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Journal Articles

System Thermal-Hydraulics Model for Fluoride Salt-Cooled Reactor Based on Small Modular Advanced High Temperature Reactor (SmAHTR) Design Concept

Shujun Wang, Xianmin Huang, Blair P. Bromley
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041302.
Paper No: NERS-23-1011
https://doi.org/10.1115/1.4062500
Published Online: September 15, 2023
View Article titled, System Thermal-Hydraulics Model for Fluoride Salt-Cooled Reactor Based on Small Modular Advanced High Temperature Reactor (SmAHTR) Design Concept
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Topics: Coolants, Cycles, Design, Flow (Dynamics), Fuels, High temperature, Modeling, Temperature, Thermal hydraulics, Steady state
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
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

The Heat Capacity of PuO 2 at High Temperature: Molecular Dynamics Calculations

Rolando Calabrese
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041603.
Paper No: NERS-21-1027
https://doi.org/10.1115/1.4054941
Published Online: September 1, 2022
View Article titled, The Heat Capacity of PuO 2 at High Temperature: Molecular Dynamics Calculations
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Topics: Heat capacity, High temperature, Oxygen, Temperature, Molecular dynamics, Enthalpy, Modeling
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

Physics Modeling for Conceptual Designs of Proposed Experiments in the Zero Energy Deuterium-2 Critical Facility for Testing Small Modular Reactor-Type Fuels

D. G. Watts, F. P. Adams, E. Masala, L. Blomeley, B. P. Bromley
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031501.
Paper No: NERS-21-1118
https://doi.org/10.1115/1.4054079
Published Online: May 26, 2022
View Article titled, Physics Modeling for Conceptual Designs of Proposed Experiments in the Zero Energy Deuterium-2 Critical Facility for Testing Small Modular Reactor-Type Fuels
Open the PDF for Physics Modeling for Conceptual Designs of Proposed Experiments in the Zero Energy Deuterium-2 Critical Facility for Testing Small Modular Reactor-Type Fuels in another window
Topics: Fuels, Modeling, Physics, Pressurized water reactors, Water, Neutrons, High temperature
Journal Articles

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

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
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

Reassessment of Computational Tools for the Modeling of Heat Transfer in a Molten UO 2 Pool in Natural Convection

Claude Jamond, Elena Martin Lopez, Xue-Nong Chen, Nathalie Girault, Pierre Gubernatis, Andrei Rineiski
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011325.
Paper No: NERS-20-1142
https://doi.org/10.1115/1.4052489
Published Online: December 14, 2021
View Article titled, Reassessment of Computational Tools for the Modeling of Heat Transfer in a Molten UO 2 Pool in Natural Convection
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Topics: Fuels, Heat transfer, Modeling, Natural convection, Heat, Temperature, Flux (Metallurgy)
Journal Articles

Special Issue: EU ESFR-SMART ProjectWord From the Horizon: 2020 EU ESFR-SMART Project Coordinator

Konstantin Mikityuk
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Guest Editorial
ASME J of Nuclear Rad Sci. January 2022, 8(1): 010305.
Paper No: NERS-21-1121
https://doi.org/10.1115/1.4052641
Published Online: December 14, 2021
View Article titled, Special Issue: EU ESFR-SMART ProjectWord From the Horizon: 2020 EU ESFR-SMART Project Coordinator
Open the PDF for Special Issue: EU ESFR-SMART ProjectWord From the Horizon: 2020 EU ESFR-SMART Project Coordinator in another window
Topics: Safety, Sodium, Sodium fast reactors, Modeling
Journal Articles

Superphénix Benchmark Part II: Transient Results

A. Ponomarev, K. Mikityuk, E. Fridman, V. A. Di Nora, E. Bubelis, M. Schikorr
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011321.
Paper No: NERS-21-1052
https://doi.org/10.1115/1.4051877
Published Online: October 8, 2021
View Article titled, Superphénix Benchmark Part II: Transient Results
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Topics: Flow (Dynamics), Fuels, Sodium, Temperature, Transients (Dynamics), Modeling
Journal Articles

Modeling of Reactivity Effects and Transient Behavior of Large Sodium Fast Reactor

Alexander Ponomarev, Konstantin Mikityuk
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011313.
Paper No: NERS-20-1186
https://doi.org/10.1115/1.4051514
Published Online: September 13, 2021
View Article titled, Modeling of Reactivity Effects and Transient Behavior of Large Sodium Fast Reactor
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Topics: Flow (Dynamics), Fuels, Modeling, Rods, Sodium, Sodium fast reactors, Temperature, Transients (Dynamics), Electrical conductance, Heat
Journal Articles

Neutronic Analysis of the European Sodium Fast Reactor: Part I—Fresh Core Results

Emil Fridman, Francisco Álvarez Velarde, Pablo Romojaro Otero, Haileyesus Tsige-Tamirat, Antonio Jiménez Carrascosa, Nuria García Herranz, Franck Bernard, Robert Gregg, Una Davies, Jiri Krepel, Simone Massara, Sandra Poumerouly, Enrico Girardi, Konstantin Mikityuk
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011301.
Paper No: NERS-20-1056
https://doi.org/10.1115/1.4048905
Published Online: July 20, 2021
View Article titled, Neutronic Analysis of the European Sodium Fast Reactor: Part I—Fresh Core Results
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Topics: Modeling, Safety, Scram, Sodium, Sodium fast reactors, Temperature, Fuels, Design, Computers, Equilibrium (Physics)
Journal Articles

Neutronic Analysis of the European Sodium Fast Reactor: Part II—Burnup Results

Emil Fridman, Francisco Álvarez Velarde, Pablo Romojaro Otero, Haile Tsige-Tamirat, Antonio Jiménez Carrascosa, Nuria García Herranz, Franck Bernard, Robert Gregg, Una Davies, Jiri Krepel, Ben Lindley, Simone Massara, Sandra Poumerouly, Enrico Girardi, Konstantin Mikityuk
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011302.
Paper No: NERS-20-1067
https://doi.org/10.1115/1.4048765
Published Online: July 20, 2021
View Article titled, Neutronic Analysis of the European Sodium Fast Reactor: Part II—Burnup Results
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Topics: Cycles, Equilibrium (Physics), Fuels, Modeling, Safety, Sodium fast reactors, Irradiation (Radiation exposure)
Journal Articles

Serpent and Monte Carlo Continuous Energy Burnup Code Comparison for Neutronics Calculations of the European Lead-Cooled Fast Reactor

L. C. Juárez, J. I. Torres, J. L. François
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. July 2021, 7(3): 034505.
Paper No: NERS-20-1068
https://doi.org/10.1115/1.4049714
Published Online: April 1, 2021
View Article titled, Serpent and Monte Carlo Continuous Energy Burnup Code Comparison for Neutronics Calculations of the European Lead-Cooled Fast Reactor
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Topics: Coolants, Density, Fast neutron reactors, Fuels, Neutrons, Cycles, Temperature, Modeling
Journal Articles

Modeling and Simulation of Subcooled Coolant Loss Through Circumferential Pipe Leakage

Sandip Ghosh, Samir Kumar Saha
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. July 2021, 7(3): 034503.
Paper No: NERS-20-1012
https://doi.org/10.1115/1.4048477
Published Online: March 16, 2021
View Article titled, Modeling and Simulation of Subcooled Coolant Loss Through Circumferential Pipe Leakage
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Topics: Flow (Dynamics), Leakage, Pipes, Simulation, Subcooling, Flashing, Coolants, Fracture (Materials), Modeling, Vapors
Journal Articles

The Other Metallic Phase in Spent Nuclear Fuel: A Complete Thermodynamic Evaluation of the U–Pd–Rh–Ru System

Lian-Cheng Wang, Matthew H. Kaye
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011601.
Paper No: NERS-19-1094
https://doi.org/10.1115/1.4046784
Published Online: October 1, 2020
View Article titled, The Other Metallic Phase in Spent Nuclear Fuel: A Complete Thermodynamic Evaluation of the U–Pd–Rh–Ru System
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Topics: Nuclear fuels, Phase diagrams, Temperature, Uranium, Modeling, Military systems, Nuclear fission, Spent nuclear fuels
Journal Articles

A Simplified Two-Group Multipoint Kinetics Model

Santosh K. Pradhan, K. Obaidurrahman, Kannan N. Iyer
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011502.
Paper No: NERS-19-1155
https://doi.org/10.1115/1.4046254
Published Online: October 1, 2020
View Article titled, A Simplified Two-Group Multipoint Kinetics Model
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Topics: Eigenvalues, Heat flux, Neutrons, Steady state, Transients (Dynamics), Thermal hydraulics, Diffusion (Physics), Simulation, Circuits, Fluid dynamics
Journal Articles

A Critical Review of the Physics and Modeling of Deteriorated Heat Transfer in Supercritical Fluids

Andrew W. Copping, Metin I. Yaras
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2020, 6(3): 031112.
Paper No: NERS-19-1081
https://doi.org/10.1115/1.4046654
Published Online: June 5, 2020
View Article titled, A Critical Review of the Physics and Modeling of Deteriorated Heat Transfer in Supercritical Fluids
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Topics: Buoyancy, Flow (Dynamics), Heat transfer, Modeling, Turbulence
Journal Articles

Analysis of Heat Transfer Characteristics of Canadian SCWR Fuel Assembly Concept

A. Nava Domínguez, Y. F. Rao, T. Beuthe
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2020, 6(3): 031114.
Paper No: NERS-19-1083
https://doi.org/10.1115/1.4046843
Published Online: June 5, 2020
View Article titled, Analysis of Heat Transfer Characteristics of Canadian SCWR Fuel Assembly Concept
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Topics: Cladding systems (Building), Coolants, Flow (Dynamics), Fuels, Heat losses, Heat transfer, Manufacturing, Supercritical water reactors, Temperature, Modeling
Journal Articles

Integration of Modeling Capabilities in CATHENA for Supercritical Water Reactors

T. Beuthe, A. Vasić, H. Zahlan, A. Nava Domínguez
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2020, 6(3): 031115.
Paper No: NERS-20-1002
https://doi.org/10.1115/1.4047288
Published Online: June 5, 2020
View Article titled, Integration of Modeling Capabilities in CATHENA for Supercritical Water Reactors
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Topics: Heat transfer, Modeling, Pressure, Supercritical water reactors, Temperature, Simulation, Accidents, Testing, Water, Transients (Dynamics)