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Journal Articles

Eddy Current Flow Meter Measurements in Liquid Sodium at High Temperatures

Accepted Manuscript
Nico Krauter, Alexandru Onea, Gunter Gerbeth, Sven Eckert
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-22-1185
DOI: https://doi.org/10.1115/1.4062239
Published Online: March 31, 2023
View Article titled, Eddy Current Flow Meter Measurements in Liquid Sodium at High Temperatures
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Topics: Eddies (Fluid dynamics), Eddy currents (Electricity), Flowmeters, High temperature, Sodium, Sensors, Flow (Dynamics), Liquid metals, Coolants, Engineering prototypes
Journal Articles

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

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
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041302.
Paper No: NERS-22-1136
DOI: https://doi.org/10.1115/1.4056854
Published Online: March 14, 2023
View Article titled, Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Study on Device Specifications
Click here to open pdf in another window PDF for Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Study on Device Specifications
Topics: Coolants, Flow (Dynamics), Fuels, Sodium, Temperature, Accidents, Transients (Dynamics), Pins (Engineering)
Journal Articles

On Some Differences of the Thermoelectrical Effects in BN-600 and Superphenix

Serguei Podobed
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. April 2022, 8(2): 024505.
Paper No: NERS-20-1167
DOI: https://doi.org/10.1115/1.4052591
Published Online: January 11, 2022
View Article titled, On Some Differences of the Thermoelectrical Effects in BN-600 and Superphenix
Click here to open pdf in another window PDF for On Some Differences of the Thermoelectrical Effects in BN-600 and Superphenix
Topics: Coolants, Currents, Design, Excitation, Liquid metals, Magnetic fields, Pressure, Sodium, Heat exchangers, Pumps
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
Article Type: Guest Editorial
ASME J of Nuclear Rad Sci. January 2022, 8(1): 010305.
Paper No: NERS-21-1121
DOI: 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
Click here to open pdf in another window PDF for Special Issue: EU ESFR-SMART ProjectWord From the Horizon: 2020 EU ESFR-SMART Project Coordinator
Topics: Safety, Sodium, Sodium fast reactors, Modeling
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
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011324.
Paper No: NERS-21-1031
DOI: 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)
Click here to open pdf in another window PDF for Experiment and Codes to Support Safety Assessments for Sodium Fast Reactors (KASOLA, SOLTEC and KARIFA)
Topics: Flow (Dynamics), Safety, Sodium, Temperature, Test facilities, Liquid metals, Boiling, Computational fluid dynamics, Fluids, Instrumentation
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
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011322.
Paper No: NERS-20-1130
DOI: 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

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
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011323.
Paper No: NERS-21-1043
DOI: 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
Click here to open pdf in another window PDF for Optimization of the European Sodium Fast Reactor Secondary Sodium Loop as Part of the ESFR-SMART Project
Topics: Circuits, Safety, Sodium, Pumps, Pipes, Boilers, Industrial research, Optimization
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
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011320.
Paper No: NERS-21-1046
DOI: 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
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011321.
Paper No: NERS-21-1052
DOI: 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

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

Hubert Delacroix, Frédéric Navacchia
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
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
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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
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
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
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Topics: Sodium, Cycles, Simulation
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
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011314.
Paper No: NERS-20-1204
DOI: 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

Analysis of ESFR Decay Heat Removal Systems in Protected Station Blackout

Janos Bodi, Alexander Ponomarev, Evaldas Bubelis, Konstantin Mikityuk
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
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
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Topics: Heat, Simulation, Sodium, Temperature, Design, Circuits, Flow (Dynamics)
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
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011313.
Paper No: NERS-20-1186
DOI: 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

New Reactor Safety Measures for the European Sodium Fast Reactor—Part I: Conceptual Design

Joel Guidez, Janos Bodi, Konstantin Mikityuk, Enrico Girardi, Bernard Carluec
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011311.
Paper No: NERS-20-1059
DOI: https://doi.org/10.1115/1.4051364
Published Online: August 12, 2021
View Article titled, New Reactor Safety Measures for the European Sodium Fast Reactor—Part I: Conceptual Design
Click here to open pdf in another window PDF for New Reactor Safety Measures for the European Sodium Fast Reactor—Part I: Conceptual Design
Topics: Heat, Safety, Sodium, Vessels, Pumps, Design, Natural convection, Roofs, Leakage, Water
Journal Articles

New Reactor Safety Measures for the European Sodium Fast Reactor—Part II: Preliminary Assessment

Joel Guidez, Janos Bodi, Konstantin Mikityuk, Enrico Girardi, Jeremy Bittan, Aleksander Grah, Haileyesus Tsige-Tamirat, Pablo Romojaro, Francisco Álvarez-Velarde, Bernard Carluec
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011312.
Paper No: NERS-20-1080
DOI: https://doi.org/10.1115/1.4051723
Published Online: August 12, 2021
View Article titled, New Reactor Safety Measures for the European Sodium Fast Reactor—Part II: Preliminary Assessment
Click here to open pdf in another window PDF for New Reactor Safety Measures for the European Sodium Fast Reactor—Part II: Preliminary Assessment
Topics: Cooling systems, Design, Heat, Heat transfer, Pumps, Safety, Sodium, Sodium fast reactors, Temperature, Vessels
Journal Articles

A Review of Models for the Sodium Boiling Phenomena in Sodium-Cooled Fast Reactor Subassemblies

Haileyesus Tsige-Tamirat, Sara Perez-Martin, Werner Pfrang, Marine Anderhuber, Antoine Gerschenfeld, Laurent Laborde, Konstantin Mikityuk, Christophe Peniguel, Stephane Mimouni
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011305.
Paper No: NERS-20-1117
DOI: https://doi.org/10.1115/1.4051066
Published Online: August 3, 2021
View Article titled, A Review of Models for the Sodium Boiling Phenomena in Sodium-Cooled Fast Reactor Subassemblies
Click here to open pdf in another window PDF for A Review of Models for the Sodium Boiling Phenomena in Sodium-Cooled Fast Reactor Subassemblies
Topics: Boiling, Sodium, Sodium fast reactors
Journal Articles

Evaluation of Sodium Boiling Models Using KNS-37 Loss of Flow Experiments

Sara Perez-Martin, Marine Anderhuber, Laurent Laborde, Nathalie Girault, Calogera Lombardo, Luca Ammirabile, Konstantin Mikityuk, Stephane Mimouni, Christophe Péniguel, Werner Pfrang
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011310.
Paper No: NERS-21-1049
DOI: https://doi.org/10.1115/1.4050769
Published Online: August 3, 2021
View Article titled, Evaluation of Sodium Boiling Models Using KNS-37 Loss of Flow Experiments
Click here to open pdf in another window PDF for Evaluation of Sodium Boiling Models Using KNS-37 Loss of Flow Experiments
Topics: Boiling, Coolants, Flow (Dynamics), Sodium, Sodium fast reactors, Temperature, Temperature profiles, Transients (Dynamics)
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
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011301.
Paper No: NERS-20-1056
DOI: 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
Click here to open pdf in another window PDF for Neutronic Analysis of the European Sodium Fast Reactor: Part I—Fresh Core Results
Topics: Modeling, Safety, Scram, Sodium, Sodium fast reactors, Temperature, Fuels, Design, Computers, Equilibrium (Physics)
Journal Articles

Preliminary Assessment of Decay Heat Removal Systems in the ESFR-SMART Design: The Role of Natural Air Convection Around Steam Generators Outer Shells in Accidental Conditions

Jeremy Bittan, Clement Bore, Joel Guidez
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2021, 7(4): 041301.
Paper No: NERS-20-1079
DOI: https://doi.org/10.1115/1.4048991
Published Online: April 16, 2021
View Article titled, Preliminary Assessment of Decay Heat Removal Systems in the ESFR-SMART Design: The Role of Natural Air Convection Around Steam Generators Outer Shells in Accidental Conditions
Click here to open pdf in another window PDF for Preliminary Assessment of Decay Heat Removal Systems in the ESFR-SMART Design: The Role of Natural Air Convection Around Steam Generators Outer Shells in Accidental Conditions
Topics: Boilers, Heat, Reactor vessels, Sodium, Temperature, Vessels, Shells, Design, Energy budget (Physics), Pumps