Volume 8 Issue 1 | ASME J. of Nuclear Rad Sci.

Special Issue: EU ESFR-SMART Project

Editorial

Igor L. Pioro

ASME J of Nuclear Rad Sci. January 2022, 8(1): 010201. doi: https://doi.org/10.1115/1.4052829

Topics: China , Nuclear engineering , Radiation (Physics) , Nuclear reactors , Statistics , Switchable insulation systems

Reviewer's Recognition

ASME J of Nuclear Rad Sci. January 2022, 8(1): 010202. doi: https://doi.org/10.1115/1.4052667

Extract

View articletitled, Reviewer's Recognition

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Topics: User interfaces

Guest Editorial

The ASME Nuclear Engineering Division Celebrates the 7th Year of the Journal

Richard R. Schultz

ASME J of Nuclear Rad Sci. January 2022, 8(1): 010301. doi: https://doi.org/10.1115/1.4052787

Extract

View articletitled, The ASME Nuclear Engineering Division Celebrates the 7th Year of the Journal

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Topics: Nuclear engineering

Greetings From the Chair of the JSME Power Energy Systems Division (PESD)

Hisatsune Masakazu

ASME J of Nuclear Rad Sci. January 2022, 8(1): 010302. doi: https://doi.org/10.1115/1.4052666

Extract

View articletitled, Greetings From the Chair of the JSME Power Energy Systems Division (PESD)

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Topics: Energy / power systems , Japan Society of Mechanical Engineers

Guest Editorial by Gilles Rodriguez

Gilles Rodriguez

ASME J of Nuclear Rad Sci. January 2022, 8(1): 010303. doi: https://doi.org/10.1115/1.4052719

Extract

View articletitled, Guest Editorial by Gilles Rodriguez

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Topics: Carbon , Collaboration , Economics , Energy consumption , Heat , Hydrogen , Industrial capacity , Innovation , Manufacturing systems , Molten salt reactors

Professor Igor Leonardovich Pioro on His 65th Birthday

ASME J of Nuclear Rad Sci. January 2022, 8(1): 010304. doi: https://doi.org/10.1115/1.4052785

Extract

View articletitled, Professor Igor Leonardovich Pioro on His 65th Birthday

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Topics: Engineering teachers

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. doi: https://doi.org/10.1115/1.4052641

Extract

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

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Topics: Safety , Sodium , Sodium fast reactors , Modeling

History of the ESFR SMART Project

Joel Guidez

ASME J of Nuclear Rad Sci. January 2022, 8(1): 010306. doi: https://doi.org/10.1115/1.4050298

Extract

View articletitled, History of the ESFR SMART Project

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Topics: Safety , Sodium fast reactors , Design

Research Papers

Next Generation/Advanced Reactors

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. doi: https://doi.org/10.1115/1.4048905

Abstract

View articletitled, 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)

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

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011302. doi: https://doi.org/10.1115/1.4048765

Abstract

View articletitled, 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)

Eddy Current Flow Meter Performance in Liquid Metal Flows Inclined to the Sensor Axis

Nico Krauter, Vladimir Galindo, Thomas Wondrak, Sven Eckert, Gunter Gerbeth

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011303. doi: https://doi.org/10.1115/1.4050420

Abstract

View articletitled, Eddy Current Flow Meter Performance in Liquid Metal Flows Inclined to the Sensor Axis

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Topics: Eddies (Fluid dynamics) , Flow (Dynamics) , Flowmeters , Liquid metals , Sensors , Computer simulation

Safety Method for the Preconceptual Phase of Sodium-Cooled Fast Reactors

S. Ehster, L. Ammirabile, E. Bubelis, B. Carluec, J. B. Droin, E. Girardi

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011304. doi: https://doi.org/10.1115/1.4050766

Abstract

View articletitled, Safety Method for the Preconceptual Phase of Sodium-Cooled Fast Reactors

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Topics: Failure , Safety , Heat , Sodium fast reactors , Design , Defense industry , Performance , Accidents

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. doi: https://doi.org/10.1115/1.4051066

Abstract

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

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Topics: Boiling , Sodium , Sodium fast reactors

Burn-Up Dependent Modeling of Fuel-to-Clad Gap Conductance and Temperature Predictions for Mixed-Oxide Fuel in the ESFR-SMART Core

Jean Lavarenne, Evaldas Bubelis, Una Davies, Simone Gianfelici, Solène Gicquel, Jiri Krepel, Marc Lainet, Ben Lindley, Konstantin Mikityuk, Christophe Murphy, Benoit Perrin, Werner Pfrang, Alexander Ponomarev, Arndt Schubert, Eugene Shwageraus, Paul Van Uffelen

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011306. doi: https://doi.org/10.1115/1.4050479

Abstract

View articletitled, Burn-Up Dependent Modeling of Fuel-to-Clad Gap Conductance and Temperature Predictions for Mixed-Oxide Fuel in the ESFR-SMART Core

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Topics: Electrical conductance , Fuels , Temperature

Coupled Neutronics–Mechanics Analysis Method for Evaluation of Reactivity Change Due to Core Distortion in Sodium Fast Reactor

Janos Bodi, Alexander Ponomarev, Konstantin Mikityuk

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011307. doi: https://doi.org/10.1115/1.4050417

Abstract

View articletitled, Coupled Neutronics–Mechanics Analysis Method for Evaluation of Reactivity Change Due to Core Distortion in Sodium Fast Reactor

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Topics: Deformation , Displacement , Finite element analysis , Geometry , Manufacturing , Sodium fast reactors , Fuels , Simulation , Absorption

Ablation of a Solid Material by High-Temperature Liquid Jet Impingement: An Application to Corium Jet Impingement on a Sodium Fast Reactor Core-Catcher

Alexandre Lecoanet, Michel Gradeck, Xiaoyang Gaus-Liu, Thomas Cron, Beatrix Fluhrer, Frédéric Payot, Christophe Journeau, Nicolas Rimbert

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011308. doi: https://doi.org/10.1115/1.4051448

Abstract

View articletitled, Ablation of a Solid Material by High-Temperature Liquid Jet Impingement: An Application to Corium Jet Impingement on a Sodium Fast Reactor Core-Catcher

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Topics: Ablation (Vaporization technology) , Heat transfer , Melting , Sodium fast reactors , Cavities , High temperature , Ice , Design , Temperature , Water

Evaluation of the Passive Reactor Shutdown System Performance in European Sodium Fast Reactor

Evaldas Bubelis, Michael Schikorr, Konstantin Mikityuk

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011309. doi: https://doi.org/10.1115/1.4050563

Abstract

View articletitled, Evaluation of the Passive Reactor Shutdown System Performance in European Sodium Fast Reactor

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Topics: Rods , Sodium fast reactors , Transients (Dynamics) , Cooling , Circuits , Flow (Dynamics)

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. doi: https://doi.org/10.1115/1.4050769

Abstract

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

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

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. doi: https://doi.org/10.1115/1.4051364

Abstract

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

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Topics: Heat , Safety , Sodium , Vessels , Pumps , Design , Natural convection , Roofs , Leakage , Water

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. doi: https://doi.org/10.1115/1.4051723

Abstract

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

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

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. doi: https://doi.org/10.1115/1.4051514

Abstract

View articletitled, 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

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. doi: https://doi.org/10.1115/1.4051292

Abstract

View articletitled, 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

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. doi: https://doi.org/10.1115/1.4052190

Abstract

View articletitled, Analysis of ESFR Decay Heat Removal Systems in Protected Station Blackout

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Topics: Heat , Simulation , Sodium , Temperature , Design , Circuits , Flow (Dynamics)

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. doi: https://doi.org/10.1115/1.4052121

Abstract

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

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Topics: Sodium , Cycles , Simulation

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. doi: https://doi.org/10.1115/1.4052376

Abstract

View articletitled, 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

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

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011318. doi: https://doi.org/10.1115/1.4052306

Abstract

View articletitled, 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

Decay Heat Characterization for the European Sodium Fast Reactor

Antonio Jiménez-Carrascosa, Nuria García-Herranz, Jiri Krepel, Marat Margulis, Una Baker, Eugene Shwageraus, Emil Fridman, Robert Gregg

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011319. doi: https://doi.org/10.1115/1.4051798

Abstract

View articletitled, Decay Heat Characterization for the European Sodium Fast Reactor

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Topics: Heat , Cooling

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. doi: https://doi.org/10.1115/1.4051449

Abstract

View articletitled, 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

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. doi: https://doi.org/10.1115/1.4051877

Abstract

View articletitled, Superphénix Benchmark Part II: Transient Results

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Topics: Flow (Dynamics) , Fuels , Sodium , Temperature , Transients (Dynamics) , Modeling

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. doi: https://doi.org/10.1115/1.4052588

Abstract

View articletitled, ESFR-SMART Core Safety Measures and Their Preliminary Assessment

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

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. doi: https://doi.org/10.1115/1.4052589

Abstract

View articletitled, 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

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. doi: https://doi.org/10.1115/1.4052642

Abstract

View articletitled, 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