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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

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

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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

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

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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

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

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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

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

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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

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

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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

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

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Topics: Fuels, Safety, Sodium, Sodium fast reactors, Design, Accidents

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

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

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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

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

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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

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

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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

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

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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

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

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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

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

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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

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

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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

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

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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

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

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Topics: Cooling systems, Design, Heat, Heat transfer, Pumps, Safety, Sodium, Sodium fast reactors, Temperature, Vessels

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

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

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Topics: Boiling, Coolants, Flow (Dynamics), Sodium, Sodium fast reactors, Temperature, Temperature profiles, Transients (Dynamics)

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

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

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Topics: Boiling, Sodium, Sodium fast reactors

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

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

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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

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

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Topics: Boilers, Heat, Reactor vessels, Sodium, Temperature, Vessels, Shells, Design, Energy budget (Physics), Pumps

Journal Articles

Comparative Study of Physical Models for Particle Sedimentation Using SIMMER Code

Eszter Csengeri, Andrea Bachrata, Laurent Trotignon, Elsa Merle

ASME J of Nuclear Rad Sci. October 2021, 7(4): 041601.

Paper No: NERS-20-1122

DOI: https://doi.org/10.1115/1.4049197

Published Online: April 16, 2021

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Topics: Particulate matter, Sodium

Journal citation

NARROW

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

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

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

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

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

ESFR-SMART Core Safety Measures and Their Preliminary Assessment

Superphénix Benchmark Part I: Results of Static Neutronics

Superphénix Benchmark Part II: Transient Results

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

Evaluation of the ESFR End of Equilibrium Cycle State: Spatial Distributions of Reactivity Coefficients

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

Analysis of ESFR Decay Heat Removal Systems in Protected Station Blackout

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

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

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

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

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

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

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

Comparative Study of Physical Models for Particle Sedimentation Using SIMMER Code

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