| Creation of an OpenFOAM fuel performance class based on FRED and integration into the GeN-Foam multi-physics code
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. In Proceedings of the 26th international conference on nuclear engineering (ICONE26). Nuclear fuel and material, reactor physics, and transport theory (pp. ICONE26-81574 (7 pp.). https://doi.org/10.1115/ICONE26-81574 |
| A simplified numerical benchmark for pool-type sodium fast reactors
Radman, S., Fiorina, C., Mikityuk, K., & Pautz, A. (2018). A simplified numerical benchmark for pool-type sodium fast reactors. In Proceedings of the 26th international conference on nuclear engineering (pp. ICONE26-82260 (9 pp.). https://doi.org/10.1115/ICONE26-82260 |
| First steps towards the development of a 3D nuclear fuel behaviour solver with OpenFOAM
Scolaro, A., Clifford, I., Fiorina, C., & Pautz, A. (2018). First steps towards the development of a 3D nuclear fuel behaviour solver with OpenFOAM. In Vol. 3. Proceedings of the 26th international conference on nuclear engineering (ICONE26). Nuclear fuel and material, reactor physics, and transport theory (pp. ICONE26-82381 (10 pp.). https://doi.org/10.1115/ICONE26-82381 |
| The proto-Earth geo-reactor: a thorium reactor?
Degueldre, C., & Fiorina, C. (2016). The proto-Earth geo-reactor: a thorium reactor? In J. P. Revol, M. Bourquin, Y. Kadi, E. Lillestol, J. C. de Mestral, & K. Samec (Eds.), Thorium energy for the world. Proceedings of the ThEC13 conference, CERN, globe of science and innovation, Geneva, Switzerland, October 27-31, 2013 (pp. 415-416). https://doi.org/10.1007/978-3-319-26542-1 |
| The proto-Earth geo-reactor: reassessing the hypotheses
Degueldre, C., & Fiorina, C. (2016). The proto-Earth geo-reactor: reassessing the hypotheses. Solid Earth Sciences, 1(2), 49-63. https://doi.org/10.1016/j.sesci.2016.08.002 |
| Paul Scherrer Institute's studies on advanced molten salt reactor fuel cycle options
Krepel, J., Hombourger, B., Bykov, V., Fiorina, C., Mikityuk, K., & Pautz, A. (2016). Paul Scherrer Institute's studies on advanced molten salt reactor fuel cycle options. In J. P. Revol, M. Bourquin, Y. Kadi, E. Lillestol, J. C. de Mestral, & K. Samec (Eds.), Thorium energy for the world. Proceedings of the ThEC13 conference, CERN, globe of science and innovation, Geneva, Switzerland, October 27-31, 2013 (pp. 185-192). https://doi.org/10.1007/978-3-319-26542-1_29 |
| The effectiveness of full actinide recycle as a nuclear waste management strategy when implemented over a limited timeframe – Part II: thorium fuel cycle
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. Progress in Nuclear Energy, 87, 144-155. https://doi.org/10.1016/j.pnucene.2014.11.016 |
| Serpent-OpenFOAM coupling in transient mode: simulation of a Godiva prompt critical burst
Aufiero, M., Fiorina, C., Laureau, A., Rubiolo, P., & Valtavirta, V. (2015). Serpent-OpenFOAM coupling in transient mode: simulation of a Godiva prompt critical burst. In Mathematics and computations, supercomputing in nuclear applications and Monte Carlo international conference (M&C+SNA+MC 2015). Mathematics and computations, supercomputing in nuclear applications and Monte Carlo international conference (M&C and SNA and MC 2015) (pp. 1995-2006). American Nuclear Society. |
| Application of the new GeN-Foam multi-physics solver to the European Sodium Fast Reactor and verification against available codes
Fiorina, C., & Mikityuk, K. (2015). Application of the new GeN-Foam multi-physics solver to the European Sodium Fast Reactor and verification against available codes. In Proceedings of 2015 international congress on advances in nuclear power plants (ICAPP 2015) (pp. 2017-2024). |
| GeN-Foam: A novel OpenFOAM<sup>®</sup> based multi-physics solver for 2D/3D transient analysis of nuclear reactors
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. https://doi.org/10.1016/j.nucengdes.2015.05.035 |
| Comparison of several recycling strategies and relevant fuel cycles for molten salt reactor
Krepel, J., Fiorina, C., & Mikityuk, K. (2015). Comparison of several recycling strategies and relevant fuel cycles for molten salt reactor. In Proceedings of 2015 international congress on advances in nuclear power plants (ICAPP 2015). Nice, France: SFEN. |
| The effectiveness of full actinide recycle as a nuclear waste management strategy when implemented over a limited timeframe - part I: uranium fuel cycle
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. Progress in Nuclear Energy, 85, 498-510. https://doi.org/10.1016/j.pnucene.2015.07.020 |
| A Geometric Multiscale modelling approach to the analysis of MSR plant dynamics
Zanetti, M., Cammi, A., Fiorina, C., & Luzzi, L. (2015). A Geometric Multiscale modelling approach to the analysis of MSR plant dynamics. Progress in Nuclear Energy, 83, 82-98. https://doi.org/10.1016/j.pnucene.2015.02.014 |
| A time-dependent solver for coupled neutron-transport thermal-mechanics calculations and simulation of a Godiva prompt-critical burst
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. In Proceedings of the 2014 22nd international conference on nuclear engineering (ICONE22) (p. V004T11A008 (9 pp.). https://doi.org/10.1115/ICONE22-30395 |
| Thermal-hydraulics of internally heated molten salts and application to the Molten Salt Fast Reactor
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. In Journal of physics: conference series: Vol. 501. 31st UIT (Italian union of thermo-fluid-dynamics) heat transfer conference 2013 (p. 012030 (10 pp.). https://doi.org/10.1088/1742-6596/501/1/012030 |
| Molten salt reactor with simplified fuel recycling and delayed carrier salt cleaning
Křepel, J., Bykov, V., Mikityuk, K., Hombourger, B., Fiorina, C., & Pautz, A. (2014). Molten salt reactor with simplified fuel recycling and delayed carrier salt cleaning. In Proceedings of the 2014 22nd international conference on nuclear engineering (ICONE22) (p. V003T05A015 (11 pp.). https://doi.org/10.1115/ICONE22-30396 |
| Thorium breeder and burner fuel cycles in reduced-moderation LWRs compared to fast reactors
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. Progress in Nuclear Energy, 77, 107-123. https://doi.org/10.1016/j.pnucene.2014.06.010 |
| An innovative approach to dynamics modeling and simulation of the Molten Salt Rector Experiment
Zanetti, M., Luzzi, L., Cammi, A., & Fiorina, C. (2014). An innovative approach to dynamics modeling and simulation of the Molten Salt Rector Experiment (p. 1104090 (14 pp.). Presented at the International conference on physics of reactors (PHYSOR 2014). . |
| MSFR TRU-burning potential and comparison with an SFR
Fiorina, C., Franceschini, F., Cammi, A., & Krepel, J. (2013). MSFR TRU-burning potential and comparison with an SFR. International nuclear fuel cycle conference, GLOBAL 2013: nuclear energy at a crossroads: Vol. 1. (pp. 813-822). Presented at the International nuclear fuel cycle conference: nuclear energy at a crossroads, GLOBAL 2013. American Nuclear Society. |
| The MSFR as a flexible CR reactor: the viewpoint of safety
Fiorina, C., Franceschini, F., Cammi, A., & Krepel, J. (2013). The MSFR as a flexible CR reactor: the viewpoint of safety. In Vol. 2. Proceedings of GLOBAL 2013: international nuclear fuel cycle conference - nuclear energy at a crossroads (pp. 833-842). American Nuclear Society. |
