yoon, Sang-Gyu Lee, Taejoon Kim
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2020, 6(4): 041112.
Paper No: NERS-19-1168
https://doi.org/10.1115/1.4047441
Published Online: September 4, 2020
View Article titled, Analysis Methods for High Energy Line Break Jet Flows in Nuclear Power Plants
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Topics: Computational fluid dynamics, Flow (Dynamics), Jets, Nozzles, Nuclear power stations, Pipes, Pressure, Reflection, Resonance, Waves