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Journal Articles

Verification and Geometry Optimization of a One Fluid Molten Salt Reactor With Fixed Volume

R. Andika Putra Dwijayanto, Harun Ardiansyah, Andang Widi Harto
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2024, 10(3): 031301.
Paper No: NERS-23-1088
https://doi.org/10.1115/1.4064465
Published Online: April 17, 2024
View Article titled, Verification and Geometry Optimization of a One Fluid Molten Salt Reactor With Fixed Volume
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Topics: Fluids, Fuels, Geometry, Molten salt reactors, Neutrons, Optimization, Temperature
Journal Articles

Evaluating Hydrogen-Based Moderators in High-Temperature Gas-Cooled Reactors With 5 wt.% Enriched Uranium Annular Fuel Rods

Daniel T. Wojtaszek, Blair P. Bromley
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2024, 10(3): 031302.
Paper No: NERS-23-1090
https://doi.org/10.1115/1.4064581
Published Online: April 17, 2024
View Article titled, Evaluating Hydrogen-Based Moderators in High-Temperature Gas-Cooled Reactors With 5 wt.% Enriched Uranium Annular Fuel Rods
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Topics: Fuels, Hydrogen, Temperature, Very high temperature reactors, Uranium, Manufacturing
Journal Articles

Depletion Calculations for an Integral Small Molten Salt Reactor With Serpent

Xiaolin Wang, T. Sinh Nguyen, Daniel Wojtaszek
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2024, 10(2): 021301.
Paper No: NERS-23-1004
https://doi.org/10.1115/1.4063111
Published Online: October 20, 2023
View Article titled, Depletion Calculations for an Integral Small Molten Salt Reactor With Serpent
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Topics: Fuels, Molten salt reactors, Flow (Dynamics), Cycles, Nuclear fission
Journal Articles

Uncertainty and Sensitivity Evaluation of the QUENCH-02 Experiment Simulation Using the ASYST Code

Siniša Šadek, Renato Pavlinac, Karlo Ivanjko, Davor Grgić
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2024, 10(1): 011301.
Paper No: NERS-23-1016
https://doi.org/10.1115/1.4062799
Published Online: October 20, 2023
View Article titled, Uncertainty and Sensitivity Evaluation of the QUENCH-02 Experiment Simulation Using the ASYST Code
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Topics: Cladding systems (Building), Electricity (Physics), Flow (Dynamics), Hydrogen, Oxidation, Steam, Temperature, Uncertainty, Water, Boundary-value problems
Journal Articles

Advancement Toward the Experimental Measurement of the Lead–Bismuth Eutectic Thermal Properties Using Differential Scanning Calorimetry Technique

Satya Prakash Saraswat, Nicola Forgione, Massimo Emilio Angiolini
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2024, 10(2): 021302.
Paper No: NERS-23-1045
https://doi.org/10.1115/1.4063572
Published Online: October 20, 2023
View Article titled, Advancement Toward the Experimental Measurement of the Lead–Bismuth Eutectic Thermal Properties Using Differential Scanning Calorimetry Technique
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Topics: Calibration, Differential scanning calorimetry, Heating, Latent heat, Melting, Melting point, Specific heat, Temperature, Thermal properties, Uncertainty
Journal Articles

Eddy Current Flow Meter Measurements in Liquid Sodium at High Temperatures

Nico Krauter, Alexandru Aurelian Onea, Gunter Gerbeth, Sven Eckert
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041301.
Paper No: NERS-22-1185
https://doi.org/10.1115/1.4062239
Published Online: September 15, 2023
View Article titled, Eddy Current Flow Meter Measurements in Liquid Sodium at High Temperatures
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Topics: Eddies (Fluid dynamics), Flow (Dynamics), Flowmeters, High temperature, Sensors, Sodium, Temperature, Wire, Eddy currents (Electricity), Liquid metals
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

Impact of Thermal-Hydraulic Feedback and Differential Thermal Expansion on European Sodium-Cooled Fast Reactor Core Power Distribution

Ben Lindley, Francisco Álvarez Velarde, Una Baker, Janos Bodi, Paul Cosgrove, Alan Charles, Carlo Fiorina, Emil Fridman, Jiri Krepel, Jean Lavarenne, Konstantin Mikityuk, Evgeny Nikitin, Alexander Ponomarev, Stefan Radman, Eugene Shwageraus, Brendan Tollit
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2023, 9(3): 031301.
Paper No: NERS-22-1119
https://doi.org/10.1115/1.4056930
Published Online: March 13, 2023
View Article titled, Impact of Thermal-Hydraulic Feedback and Differential Thermal Expansion on European Sodium-Cooled Fast Reactor Core Power Distribution
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Topics: Coolants, Density, Feedback, Fuels, Sodium fast reactors, Temperature, Thermal expansion, Manufacturing, Electrical conductance, Heat
Journal Articles

Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Preliminary Study

Koji Morita, Wei Liu, Tatsumi Arima, Yuji Arita, Isamu Sato, Haruaki Matsuura, Yoshihiro Sekio, Hiroshi Sagara, Masatoshi Kawashima
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2023, 9(2): 021301.
Paper No: NERS-21-1161
https://doi.org/10.1115/1.4056834
Published Online: March 2, 2023
View Article titled, Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Preliminary Study
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Topics: Accidents, Coolants, Fuels, Temperature, Fast neutron reactors, Flow (Dynamics), Pins (Engineering), Transients (Dynamics)
Journal Articles

Thermophysical Characteristics of Liquid Metal In-Bi-Sn Eutectic (Field's Metal) as a Similarity Coolant

Adam Lipchitz, Glenn Harvel, T. Sunagawa
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031301.
Paper No: NERS-21-1079
https://doi.org/10.1115/1.4053632
Published Online: May 26, 2022
View Article titled, Thermophysical Characteristics of Liquid Metal In-Bi-Sn Eutectic (Field's Metal) as a Similarity Coolant
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Topics: Density, Liquid metals, Metals, Temperature, Thermal conductivity, Viscosity, Specific heat, Alloys
Journal Articles

Synergy of a Small Modular Reactor for Addressing Remote Communities Non-Nuclear Waste

Glenn Harvel
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031302.
Paper No: NERS-21-1100
https://doi.org/10.1115/1.4052808
Published Online: May 26, 2022
View Article titled, Synergy of a Small Modular Reactor for Addressing Remote Communities Non-Nuclear Waste
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Topics: Fuels, Heat, Nuclear power stations, Plastics, Pyrolysis, Small modular reactors, Heating, Syngas, Temperature, Biochar
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

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

Optimization of the European Sodium Fast Reactor Secondary Sodium Loop as Part of the ESFR-SMART Project

Joel Guidez, Janos Bodi, Konstantin Mikityuk, 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): 011323.
Paper No: NERS-21-1043
https://doi.org/10.1115/1.4052589
Published Online: October 29, 2021
View Article titled, Optimization of the European Sodium Fast Reactor Secondary Sodium Loop as Part of the ESFR-SMART Project
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Topics: Circuits, Safety, Sodium, Pumps, Pipes, Boilers, Industrial research, Optimization
Journal Articles

ESFR-SMART Core Safety Measures and Their Preliminary Assessment

Andrei Rineiski, Clément Mériot, Marco Marchetti, Jiri Krepel, Christine Coquelet-Pascal, Haileyesus Tsige-Tamirat, Francisco Álvarez-Velarde, 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): 011322.
Paper No: NERS-20-1130
https://doi.org/10.1115/1.4052588
Published Online: October 29, 2021
View Article titled, ESFR-SMART Core Safety Measures and Their Preliminary Assessment
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Topics: Fuels, Safety, Sodium, Sodium fast reactors, Design, Accidents
Journal Articles

A Heuristic for Designing Hybrid Compact Heat Exchangers for Nuclear Applications

Venkata Rajesh Saranam, Peter Carter, Kyle A. Rozman, Ömer N. Doğan, Brian K. Paul
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2022, 8(2): 021302.
Paper No: NERS-20-1185
https://doi.org/10.1115/1.4050421
Published Online: October 19, 2021
View Article titled, A Heuristic for Designing Hybrid Compact Heat Exchangers for Nuclear Applications
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Topics: Bonding, Creep, Design, Diffusion bonding (Metals), Fatigue, Heat exchangers, Rupture, Temperature, Stress, Pressure
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
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2022, 8(2): 021303.
Paper No: NERS-20-1207
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
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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
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2022, 8(2): 021301.
Paper No: NERS-20-1179
https://doi.org/10.1115/1.4051790
Published Online: October 19, 2021
View Article titled, Molecular Dynamics of Supercritical Water for Nuclear Data Development
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Topics: Molecular dynamics simulation, Simulation, Statistical process control, Water, Electromagnetic scattering, Radiation scattering, Scattering (Physics)
Journal Articles

Superphénix Benchmark Part I: Results of Static Neutronics

Alexander Ponomarev, Konstantin Mikityuk, Liang Zhang, Evgeny Nikitin, Emil Fridman, Francisco Álvarez-Velarde, Pablo Romojaro Otero, Antonio Jiménez-Carrascosa, Nuria García-Herranz, Ben Lindley, Una Baker, Armin Seubert, Romain Henry
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011320.
Paper No: NERS-21-1046
https://doi.org/10.1115/1.4051449
Published Online: October 8, 2021
View Article titled, Superphénix Benchmark Part I: Results of Static Neutronics
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Topics: Density, Fuels, Rods, Sodium, Temperature, Steel, Geometry, Cladding systems (Building), Neutrons, Chemical kinetics
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