| ESFR SMART: a European Sodium Fast Reactor concept including the European feedback experience and the new safety commitments following Fukushima accident
Guidez, J., Bodi, J., Mikityuk, K., & Girardi, E. (2023). ESFR SMART: a European Sodium Fast Reactor concept including the European feedback experience and the new safety commitments following Fukushima accident. In I. L. Pioro (Ed.), A handbook of generation IV nuclear rectors. A guidebook (pp. 355-393). https://doi.org/10.1016/B978-0-12-820588-4.00022-0 |
| Impact of thermal-hydraulic feedback and differential thermal expansion on european sodium-cooled fast reactor core power distribution
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), 031301 (13 pp.). https://doi.org/10.1115/1.4056930 |
| Analysis of ESFR decay heat removal systems in protected station blackout
Bodi, J., Ponomarev, A., Bubelis, E., & Mikityuk, K. (2022). Analysis of ESFR decay heat removal systems in protected station blackout. Journal of Nuclear Engineering and Radiation Science, 8(1), 011315 (18 pp.). https://doi.org/10.1115/1.4052190 |
| Analysis of sodium boiling initiated by unprotected loss of flow in European sodium fast reactor core with different subassembly designs
Bodi, J., Ponomarev, A., & Mikityuk, K. (2022). Analysis of sodium boiling initiated by unprotected loss of flow in European sodium fast reactor core with different subassembly designs. Nuclear Engineering and Design, 399, 112014 (12 pp.). https://doi.org/10.1016/j.nucengdes.2022.112014 |
| Coupled neutronics-mechanics analysis method for evaluation of reactivity change due to core distortion in sodium fast reactor
Bodi, J., Ponomarev, A., & Mikityuk, K. (2022). Coupled neutronics-mechanics analysis method for evaluation of reactivity change due to core distortion in sodium fast reactor. Journal of Nuclear Engineering and Radiation Science, 8(1), 011307 (7 pp.). https://doi.org/10.1115/1.4050417 |
| Computational fluid dynamic analysis of the ESFR reactor pit cooling system in case of sodium leakage
Grah, A., Tsige-Tamirat, H., Guidez, J., Gerschenfeld, A., Mikityuk, K., Bodi, J., & Girardi, E. (2022). Computational fluid dynamic analysis of the ESFR reactor pit cooling system in case of sodium leakage. Journal of Nuclear Engineering and Radiation Science, 8(1), 011314 (9 pp.). https://doi.org/10.1115/1.4051292 |
| New reactor safety measures for the European sodium fast reactor - part I: conceptual design
Guidez, J., Bodi, J., Mikityuk, K., Girardi, E., & Carluec, B. (2022). New reactor safety measures for the European sodium fast reactor - part I: conceptual design. Journal of Nuclear Engineering and Radiation Science, 8(1), 011311 (17 pp.). https://doi.org/10.1115/1.4051364 |
| New reactor safety measures for the european sodium fast reactor—part II: preliminary assessment
Guidez, J., Bodi, J., Mikityuk, K., Girardi, E., Bittan, J., Grah, A., … Carluec, B. (2022). New reactor safety measures for the european sodium fast reactor—part II: preliminary assessment. Journal of Nuclear Engineering and Radiation Science, 8(1), 011312 (14 pp.). https://doi.org/10.1115/1.4051723 |
| Optimization of the European sodium fast reactor secondary sodium loop as part of the ESFR-SMART project
Guidez, J., Bodi, J., Mikityuk, K., & Girardi, E. (2022). Optimization of the European sodium fast reactor secondary sodium loop as part of the ESFR-SMART project. Journal of Nuclear Engineering and Radiation Science, 8(1), 011323 (10 pp.). https://doi.org/10.1115/1.4052589 |
| Coupled neutronic-therma-hydraulic simulations of the European SFR core
Lindley, B., Álvarez Velarde, F., Bodi, J., Charles, A., Fridman, E., Krepel, J., … Tollit, B. (2022). Coupled neutronic-therma-hydraulic simulations of the European SFR core. In Proceedings international conference on physics of reactors (pp. 625-634). https://doi.org/10.13182/PHYSOR22-37339 |
| Preliminary CFD analysis of innovative decay heat removal system for the European Sodium Fast Reactor concept
Grah, A., Tsige-Tamirat, H., Guidez, J., Gerschenfeld, A., Mikityuk, K., Bodi, J., & Girardi, E. (2021). Preliminary CFD analysis of innovative decay heat removal system for the European Sodium Fast Reactor concept. atw: International Journal of Nuclear Power, 66(6), 41-48. |
| ESFR smart project conceptual design of in-vessel core catcher
Guidez, J., Gerschenfeld, A., Bodi, J., Mikityuk, K., Alvarez-Velarde, F., Romojaro, P., & Diaz-Chiron, U. (2021). ESFR smart project conceptual design of in-vessel core catcher. In M. Margulis & P. Blaise (Eds.), EPJ web of conferences: Vol. 247. PHYSOR2020 - international conference on physics of reactors: transition to a scalable nuclear future (p. 01002 (7 pp.). https://doi.org/10.1051/epjconf/202124701002 |
| Use of CAD models in ESFR-SMART EU project
Bodi, J., Mikityuk, K., Ponomarev, A., & Guidez, J. (2018). Use of CAD models in ESFR-SMART EU project. In 2018 GIF symposium proceedings (pp. 363-368). https://doi.org/10.5281/zenodo.1479030 |
| New safety measures proposed for European sodium fast reactor in Horizon-2020 ESFR-SMART project
Guidez, J., Bodi, J., Mikityuk, K., Rineiski, A., & Girardi, E. (2018). New safety measures proposed for European sodium fast reactor in Horizon-2020 ESFR-SMART project. In 2018 GIF symposium proceedings (pp. 239-248). Generation IV International Forum. |
| Proposal of new safety measures for European Sodium Fast Reactor to be evaluated in framework of Horizon-2020 ESFR-SMART project
Guidez, J., Rineiski, A., Prêle, G., Girardi, E., Bodi, J., & Mikityuk, K. (2018). Proposal of new safety measures for European Sodium Fast Reactor to be evaluated in framework of Horizon-2020 ESFR-SMART project. In 2018 international congress on advances in nuclear power plants (ICAPP 2018) (pp. 26-35). https://doi.org/10.5281/zenodo.1309316 |
