1-11 of 11
Carlo Fiorina
Close
Save search
Follow your search
Access your saved searches in your account
Would you like to receive an alert when new items match your search?
Close Modal
Sort by
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
Open the PDF for Impact of Thermal-Hydraulic Feedback and Differential Thermal Expansion on European Sodium-Cooled Fast Reactor Core Power Distribution in another window
Topics: Coolants, Density, Feedback, Fuels, Sodium fast reactors, Temperature, Thermal expansion, Manufacturing, Electrical conductance, Heat
Proceedings Papers

Creation of an OpenFOAM Fuel Performance Class Based on FRED and Integration Into the GeN-Foam Multi-Physics Code

Carlo Fiorina, Andreas Pautz, Konstantin Mikityuk
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A027, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81574
https://doi.org/10.1115/ICONE26-81574
View Paper titled, Creation of an OpenFOAM Fuel Performance Class Based on FRED and Integration Into the GeN-Foam Multi-Physics Code
Open the PDF for Creation of an OpenFOAM Fuel Performance Class Based on FRED and Integration Into the GeN-Foam Multi-Physics Code in another window
Topics: Fuels, Physics, Computational fluid dynamics, Nuclear engineering, Nuclear fuels, Sodium fast reactors
Proceedings Papers

First Steps Towards the Development of a 3D Nuclear Fuel Behavior Solver With OpenFOAM

Alessandro Scolaro, Ivor Clifford, Carlo Fiorina, Andreas Pautz
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A051, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82381
https://doi.org/10.1115/ICONE26-82381
View Paper titled, First Steps Towards the Development of a 3D Nuclear Fuel Behavior Solver With OpenFOAM
Open the PDF for First Steps Towards the Development of a 3D Nuclear Fuel Behavior Solver With OpenFOAM in another window
Topics: Nuclear fuels, Temperature, Electrical conductance, Fuels, Materials properties, Cracking (Materials), Creep, Databases, Fracture (Process), Fuel rods
Proceedings Papers

CFD-Based Correlation for Forced Convection Heat Transfer in Circular Ducts of Internally Heated Molten Salts

Francesco Di Lecce, Sandra Dulla, Piero Ravetto, Antonio Cammi, Stefano Lorenzi, Carlo Fiorina
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A062, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82507
https://doi.org/10.1115/ICONE26-82507
View Paper titled, CFD-Based Correlation for Forced Convection Heat Transfer in Circular Ducts of Internally Heated Molten Salts
Open the PDF for CFD-Based Correlation for Forced Convection Heat Transfer in Circular Ducts of Internally Heated Molten Salts in another window
Topics: Computational fluid dynamics, Ducts, Forced convection, Heat, Heat transfer, Molten salt reactors, Flow (Dynamics), Fluid dynamics, Fuels, Internal flow
Proceedings Papers

A Simplified Numerical Benchmark for Pool-Type Sodium Fast Reactors

Stefan Radman, Carlo Fiorina, Konstantin Mikityuk, Andreas Pautz
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A018, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82260
https://doi.org/10.1115/ICONE26-82260
View Paper titled, A Simplified Numerical Benchmark for Pool-Type Sodium Fast Reactors
Open the PDF for A Simplified Numerical Benchmark for Pool-Type Sodium Fast Reactors in another window
Topics: Sodium fast reactors, Physics, Modeling, Geometry, Neutrons, Simulation, Testing, Thermal hydraulics
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
Open the PDF for Molten Salt Reactor With Simplified Fuel Recycling and Delayed Carrier Salt Cleaning in another window
Topics: Fuels, Molten salt reactors, Recycling, Cycles, Manufacturing, Matlab, Neutron flux, Neutrons, Nuclear fuel cycle, Safety
Proceedings Papers

A Time-Dependent Solver for Coupled Neutron-Transport Thermal-Mechanics Calculations and Simulation of a Godiva Prompt-Critical Burst

Carlo Fiorina, Manuele Aufiero, Sandro Pelloni, Konstantin Mikityuk
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T11A008, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30395
https://doi.org/10.1115/ICONE22-30395
View Paper titled, A Time-Dependent Solver for Coupled Neutron-Transport Thermal-Mechanics Calculations and Simulation of a Godiva Prompt-Critical Burst
Open the PDF for A Time-Dependent Solver for Coupled Neutron-Transport Thermal-Mechanics Calculations and Simulation of a Godiva Prompt-Critical Burst in another window
Topics: Neutrons, Simulation, Transients (Dynamics), Uranium, Collaboration, Computer software, Fluid dynamics, Manufacturing, Physics, Slabs
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
Open the PDF for A Procedure for the Pre-Conceptual Design of Fast Reactors and Application to a Gas-Cooled Sub-Critical Transmuter in another window
Topics: Design, Fast neutron reactors, Pins (Engineering), Fuels, Equilibrium (Physics), Nuclear fuel cycle, Temperature, Cladding systems (Building), Matlab, Optimization
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
Open the PDF for Analysis of the MSFR Core Neutronics Adopting Different Neutron Transport Models in another window
Topics: Neutrons, Diffusion (Physics), Feedback, Graphite, Molten salt reactors, Transients (Dynamics), Approximation, Combustion, Computer software, Design
Proceedings Papers

A Preliminary Study of the MSFR Dynamics

Claudia Guerrieri, Manuele Aufiero, Antonio Cammi, Carlo Fiorina, Lelio Luzzi
Proc. ASME. ICONE20-POWER2012, Volume 5: Fusion Engineering; Student Paper Competition; Design Basis and Beyond Design Basis Events; Simple and Combined Cycles, 229-238, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54521
https://doi.org/10.1115/ICONE20-POWER2012-54521
View Paper titled, A Preliminary Study of the MSFR Dynamics
Open the PDF for A Preliminary Study of the MSFR Dynamics in another window
Topics: Dynamics (Mechanics), Molten salt reactors, Neutrons, Fast neutron reactors, Graphite, Safety, Transients (Dynamics), Circuits, Coolants, Dynamic response
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
Open the PDF for Preliminary Analysis of the MSFR Fuel Cycle Using Modified-EQL3D Procedure in another window
Topics: Nuclear fuel cycle, Fast neutron reactors, Fuels, Cycles, Isotopes, Manufacturing, Design, Equilibrium (Physics), Hazards, Molten salt reactors