selected publications academicarticle 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. Zanetti, M., Cammi, A., Fiorina, C., & Luzzi, L. A Geometric Multiscale modelling approach to the analysis of MSR plant dynamics. PROGRESS IN NUCLEAR ENERGY. 83, 82-98. Radman, S., Fiorina, C., Mikityuk, K., & Pautz, A. A coarse-mesh methodology for modelling of single-phase thermal-hydraulics of ESFR innovative assembly design. Nuclear Engineering and Design. 355, 110291-110291. Aufiero, M., Cammi, A., Fiorina, C., Luzzi, L., & Sartori, A. A multi-physics time-dependent model for the Lead Fast Reactor single-channel analysis. Nuclear Engineering and Design. 256, 14-27. Fiorina, C., Radman, S., Scolaro, A., & Pautz, A. A reduced order accelerator for time-dependent segregated neutronic solvers. Annals of Nuclear Energy. 121, 177-185. Lamirand, V., Rais, A., Pakari, O., Hursin, M., Laureau, A., Pohlus, J., ... Pautz, A. 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. Luzzi, L., Cammi, A., Di Marcello, V., & Fiorina, C. An approach for the modelling and the analysis of the MSR thermo-hydrodynamic behaviour. Chemical Engineering Science (CES). 65(16), 4873-4883. Aufiero, M., Cammi, A., Fiorina, C., Leppanen, J., Luzzi, L., & Ricotti, M. E. An extended version of the SERPENT-2 code to investigate fuel burn-up and core material evolution of the Molten Salt Fast Reactor. Journal of Nuclear Materials. 441(1-3), 473-486. Fiorina, C., Krepel, J., Cammi, A., Franceschini, F., Mikityuk, K., & Ricotti, M. E. 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. German, P., Ragusa, J. C., & Fiorina, C. Application of multiphysics model order reduction to doppler/neutronic feedback. EPJ Nuclear Sciences & Technologies. 5(17), 17-17. Fiorina, C., Scolaro, A., Siefman, D., Hursin, M., & Pautz, A. Artificial Neural Networks as Surrogate Models for Uncertainty Quantification and Data Assimilation in 2-D/3-D Fuel Performance Studies. 1(1), 54-62. Fiorina, C., Stauff, N. E., Franceschini, F., Wenner, M. T., Stanculescu, A., Kim, T. K., ... Salvatores, M. Comparative analysis of thorium and uranium fuel for transuranic recycle in a sodium cooled Fast Reactor. Annals of Nuclear Energy. 62, 26-39. German, P., Tano, M., Ragusa, J. C., & Fiorina, C. Comparison of Reduced-Basis techniques for the model order reduction of parametric incompressible fluid flows. 130, 103551-103551. De Pietri, M., Fiorina, C., Le Tonqueze, Y., & Juarez, R. Computational study of the Nitrogen-16 source term in the ITER vacuum vessel cooling circuit through the coupling of system-level analysis code and CFD. Nuclear Engineering and Technology. 56(8), 2990-2998. Mylonakis, A. G., Demazire, C., Vinai, P., Lamirand, V., Rais, A., Pakari, O., ... Pautz, A. Core SIM+ Simulations of Colibri Fuel Rods Oscillation Experiments and Comparison with Measurements. EPJ Web of Conferences. 247, 21006-21006. German, P., Tano, M. E., Fiorina, C., & Ragusa, J. C. Data-Driven Reduced-Order Modeling of Convective Heat Transfer in Porous Media. Fluids. 6(8), 266-266. Fiorina, C., Kerkar, N., Mikityuk, K., Rubiolo, P., & Pautz, A. Development and verification of the neutron diffusion solver for the GeN-Foam multi-physics platform. Annals of Nuclear Energy. 96, 212-222. Radman, S., Fiorina, C., & Pautz, A. 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. 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. Radman, S., Fiorina, C., Song, P., & Pautz, A. 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. Scolaro, A., Fiorina, C., Clifford, I., & Pautz, A. Development of a semiimplicit contact methodology for finite volume stress solvers. International Journal for Numerical Methods in Engineering. 123(2), 309-338. Cammi, A., Fiorina, C., Guerrieri, C., & Luzzi, L. 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. Niu, Y., Alessandro, S., Fiorina, C., Qin, H., Lazare, G., Wu, Y., Tian, W., & Su, G. H. 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. Extension of GeN-Foam to modeling of boiling water and validation against the OECD/NRC PSBT benchmark. Nuclear Engineering and Design. 408, 112320-112320. Fiorina, C., Hursin, M., & Pautz, A. Extension of the GeN-Foam neutronic solver to SP3 analysis and application to the CROCUS experimental reactor. Annals of Nuclear Energy. 101, 419-428. Brunetto, E. L., Scolaro, A., Fiorina, C., & Pautz, A. Extension of the OFFBEAT fuel performance code to finite strains and validation against LOCA experiments. Nuclear Engineering and Design. 406, 112232-112232. Krepel, J., Hombourger, B., Fiorina, C., Mikityuk, K., Rohde, U., Kliem, S., & Pautz, A. Fuel cycle advantages and dynamics features of liquid fueled MSR. Annals of Nuclear Energy. 64, 380-397. Guilbaud, T., Simonnot, E., Scolaro, A., & Fiorina, C. Full core study of the KIWI-B-4E Nuclear Thermal Propulsion system using OpenMC and GeN-Foam. Nuclear Engineering and Design. 429, 113639-113639. Fiorina, C., Clifford, I., Aufiero, M., & Mikityuk, K. GeN-Foam: a novel OpenFOAM based multi-physics solver for 2D/3D transient analysis of nuclear reactors. Nuclear Engineering and Design. 294, 24-37. German, P., Tano, M., Fiorina, C., & Ragusa, J. C. GeN-ROM-An OpenFOAM(R)-based multiphysics reduced-order modeling framework for the analysis of Molten Salt Reactors. PROGRESS IN NUCLEAR ENERGY. 146, 104148-104148. Lindley, B., Velarde, F. A., Baker, U., Bodi, J., Cosgrove, P., Charles, A., ... Tollit, B. 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), Fiorina, C. Impact of the volume heat source on the RANS-based CFD analysis of Molten Salt Reactors. Annals of Nuclear Energy. 134, 376-382. Seo, S., Folsom, C., Jensen, C., Kamerman, D., Giaccardi, L., Cherubini, M., ... Fiorina, C. International fuel performance study of fresh fuel experiments for PCMI effects during RIA experiments. Nuclear Engineering and Design. 430, 113673-113673. Guilbaud, T., Fiorina, C., Lorenzi, S., Scolaro, A., Carminati, F., Maire, D., & Pautz, A. 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. Mager, T., Fiorina, C., Hursin, M., & Pautz, A. Investigation and Validation of Unstructured Mesh Methodologies for Modeling Experimental Reactors. Energies. 15(4), 1512-1512. Fiorina, C., Aufiero, M., Cammi, A., Franceschini, F., Krepel, J., Luzzi, L., Mikityuk, K., & Ricotti, M. E. Investigation of the MSFR core physics and fuel cycle characteristics. PROGRESS IN NUCLEAR ENERGY. 68, 153-168. Scolaro, A., Van Uffelen, P., Fiorina, C., Schubert, A., Clifford, I., & Pautz, A. Investigation on the effect of eccentricity for fuel disc irradiation tests. Nuclear Engineering and Technology. 53(5), 1602-1611. Fiorina, C., Lathouwers, D., Aufiero, M., Cammi, A., Guerrieri, C., Kloosterman, J. L., Luzzi, L., & Ricotti, M. E. Modelling and analysis of the MSFR transient behaviour. Annals of Nuclear Energy. 64, 485-498. Nikitin, E., Fridman, E., Mikityuk, K., Radman, S., & Fiorina, C. NEUTRONIC MODELLING OF THE FFTF CONTROL ROD WORTH MEASUREMENTS WITH DIFFUSION CODES. EPJ Web of Conferences. 247, 10017-10017. Lamirand, V., Rais, A., Hbner, S., Lange, C., Pohlus, J., Paquee, U., ... Pautz, A. Neutron noise experiments in the AKR-2 and CROCUS reactors for the European project CORTEX. EPJ Web of Conferences. 225, 04023-04023. Brovchenko, M., Kloosterman, J., Luzzi, L., Merle, E., Heuer, D., Laureau, A., ... Merk, B. 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., Clifford, I., Kelm, S., & Lorenzi, S. 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. Habtemariam, N., Fiorina, C., Lorenzi, S., & Cammi, A. On the need for multi-dimensional models for the safety analysis of (fast-spectrum) Molten Salt Reactors. Annals of Nuclear Energy. 197, 110237-110237. Altahhan, M. R., Bhaskar, S., Ziyad, D., Balestra, P., Fiorina, C., Hou, J., Smith, N., & Avramova, M. Preliminary design and analysis of Liquid Fuel Molten Salt Reactor using multi-physics code GeN-Foam. Nuclear Engineering and Design. 369, 110826-110826. Guilbaud, T., Fiorina, C., Pautz, A., & Carminati, F. Preliminary safety analysis of the TRANSMUTEX sub-critical reactor using the GeN-Foam multi-physics solver. PROGRESS IN NUCLEAR ENERGY. 168, 104980-104980. Lamirand, V., Frajtag, P., Godat, D., Pakari, O., Laureau, A., Rais, A., ... Pautz, A. The COLIBRI experimental program in the CROCUS reactor: characterization of the fuel rods oscillator. EPJ Web of Conferences. 225, 04020-04020. Scolaro, A., Clifford, I., Fiorina, C., & Pautz, A. The OFFBEAT multi-dimensional fuel behavior solver. Nuclear Engineering and Design. 358, 110416-110416. Lindley, B. A., Fiorina, C., Gregg, R., Franceschini, F., & Parks, G. T. The effectiveness of full actinide recycle as a nuclear waste management strategy when implemented over a limited timeframe Part I: Uranium fuel cycle. PROGRESS IN NUCLEAR ENERGY. 85, 498-510. Lindley, B. A., Fiorina, C., Gregg, R., Franceschini, F., & Parks, G. T. The effectiveness of full actinide recycle as a nuclear waste management strategy when implemented over a limited timeframe Part II: Thorium fuel cycle. PROGRESS IN NUCLEAR ENERGY. 87, 144-155. Degueldre, C., & Fiorina, C. The proto-Earth geo-reactor: Reassessing the hypotheses. Solid Earth Sciences. 1(2), 49-63. Fiorina, C., Cammi, A., Luzzi, L., Mikityuk, K., Ninokata, H., & Ricotti, M. E. Thermal-hydraulics of internally heated molten salts and application to the Molten Salt Fast Reactor. Journal of Physics : Conference Series. 501(1), 012030-012030. Lindley, B. A., Fiorina, C., Franceschini, F., Lahoda, E. J., & Parks, G. T. Thorium breeder and burner fuel cycles in reduced-moderation LWRs compared to fast reactors. PROGRESS IN NUCLEAR ENERGY. 77, 107-123. Scolaro, A., Van Uffelen, P., Schubert, A., Fiorina, C., Brunetto, E., Clifford, I., & Pautz, A. Towards coupling conventional with high-fidelity fuel behavior analysis tools. PROGRESS IN NUCLEAR ENERGY. 152, 104357-104357. book Guilbaud, T., Fiorina, C., Scolaro, A., & Pautz, A. FMI-based multi-fidelity and multi-scale simulations of a nuclear reactor chapter Fiorina, C. Advanced Modeling and Simulation Methods. Encyclopedia of Nuclear Energy. (pp. 837-850). Elsevier. Fiorina, C. 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. 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. 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. 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. Thermo-Hydrodynamics of Internally Heated Molten Salts for Innovative Nuclear Reactors. Hydrodynamics - Theory and Model. IntechOpen. 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. (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. 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. 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. 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., & 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. Guerrieri, C., Aufiero, M., Cammi, A., Fiorina, C., & Luzzi, L. A Preliminary Study of the MSFR Dynamics. 229-238. Fiorina, C., Mikityuk, K., & Krepel, J. A Procedure for the Pre-Conceptual Design of Fast Reactors and Application to a Gas-Cooled Sub-Critical Transmuter. v005t16a001-v005t16a001. Radman, S., Fiorina, C., Mikityuk, K., & Pautz, A. A Simplified Numerical Benchmark for Pool-Type Sodium Fast Reactors. v004t15a018-v004t15a018. Fiorina, C., Aufiero, M., Pelloni, S., & Mikityuk, K. A Time-Dependent Solver for Coupled Neutron-Transport Thermal-Mechanics Calculations and Simulation of a Godiva Prompt-Critical Burst. v004t11a008-v004t11a008. Fiorina, C., Sherwise, P., Dufresne, A., Ragusa, J., Ivanov, K., Valentine, T., ... Clifford, I. 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. Fiorina, C., Aufiero, M., Cammi, A., Guerrieri, C., Krepel, J., Luzzi, L., Mikityuk, K., & Ricotti, M. E. Analysis of the MSFR Core Neutronics Adopting Different Neutron Transport Models. 219-228. Fiorina, C., Scolaro, A., Siefman, D., Hursin, M., & Pautz, A. Bayesian Data Assimilation for Fuel Performance Based on OFFBEAT. 3656-3665. Di-Lecce, F., Dulla, S., Ravetto, P., Cammi, A., Lorenzi, S., & Fiorina, C. CFD-Based Correlation for Forced Convection Heat Transfer in Circular Ducts of Internally Heated Molten Salts. v06bt08a062-v06bt08a062. Simon, P. A., Tano Retamales, M. E., Habtemariam, N., Fiorina, C., & Reyes, S. Challenging Common Assumptions of Thick-Wall Chamber Dynamics in Inertial Fusion Systems using MOOSE Fiorina, C., Pautz, A., & Mikityuk, K. Creation of an OpenFOAM Fuel Performance Class Based on FRED and Integration Into the GeN-Foam Multi-Physics Code. v003t02a027-v003t02a027. Simon, P. A., Icenhour, C. T., Shimada, M., Lindsay, A. D., Giudicelli, G. L., Harbour, L. H., ... Fiorina, C. Developing Multiphysics, Integrated, High-Fidelity, Massively Parallel Computational Capabilities for Fusion Applications Using MOOSE Brunetto, E., Scolaro, A., Fiorina, C., & Pautz, A. 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. Development of a High Fidelity Model of the CROCUS Experimental Reactor. 946-956. Guilbaud, T., Fiorina, C., Scolaro, A., & Pautz, A. FMI-based multi-fidelity transient analysis of a lead-cooled fast reactor using GeN-Foam and OpenModelica. Transactions of the American Nuclear Society. 436-439. Scolaro, A., Clifford, I., Fiorina, C., & Pautz, A. First Steps Towards the Development of a 3D Nuclear Fuel Behavior Solver With OpenFOAM. v003t02a051-v003t02a051. Pakari, O., Scolaro, A., & Fiorina, C. Generative AI Tools in the Nuclear Engineering Community: A Survey-Based Evaluation of the Current Adoption and Impacts. 1457-1465. Morelova, N., Kriventsev, V., Fiorina, C., Clifford, I., Kelm, S., Lorenzi, S., ... Forget, B. 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. 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. Impact of Thermal Coupling on a Pebblebed Reactor Equilibrium from Hyper-Fidelity Depletion. The Proceedings of the International Conference on Nuclear Engineering (ICONE). 1490-1490. Brunetto, E., Scolaro, A., Fiorina, C., & Pautz, A. Implementation of a Multidimensional Diffusion-Based Neutronics Solver in OFFBEAT. 462-466. Hughes, Z., Fiorina, C., MacDonald, N., Garza, C., Guilbaud, T., & Scolaro, A. Investigating the Accuracy of Porous-Medium Treatments in the Analysis of Nuclear Thermal Propulsion Systems. Transactions of the American Nuclear Society. 1186-1195. Nervi, G., Scolaro, A., Hursin, M., & Fiorina, C. Modeling of Sodium Fast Reactors Thermal Expansion Reactivity Feedback Using GeN-Foam and Serpent. 493-502. Krepel, J., Bykov, V., Mikityuk, K., Hombourger, B., Fiorina, C., & Pautz, A. Molten Salt Reactor With Simplified Fuel Recycling and Delayed Carrier Salt Cleaning. v003t05a015-v003t05a015. Scolaro, A., Fiorina, C., Clifford, I., Brunetto, E., & Pautz, A. Pre-Release Validation Database for the Multi-Dimensional Fuel Performance Code OFFBEAT. 2914-2923. Fiorina, C., Cammi, A., Krepel, J., Mikityuk, K., & Ricotti, M. E. Preliminary Analysis of the MSFR Fuel Cycle Using Modified-EQL3D Procedure. 293-302. German, P., Tano, M., Ragusa, J., & Fiorina, C. Reduced-Order Modeling of Fluid Flows in Closed-Loop Systems. 1762-1764. German, P., Tano, M., Ragusa, J., & Fiorina, C. Reduced-Order Modeling of Parameterized Transient Flows in Closed-Lloop Systems. EPJ Web of Conferences. 06055-06055. Fiorina, C. The GeN-Foam Multiphysics Solver: A Status Update. 3138-3147. patent Aufiero, M., Fiorina, C., & Di Lecce, F. 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
teaching activities NUEN301 Nuclear Reactor Theory Instructor NUEN491 Hnr-research Instructor NUEN684 Professional Internship:in-ab Instructor NUEN685 Directed Studies Instructor NUEN689 Sptp: Fund Of Fusion Engineer Instructor NUEN691 Research Instructor
awards and honors Early Career Reactor Physicist Award, conferred by American Nuclear Society - (La Grange Park, Illinois, United States), 2023