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Jiri Krepel
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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

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

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
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011319.
Paper No: NERS-21-1051
https://doi.org/10.1115/1.4051798
Published Online: October 6, 2021
View Article titled, Decay Heat Characterization for the European Sodium Fast Reactor
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Topics: Heat, Cooling
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
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011316.
Paper No: NERS-21-1053
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

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
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011306.
Paper No: NERS-20-1156
https://doi.org/10.1115/1.4050479
Published Online: August 3, 2021
View Article titled, 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
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

Statistical Burnup Distribution of Moving Pebbles in the High-Temperature Reactor HTR-PM

Fanny Vitullo, Jiri Krepel, Jarmo Kalilainen, Horst-Michael Prasser, Andreas Pautz
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2020, 6(2): 021108.
Paper No: NERS-19-1059
https://doi.org/10.1115/1.4044910
Published Online: February 5, 2020
View Article titled, Statistical Burnup Distribution of Moving Pebbles in the High-Temperature Reactor HTR-PM
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Topics: Cross section (Physics), Fuels, Simulation, Temperature, Graphite, Neutron flux, Nuclear fission, Neutrons, High temperature, Flow (Dynamics)
Proceedings Papers

Statistical Burnup Distribution of Moving Pebbles in HTR-PM Reactor

Fanny Vitullo, Jiri Krepel, Jarmo Kalilainen, Horst-Michael Prasser, Andreas Pautz
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A005, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81082
https://doi.org/10.1115/ICONE26-81082
View Paper titled, Statistical Burnup Distribution of Moving Pebbles in HTR-PM Reactor
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Topics: China, Construction, Cross section (Physics), Discrete element methods, Engineering simulation, Flow (Dynamics), Fuels, High temperature, Matlab, Nuclear fuel cycle
Proceedings Papers

Analysis of Major Group Structures Used for Nuclear Reactor Simulations

Marco Di Filippo, Jiri Krepel, Konstantin Mikityuk, Horst-Michael Prasser
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A029, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81445
https://doi.org/10.1115/ICONE26-81445
View Paper titled, Analysis of Major Group Structures Used for Nuclear Reactor Simulations
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Topics: Nuclear reactors, Simulation, Cross section (Physics), Resolution (Optics), Fast neutron reactors, Isotopes
Journal Articles

Parametric Lattice Study of a Graphite-Moderated Molten Salt Reactor

Boris A. Hombourger, Jiří Křepel, Konstantin Mikityuk, Andreas Pautz
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. January 2015, 1(1): 011009.
Paper No: NERS-14-1038
https://doi.org/10.1115/1.4026401
Published Online: February 9, 2015
View Article titled, Parametric Lattice Study of a Graphite-Moderated Molten Salt Reactor
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Topics: Equilibrium (Physics), Fuels, Graphite, Molten salt reactors, Neutrons, Nuclear fuel cycle, Design, Nuclear fission, Uranium
Proceedings Papers

Molten Salt Reactor With Simplified Fuel Recycling and Delayed Carrier Salt Cleaning

Jiři Křepel, Valentyn Bykov, Konstantin Mikityuk, Boris Hombourger, Carlo Fiorina, Andreas Pautz
Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T05A015, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30396
https://doi.org/10.1115/ICONE22-30396
View Paper titled, Molten Salt Reactor With Simplified Fuel Recycling and Delayed Carrier Salt Cleaning
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Topics: Fuels, Molten salt reactors, Recycling, Cycles, Manufacturing, Matlab, Neutron flux, Neutrons, Nuclear fuel cycle, Safety
Proceedings Papers

A Procedure for the Pre-Conceptual Design of Fast Reactors and Application to a Gas-Cooled Sub-Critical Transmuter

Carlo Fiorina, Konstantin Mikityuk, Jiři Křepel
Proc. ASME. ICONE22, Volume 5: Innovative Nuclear Power Plant Design and New Technology Application; Student Paper Competition, V005T16A001, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30387
https://doi.org/10.1115/ICONE22-30387
View Paper titled, A Procedure for the Pre-Conceptual Design of Fast Reactors and Application to a Gas-Cooled Sub-Critical Transmuter
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Topics: Design, Fast neutron reactors, Pins (Engineering), Fuels, Equilibrium (Physics), Nuclear fuel cycle, Temperature, Cladding systems (Building), Matlab, Optimization
Proceedings Papers

Parametric Lattice Study of a Graphite-Moderated Molten Salt Reactor

Boris A. Hombourger, Jiři Křepel, Konstantin Mikityuk, Andreas Pautz
Proc. ASME. ICONE22, Volume 5: Innovative Nuclear Power Plant Design and New Technology Application; Student Paper Competition, V005T17A063, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-31050
https://doi.org/10.1115/ICONE22-31050
View Paper titled, Parametric Lattice Study of a Graphite-Moderated Molten Salt Reactor
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Topics: Graphite, Molten salt reactors, Cycles, Design, Equilibrium (Physics), Fuels, Optimization
Proceedings Papers

Molten Salt Fast Reactor Blanket Design and Proliferation Resistance Assessment

Valentyn Bykov, Jiři Křepel, Andreas Pautz
Proc. ASME. ICONE22, Volume 5: Innovative Nuclear Power Plant Design and New Technology Application; Student Paper Competition, V005T17A061, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-31026
https://doi.org/10.1115/ICONE22-31026
View Paper titled, Molten Salt Fast Reactor Blanket Design and Proliferation Resistance Assessment
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Topics: Cycles, Design, Fast neutron reactors, Fluids, Hazards, Irradiation (Radiation exposure), Isotopes, Molten salt reactors, Neutron flux, Uranium
Proceedings Papers

Analysis of the MSFR Core Neutronics Adopting Different Neutron Transport Models

Carlo Fiorina, Manuele Aufiero, Antonio Cammi, Claudia Guerrieri, Jiri Krepel, Lelio Luzzi, Konstantin Mikityuk, Marco Enrico Ricotti
Proc. ASME. ICONE20-POWER2012, Volume 5: Fusion Engineering; Student Paper Competition; Design Basis and Beyond Design Basis Events; Simple and Combined Cycles, 219-228, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54519
https://doi.org/10.1115/ICONE20-POWER2012-54519
View Paper titled, Analysis of the MSFR Core Neutronics Adopting Different Neutron Transport Models
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Topics: Neutrons, Diffusion (Physics), Feedback, Graphite, Molten salt reactors, Transients (Dynamics), Approximation, Combustion, Computer software, Design
Proceedings Papers

Preliminary Analysis of the MSFR Fuel Cycle Using Modified-EQL3D Procedure

Carlo Fiorina, Antonio Cammi, Jiri Krepel, Konstantin Mikityuk, Marco Enrico Ricotti
Proc. ASME. ICONE20-POWER2012, Volume 4: Codes, Standards, Licensing, and Regulatory Issues; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Instrumentation and Controls; Fuels and Combustion, Materials Handling, Emissions; Advanced Energy Systems and Renewables (Wind, Solar, Geothermal); Performance Testing and Performance Test Codes, 293-302, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54236
https://doi.org/10.1115/ICONE20-POWER2012-54236
View Paper titled, Preliminary Analysis of the MSFR Fuel Cycle Using Modified-EQL3D Procedure
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Topics: Nuclear fuel cycle, Fast neutron reactors, Fuels, Cycles, Isotopes, Manufacturing, Design, Equilibrium (Physics), Hazards, Molten salt reactors
Journal Articles

FAST Code System: Review of Recent Developments and Near-Future Plans

Konstantin Mikityuk, Jiri Krepel, Sandro Pelloni, Aurelia Chenu, Petr Petkevich, Rakesh Chawla
Journal: Journal of Engineering for Gas Turbines and Power
Publisher: ASME
Article Type: Research Papers
J. Eng. Gas Turbines Power. October 2010, 132(10): 102915.
https://doi.org/10.1115/1.4000336
Published Online: July 8, 2010
View Article titled, FAST Code System: Review of Recent Developments and Near-Future Plans
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Topics: Coolants, Equations of state, Flow (Dynamics), Fuels, Simulation, Sodium, Thermal hydraulics, Transients (Dynamics), Cycles, Heavy metals
Proceedings Papers

Thermophysical Analysis of the ADS Systems

Jiri Krepel
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 863-866, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22681
https://doi.org/10.1115/ICONE10-22681
View Paper titled, Thermophysical Analysis of the ADS Systems
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Topics: Diffusion (Physics), Heat, Neutron flux, Neutron sources, Temperature
Proceedings Papers

Development and Verification of Dynamics Code for Molten Salt Reactors

Jiri Krepel, Ulrich Grundmann, Ulrich Rohde
Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 1, 629-634, April 25–29, 2004
Publisher: American Society of Mechanical Engineers
Paper No: ICONE12-49130
https://doi.org/10.1115/ICONE12-49130
View Paper titled, Development and Verification of Dynamics Code for Molten Salt Reactors
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Topics: Dynamics (Mechanics), Molten salt reactors, Fuels, Transients (Dynamics), Fuel systems, Neutrons, Circuits, Design, Feedback, Flow (Dynamics)