HR job title
- Associate Professor
- Contact Info
Fiorina, Carlo Associate Professor
Positions
- Associate Professor, Nuclear Engineering, College of Engineering
- Overview
- Publications
- Teaching
- Background
- Contact
- Other
- View All
Overview
Publications
selected publications
-
academic article
-
Guilbaud, T., Fiorina, C., Lorenzi, S., Scolaro, A., Carminati, F., Maire, D., & Pautz, A.
(2024).
Investigating the Functional Mock-up Interface as a Coupling Framework for the multi-fidelity analysis of nuclear reactors. PROGRESS IN NUCLEAR ENERGY.
169, 105022-105022.
-
Habtemariam, N., Fiorina, C., Lorenzi, S., & Cammi, A.
(2024).
On the need for multi-dimensional models for the safety analysis of (fast-spectrum) Molten Salt Reactors. Annals of Nuclear Energy.
197, 110237-110237.
-
Guilbaud, T., Fiorina, C., Pautz, A., & Carminati, F.
(2024).
Preliminary safety analysis of the TRANSMUTEX sub-critical reactor using the GeN-Foam multi-physics solver. PROGRESS IN NUCLEAR ENERGY.
168, 104980-104980.
-
Niu, Y., Alessandro, S., Fiorina, C., Qin, H., Lazare, G., Wu, Y., Tian, W., & Su, G. H.
(2024).
Extension of GeN-Foam to departure from nucleate boiling prediction and validation against the OECD/NRC PSBT benchmark. Nuclear Engineering and Design.
416, 112748-112748.
-
Qin, H., Fiorina, C., Zhang, R., Radman, S., Zhang, D., Wang, C., ... Su, G. H.
(2023).
Extension of GeN-Foam to modeling of boiling water and validation against the OECD/NRC PSBT benchmark. Nuclear Engineering and Design.
408, 112320-112320.
-
Lindley, B., Velarde, F. A., Baker, U., Bodi, J., Cosgrove, P., Charles, A., ... Tollit, B.
(2023).
Impact of Thermal-Hydraulic Feedback and Differential Thermal Expansion on European Sodium-Cooled Fast Reactor Core Power Distribution. Journal of Nuclear Engineering and Radiation Science.
9(3),
-
Brunetto, E. L., Scolaro, A., Fiorina, C., & Pautz, A.
(2023).
Extension of the OFFBEAT fuel performance code to finite strains and validation against LOCA experiments. Nuclear Engineering and Design.
406, 112232-112232.
-
Scolaro, A., Van Uffelen, P., Schubert, A., Fiorina, C., Brunetto, E., Clifford, I., & Pautz, A.
(2022).
Towards coupling conventional with high-fidelity fuel behavior analysis tools. 152, 104357-104357.
-
Radman, S., Fiorina, C., Song, P., & Pautz, A.
(2022).
Development of a point-kinetics model in OpenFOAM, integration in GeN-Foam, and validation against FFTF experimental data. Annals of Nuclear Energy.
168, 108891-108891.
-
German, P., Tano, M., Fiorina, C., & Ragusa, J. C.
(2022).
GeN-ROM-An OpenFOAM(R)-based multiphysics reduced-order modeling framework for the analysis of Molten Salt Reactors. 146, 104148-104148.
-
Mager, T., Fiorina, C., Hursin, M., & Pautz, A.
(2022).
Investigation and Validation of Unstructured Mesh Methodologies for Modeling Experimental Reactors. Energies.
15(4), 1512-1512.
-
Fiorina, C., Clifford, I., Kelm, S., & Lorenzi, S.
(2022).
On the development of multi-physics tools for nuclear reactor analysis based on OpenFOAM: state of the art, lessons learned and perspectives. Nuclear Engineering and Design.
387, 111604-111604.
-
Scolaro, A., Fiorina, C., Clifford, I., & Pautz, A.
(2022).
Development of a semiimplicit contact methodology for finite volume stress solvers. International Journal for Numerical Methods in Engineering.
123(2), 309-338.
-
Radman, S., Fiorina, C., & Pautz, A.
(2021).
Development of a novel two-phase flow solver for nuclear reactor analysis: Validation against sodium boiling experiments. Nuclear Engineering and Design.
384, 111422-111422.
-
Radman, S., Fiorina, C., & Pautz, A.
(2021).
Development of a novel two-phase flow solver for nuclear reactor analysis: algorithms, verification and implementation in OpenFOAM. Nuclear Engineering and Design.
379, 111178-111178.
-
German, P., Tano, M. E., Fiorina, C., & Ragusa, J. C.
(2021).
Data-Driven Reduced-Order Modeling of Convective Heat Transfer in Porous Media. 6(8), 266-266.
-
Scolaro, A., Van Uffelen, P., Fiorina, C., Schubert, A., Clifford, I., & Pautz, A.
(2021).
Investigation on the effect of eccentricity for fuel disc irradiation tests. Nuclear Engineering and Technology.
53(5), 1602-1611.
-
Lamirand, V., Rais, A., Pakari, O., Hursin, M., Laureau, A., Pohlus, J., ... Pautz, A.
(2021).
ANALYSIS OF THE FIRST COLIBRI FUEL RODS OSCILLATION CAMPAIGN IN THE CROCUS REACTOR FOR THE EUROPEAN PROJECT CORTEX. EPJ Web of Conferences.
247, 21010-21010.
-
Mylonakis, A. G., Demazire, C., Vinai, P., Lamirand, V., Rais, A., Pakari, O., ... Pautz, A.
(2021).
CORE SIM+ SIMULATIONS OF COLIBRI FUEL RODS OSCILLATION EXPERIMENTS AND COMPARISON WITH MEASUREMENTS. EPJ Web of Conferences.
247, 21006-21006.
-
Nikitin, E., Fridman, E., Mikityuk, K., Radman, S., & Fiorina, C.
(2021).
NEUTRONIC MODELLING OF THE FFTF CONTROL ROD WORTH MEASUREMENTS WITH DIFFUSION CODES. EPJ Web of Conferences.
247, 10017-10017.
-
German, P., Tano, M., Ragusa, J. C., & Fiorina, C.
(2020).
Comparison of Reduced-Basis techniques for the model order reduction of parametric incompressible fluid flows. 130, 103551-103551.
-
Altahhan, M. R., Bhaskar, S., Ziyad, D., Balestra, P., Fiorina, C., Hou, J., Smith, N., & Avramova, M.
(2020).
Preliminary design and analysis of Liquid Fuel Molten Salt Reactor using multi-physics code GeN-Foam. Nuclear Engineering and Design.
369, 110826-110826.
-
Fiorina, C., Scolaro, A., Siefman, D., Hursin, M., & Pautz, A.
(2020).
Artificial Neural Networks as Surrogate Models for Uncertainty Quantification and Data Assimilation in 2-D/3-D Fuel Performance Studies. 1(1), 54-62.
-
Scolaro, A., Clifford, I., Fiorina, C., & Pautz, A.
(2020).
The OFFBEAT multi-dimensional fuel behavior solver. Nuclear Engineering and Design.
358, 110416-110416.
-
Lamirand, V., Rais, A., Hbner, S., Lange, C., Pohlus, J., Paquee, U., ... Pautz, A.
(2020).
Neutron noise experiments in the AKR-2 and CROCUS reactors for the European project CORTEX. EPJ Web of Conferences.
225, 04023-04023.
-
Lamirand, V., Frajtag, P., Godat, D., Pakari, O., Laureau, A., Rais, A., ... Pautz, A.
(2020).
The COLIBRI experimental program in the CROCUS reactor: characterization of the fuel rods oscillator. EPJ Web of Conferences.
225, 04020-04020.
-
German, P., Tano, M., Ragusa, J. C., & Fiorina, C.
(2020).
Comparison of Reduced-Basis techniques for the model order reduction of parametric incompressible fluid flows. 130.
-
Radman, S., Fiorina, C., Mikityuk, K., & Pautz, A.
(2019).
A coarse-mesh methodology for modelling of single-phase thermal-hydraulics of ESFR innovative assembly design. Nuclear Engineering and Design.
355, 110291-110291.
-
Fiorina, C.
(2019).
Impact of the volume heat source on the RANS-based CFD analysis of Molten Salt Reactors. Annals of Nuclear Energy.
134, 376-382.
-
German, P., Ragusa, J. C., & Fiorina, C.
(2019).
Application of multiphysics model order reduction to doppler/neutronic feedback. 5(17), 17-17.
-
Brovchenko, M., Kloosterman, J., Luzzi, L., Merle, E., Heuer, D., Laureau, A., ... Merk, B.
(2019).
Neutronic benchmark of the molten salt fast reactor in the frame of the EVOL and MARS collaborative projects. EPJ Nuclear Sciences & Technologies.
5, 2-2.
-
Fiorina, C., Radman, S., Scolaro, A., & Pautz, A.
(2018).
A reduced order accelerator for time-dependent segregated neutronic solvers. Annals of Nuclear Energy.
121, 177-185.
-
Fiorina, C., Hursin, M., & Pautz, A.
(2017).
Extension of the GeN-Foam neutronic solver to SP3 analysis and application to the CROCUS experimental reactor. Annals of Nuclear Energy.
101, 419-428.
-
Fiorina, C., Kerkar, N., Mikityuk, K., Rubiolo, P., & Pautz, A.
(2016).
Development and verification of the neutron diffusion solver for the GeN-Foam multi-physics platform. Annals of Nuclear Energy.
96, 212-222.
-
Degueldre, C., & Fiorina, C.
(2016).
The proto-Earth geo-reactor: Reassessing the hypotheses. 1(2), 49-63.
-
Lindley, B. A., Fiorina, C., Gregg, R., Franceschini, F., & Parks, G. T.
(2016).
The effectiveness of full actinide recycle as a nuclear waste management strategy when implemented over a limited timeframe Part II: Thorium fuel cycle. 87, 144-155.
-
Fiorina, C., Clifford, I., Aufiero, M., & Mikityuk, K.
(2015).
GeN-Foam: a novel OpenFOAM based multi-physics solver for 2D/3D transient analysis of nuclear reactors. Nuclear Engineering and Design.
294, 24-37.
-
Lindley, B. A., Fiorina, C., Gregg, R., Franceschini, F., & Parks, G. T.
(2015).
The effectiveness of full actinide recycle as a nuclear waste management strategy when implemented over a limited timeframe Part I: Uranium fuel cycle. 85, 498-510.
-
Zanetti, M., Cammi, A., Fiorina, C., & Luzzi, L.
(2015).
A Geometric Multiscale modelling approach to the analysis of MSR plant dynamics. 83, 82-98.
-
Lindley, B. A., Fiorina, C., Franceschini, F., Lahoda, E. J., & Parks, G. T.
(2014).
Thorium breeder and burner fuel cycles in reduced-moderation LWRs compared to fast reactors. 77, 107-123.
-
Fiorina, C., Cammi, A., Luzzi, L., Mikityuk, K., Ninokata, H., & Ricotti, M. E.
(2014).
Thermal-hydraulics of internally heated molten salts and application to the Molten Salt Fast Reactor. Journal of Physics : Conference Series.
501(1), 012030-012030.
-
Krepel, J., Hombourger, B., Fiorina, C., Mikityuk, K., Rohde, U., Kliem, S., & Pautz, A.
(2014).
Fuel cycle advantages and dynamics features of liquid fueled MSR. 64, 380-397.
-
Fiorina, C., Lathouwers, D., Aufiero, M., Cammi, A., Guerrieri, C., Kloosterman, J. L., Luzzi, L., & Ricotti, M. E.
(2014).
Modelling and analysis of the MSFR transient behaviour. Annals of Nuclear Energy.
64, 485-498.
-
Fiorina, C., Stauff, N. E., Franceschini, F., Wenner, M. T., Stanculescu, A., Kim, T. K., ... Salvatores, M.
(2013).
Comparative analysis of thorium and uranium fuel for transuranic recycle in a sodium cooled Fast Reactor. Annals of Nuclear Energy.
62, 26-39.
-
Aufiero, M., Cammi, A., Fiorina, C., Leppanen, J., Luzzi, L., & Ricotti, M. E.
(2013).
An extended version of the SERPENT-2 code to investigate fuel burn-up and core material evolution of the Molten Salt Fast Reactor. 441(1-3), 473-486.
-
Fiorina, C., Aufiero, M., Cammi, A., Franceschini, F., Krepel, J., Luzzi, L., Mikityuk, K., & Ricotti, M. E.
(2013).
Investigation of the MSFR core physics and fuel cycle characteristics. 68, 153-168.
-
Aufiero, M., Cammi, A., Fiorina, C., Luzzi, L., & Sartori, A.
(2013).
A multi-physics time-dependent model for the Lead Fast Reactor single-channel analysis. Nuclear Engineering and Design.
256, 14-27.
-
Fiorina, C., Krepel, J., Cammi, A., Franceschini, F., Mikityuk, K., & Ricotti, M. E.
(2013).
Analysis of thorium and uranium fuel cycles in an iso-breeder lead fast reactor using extended-EQL3D procedure. Annals of Nuclear Energy.
53, 492-506.
-
Cammi, A., Fiorina, C., Guerrieri, C., & Luzzi, L.
(2012).
Dimensional effects in the modelling of MSR dynamics: Moving on from simplified schemes of analysis to a multi-physics modelling approach. Nuclear Engineering and Design.
246, 12-26.
-
Luzzi, L., Cammi, A., Di Marcello, V., & Fiorina, C.
(2010).
An approach for the modelling and the analysis of the MSR thermo-hydrodynamic behaviour. Chemical Engineering Science.
65(16), 4873-4883.
-
Guilbaud, T., Fiorina, C., Lorenzi, S., Scolaro, A., Carminati, F., Maire, D., & Pautz, A.
(2024).
Investigating the Functional Mock-up Interface as a Coupling Framework for the multi-fidelity analysis of nuclear reactors. PROGRESS IN NUCLEAR ENERGY.
169, 105022-105022.
-
chapter
-
Fiorina, C.
(2021).
Advanced Modeling and Simulation Methods. Encyclopedia of Nuclear Energy.
(pp. 837-850).
Elsevier.
-
Fiorina, C.
(2019).
GEN-FOAM: An OpenFOAM-Based Multi-physics Solver for Nuclear Reactor Analysis. OpenFOAM.
(pp. 211-221).
Springer Nature.
-
Krepel, J., Hombourger, B., Fiorina, C., Nichenko, S., Kalilainen, J., Burgherr, P., Prasser, H., & Pautz, A.
(2019).
Molten Salt Reactor Research in Switzerland. Thorium Energy for the Future.
(pp. 455-468).
Springer Nature.
-
Krepel, J., Hombourger, B., Bykov, V., Fiorina, C., Mikityuk, K., & Pautz, A.
(2016).
Paul Scherrer Institutes Studies on Advanced Molten Salt Reactor Fuel Cycle Options. Thorium Energy for the World.
(pp. 185-192).
Springer Nature.
-
Degueldre, C., & Fiorina, C.
(2016).
The Proto-Earth Georeactor: A Thorium Reactor?. Thorium Energy for the World.
(pp. 415-416).
Springer Nature.
-
Luzzi, L., Aufiero, M., Cammi, A., & Fiorina, C.
(2012).
Thermo-Hydrodynamics of Internally Heated Molten Salts for Innovative Nuclear Reactors. Hydrodynamics - Theory and Model.
IntechOpen.
-
Fiorina, C.
(2021).
Advanced Modeling and Simulation Methods. Encyclopedia of Nuclear Energy.
(pp. 837-850).
Elsevier.
-
conference paper
-
Habtemariam, N., Fiorina, C., Reyes, S., & Schunert, S.
(2023).
Simulation of Gas Dynamics in the Chamber of Inertial Fusion Energy Systems Using State-of-the-Art Numerical Libraries. 276-279.
-
Morelova, N., Kriventsev, V., Sumner, T., Moisseytsev, A., Heidet, F., Wootan, D., ... Martelli, D.
(2023).
IAEA's Coordinated Research Projects and Activities on Thermal Hydraulics of Fast Reactors
-
Scolaro, A., Brunetto, E., & Fiorina, C.
(2023).
Modeling of Zircaloy Oxidation Through Dynamic Mesh Deformation
-
Cornet, A., Brunetto, E., Scolaro, A., Fiorina, C., & Pautz, A.
(2023).
Application of the OFFBEAT Fuel Performance Code to IAEA Verification Exercises on LMFBR Core Bowing
-
Fiorina, C., Habtemariam, N., Lorenzi, S., Scolaro, A., Guilbaud, T., & Alfonsi, A.
(2023).
The Functional Mock-Up Interface as a Unified Framework to Enable Multi-Scale, Multi-Fidelity and Control-Oriented Simulations of Nuclear Reactors
-
Mager, T., Hursin, M., Fiorina, C., & Pautz, A.
(2023).
Verification of the High Fidelity Model of the CROCUS Experimental Reactor
-
Guilbaud, T., Fiorina, C., & Pautz, A.
(2023).
FMI-based multi-fidelity transient analysis of a lead-cooled fast reactor using GeN-Foam and OpenModelica. Transactions of the American Nuclear Society.
-
Guilbaud, T., & Fiorina, C.
(2023).
Multi-physics modeling of the KIWI-B-4E Nuclear Thermal Propulsion system using OpenMC and GeN-Foam: preliminary assessment against experimental data. Transactions of the American Nuclear Society.
-
Habtemariam, N., Fiorina, C., & Lorenzi, S.
(2023).
Investigation of Dimensional Effects in the Modeling of Fast-Spectrum MSRs. Transactions of the American Nuclear Society.
728-731.
-
Morelova, N., Kriventsev, V., Fiorina, C., Clifford, I., Kelm, S., Lorenzi, S., ... Forget, B.
(2023).
IAEA Initiative on Open-Source Nuclear Codes for Reactor Analysis. The Proceedings of the International Conference on Nuclear Engineering (ICONE).
1639-1639.
-
Morelova, N., Kriventsev, V., Sumner, T., Moisseytsev, A., Heidet, F., Wootan, D. W., ... Lane, J.
(2023).
IAEAS Coordinated Research Projects on Thermal Hydraulics of Fast Reactors. The Proceedings of the International Conference on Nuclear Engineering (ICONE).
1632-1632.
-
Robert, Y., Jantzen, L., Siaraferas, T., Fiorina, C., & Fratoni, M.
(2023).
Impact of Thermal Coupling on a Pebblebed Reactor Equilibrium from Hyper-Fidelity Depletion. 1490-1490.
-
Fiorina, C.
(2022).
The GeN-Foam Multiphysics Solver: A Status Update
-
Fiorina, C., Scolaro, A., Siefman, D., Hursin, M., & Pautz, A.
(2022).
Bayesian Data Assimilation for Fuel Performance Based on OFFBEAT. 3656-3665.
-
Brunetto, E., Scolaro, A., Fiorina, C., & Pautz, A.
(2022).
Development in OFFBEAT of a Dynamic-Mesh Incremental Stress-Strain Solver and Validation Against the IFA 650.2 Ballooning Experiment. 401-408.
-
Mager, T., Hursin, M., Fiorina, C., & Pautz, A.
(2022).
Development of a High Fidelity Model of the CROCUS Experimental Reactor. 946-956.
-
Brunetto, E., Scolaro, A., Fiorina, C., & Pautz, A.
(2022).
Implementation of a Multidimensional Diffusion-Based Neutronics Solver in OFFBEAT. 462-466.
-
Scolaro, A., Fiorina, C., Clifford, I., Brunetto, E., & Pautz, A.
(2022).
Pre-Release Validation Database for the Multi-Dimensional Fuel Performance Code OFFBEAT. 2914-2923.
-
Gianasello, A., Scolaro, A., & Fiorina, C.
(2022).
Simulation of fission gas release in the 3D fuel performance code OFFBEAT
-
Mattioli, A. S., Fiorina, C., Lorenzi, S., & Cammi, A.
(2021).
Derivation and implementation in OpenFOAM of a point-kinetics model for Molten Salt Reactors. Transactions of the American Nuclear Society.
-
Zhang, R., Fiorina, C., Radman, S., & Qiu, S.
(2021).
Preliminary thermal-hydraulics analysis of SFR assembly windows under sodium boiling transients. Transactions of the American Nuclear Society.
1332-1335.
-
Fiorina, C., Sherwise, P., Dufresne, A., Ragusa, J., Ivanov, K., Valentine, T., ... Clifford, I.
(2021).
An Initiative For The Development And Application Of Open-Source Multi-Physics Simulation In Support Of R&D And E&T In Nuclear Science And Technology. EPJ Web of Conferences.
02040-02040.
-
German, P., Tano, M., Ragusa, J., & Fiorina, C.
(2021).
Reduced-Order Modeling of Parameterized Transient Flows in Closed-Lloop Systems. EPJ Web of Conferences.
06055-06055.
-
Scolaro, A., Fiorina, C., Clifford, I., & Pautz, A.
(2021).
Multi-Dimensional Creep Analysis Using the Novel Offbeat Fuel Performance Code. 226-235.
-
Mager, T., Fiorina, C., Hursin, M., & Pautz, A.
(2021).
Validation of the GeN-Foam model of the CROCUS experimental reactor
-
Ambrozic, K., Lamirand, V. P., Hubner, S., Hursin, M., Rais, A., Pakari, O. V., ... Pautz, A.
(2020).
Noise analysis techniques of in-core modulation experiments of the European CORTEX project. 212.1 - 212.8-212.1 - 212.8.
-
Fiorina, C.
(2019).
Cladding plasticity modeling with the multidimensional fuel performance code OFFBEAT. 47-55.
-
Scolaro, A., Yves, R., Fiorina, C., Clifford, I., & Pautz, A.
(2019).
Coupling methodology for the multidimensional fuel performance code offbeat and the Monte Carlo neutron transport code SERPENT
-
Fiorina, C., Radman, S., Koc, M., & Pautz, A.
(2019).
Detailed modelling of the expansion reactivity feedback in fast reactors using OpenFOAM. Transactions of the American Nuclear Society.
1434-1442.
-
German, P., Ragusa, J., Fiorina, C., & Tano, M.
(2019).
Reduced-Order Modeling of Parametrized Multi-Physics Computations for the Molten Salt Fast Reactor
-
Fiorina, C., Radman, S., & Pautz, A.
(2019).
Preliminary application of the GeN-Foam multiphysics tool to the analysis of the FFTF sodium fast reactor: coupling thermal-hydraulics and core deformations. Transactions of the American Nuclear Society.
5680-5690.
-
Fiorina, C.
(2019).
Preliminary development of a coarse-mes h sodium boiling model for openfoam-based multi-physics solvers. 1093-1106.
-
German, P., Tano, M., Ragusa, J., & Fiorina, C.
(2019).
Reduced-Order Modeling of Fluid Flows in Closed-Loop Systems. 1762-1764.
-
Altahhan, M., Bhaskar, S., Balestra, P., Hou, J., Avramova, M., Smith, N., & Fiorina, C.
(2018).
3D Coupled Transient simulation of a fast liquid fuel molten salt reactor primary loop using GeN-Foam
-
Radman, S., Fiorina, C., Mikityuk, K., & Pautz, A.
(2018).
A Simplified Numerical Benchmark for Pool-Type Sodium Fast Reactors. v004t15a018-v004t15a018.
-
Fiorina, C., Pautz, A., & Mikityuk, K.
(2018).
Creation of an OpenFOAM Fuel Performance Class Based on FRED and Integration Into the GeN-Foam Multi-Physics Code. v003t02a027-v003t02a027.
-
Scolaro, A., Clifford, I., Fiorina, C., & Pautz, A.
(2018).
First Steps Towards the Development of a 3D Nuclear Fuel Behavior Solver With OpenFOAM. v003t02a051-v003t02a051.
-
Di-Lecce, F., Dulla, S., Ravetto, P., Cammi, A., Lorenzi, S., & Fiorina, C.
(2018).
CFD-Based Correlation for Forced Convection Heat Transfer in Circular Ducts of Internally Heated Molten Salts. v06bt08a062-v06bt08a062.
-
Radman, S., Fiorina, C., & Pautz, A.
(2017).
Investigation of Partial Coolant Flow Blockage in a Sodium Fast Reactor Assembly with Coarse-mesh Methodologies
-
Fiorina, C., & Pautz, A.
(2016).
Status and Ongoing Developments for the GeN-Foam Multi-Physics Solver. Transactions of the American Nuclear Society.
1106-1109.
-
Fiorina, C., Aufiero, M., Pelloni, S., & Mikityuk, K.
(2014).
A Time-Dependent Solver for Coupled Neutron-Transport Thermal-Mechanics Calculations and Simulation of a Godiva Prompt-Critical Burst. v004t11a008-v004t11a008.
-
Fiorina, C., Mikityuk, K., & Krepel, J.
(2014).
A Procedure for the Pre-Conceptual Design of Fast Reactors and Application to a Gas-Cooled Sub-Critical Transmuter. v005t16a001-v005t16a001.
-
Krepel, J., Bykov, V., Mikityuk, K., Hombourger, B., Fiorina, C., & Pautz, A.
(2014).
Molten Salt Reactor With Simplified Fuel Recycling and Delayed Carrier Salt Cleaning. v003t05a015-v003t05a015.
-
Guerrieri, C., Aufiero, M., Cammi, A., Fiorina, C., & Luzzi, L.
(2012).
A Preliminary Study of the MSFR Dynamics. 229-238.
-
Fiorina, C., Aufiero, M., Cammi, A., Guerrieri, C., Krepel, J., Luzzi, L., Mikityuk, K., & Ricotti, M. E.
(2012).
Analysis of the MSFR Core Neutronics Adopting Different Neutron Transport Models. 219-228.
-
Fiorina, C., Cammi, A., Krepel, J., Mikityuk, K., & Ricotti, M. E.
(2012).
Preliminary Analysis of the MSFR Fuel Cycle Using Modified-EQL3D Procedure. 293-302.
-
Habtemariam, N., Fiorina, C., Reyes, S., & Schunert, S.
(2023).
Simulation of Gas Dynamics in the Chamber of Inertial Fusion Energy Systems Using State-of-the-Art Numerical Libraries. 276-279.
-
patent
-
Aufiero, M., Fiorina, C., & Di Lecce, F.
(2023).
Flexible floating reservoir for storing and transporting liquids heavier than the environmental liquid in which the reservoir is immersible
-
Aufiero, M., Fiorina, C., & Di Lecce, F.
(2023).
Flexible floating reservoir for storing and transporting liquids heavier than the environmental liquid in which the reservoir is immersible
-
report
-
Stefanowska-Srkordzka, M., Lavarenne, J., Deveaux, E., Brunetto, E., Jaramillo Sierra, D., Matocha, V., ... Strmensky, C.
(2023).
Fuel pin behaviour under irradiation with high Pu content: Benchmark exercise
-
Fiorina, C.
(2020).
Development and Application of Open-source Modeling and Simulation for Nuclear Reactors
-
Stefanowska-Srkordzka, M., Lavarenne, J., Deveaux, E., Brunetto, E., Jaramillo Sierra, D., Matocha, V., ... Strmensky, C.
(2023).
Fuel pin behaviour under irradiation with high Pu content: Benchmark exercise
Teaching
teaching activities
- NUEN301 Nuclear Reactor Theory Instructor
- NUEN491 Hnr-research Instructor
- NUEN685 Directed Studies Instructor
- NUEN691 Research Instructor
Background
awards and honors
Contact
first name
- Carlo
has last name
- Fiorina
Other
- carlo.fiorina@tamu.edu