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Analysis of hypothetical Unprotected Loss Of Flow in Superphénix start-up core: sensitivity to modeling details
Ponomarev, A., & Mikityuk, K. (2019). Analysis of hypothetical Unprotected Loss Of Flow in Superphénix start-up core: sensitivity to modeling details. The proceedings of the international conference on nuclear engineering (ICONE): Vol. 2019.27. . Presented at the 27th international conference on nuclear engineering (ICONE-27). sine loco: The Japan Society of Mechanical Engineers.
A coarse-mesh methodology for modelling of single-phase thermal-hydraulics of ESFR innovative assembly design
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 (17 pp.). https://doi.org/10.1016/j.nucengdes.2019.110291
Conclusions of a benchmark study on the EBR-II SHRT-45R experiment
Bates, E., Zhang, D., Truong, B., Sui, D., Hu, W., Su, G. H., … Mikityuk, K. (2018). Conclusions of a benchmark study on the EBR-II SHRT-45R experiment. In Proceedings series (International Atomic Energy Agency): Vol. CN245. Fast reactors and related fuel cycles: next generation nuclear systems for sustainable development (FR17). Proceedings of an international conference organized by the International Atomic Energy Agency, hosted by the government of the Russian Federation through the state atomic energy corporation "Rosatom" and held in Yekaterinburg, Russian Federation, 26–29 June 2017. Vienna: International Atomic Energy Agency.
IAEA's coordinated research project on EBR-II shutdown heat removal tests: an overview
Batra, C., Kriventsev, V., Monti, S., Briggs, L., Hu, W., Sui, D., … Bates, E. (2018). IAEA's coordinated research project on EBR-II shutdown heat removal tests: an overview. In Proceedings series (International Atomic Energy Agency): Vol. CN245. Fast reactors and related fuel cycles: next generation nuclear systems for sustainable development (FR17). Proceedings of an international conference organized by the International Atomic Energy Agency, hosted by the government of the Russian Federation through the state atomic energy corporation "Rosatom" and held in Yekaterinburg, Russian Federation, 26–29 June 2017. Vienna: International Atomic Energy Agency.
Benchmark analyses of EBR-II shutdown heat removal tests
Briggs, L., Kriventsev, V., Monti, S., Hu, W., Sui, D., Su, G., … Truong, B. (2018). Benchmark analyses of EBR-II shutdown heat removal tests. In Proceedings series (International Atomic Energy Agency): Vol. CN245. Fast reactors and related fuel cycles: next generation nuclear systems for sustainable development (FR17). Proceedings of an international conference organized by the International Atomic Energy Agency, hosted by the government of the Russian Federation through the state atomic energy corporation "Rosatom" and held in Yekaterinburg, Russian Federation, 26–29 June 2017. Vienna: International Atomic Energy Agency.
Analysis of major group structures used for nuclear reactor simulations
Di Filippo, M., Krepel, J., Mikityuk, K., & Prasser, H. M. (2018). Analysis of major group structures used for nuclear reactor simulations. In Proceedings of the 26th international conference on nuclear engineering (ICONE26). Student paper competition. https://doi.org/10.1115/ICONE26-81445
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. https://doi.org/10.1115/ICONE26-81574
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 Proceedings of the 2018 International Congress on Advances in Nuclear Power Plants, ICAPP 2018. American Nuclear Society.
On the feasibility of Breed-and-Burn fuel cycles in Molten Salt Reactors
Hombourger, B., Krepel, J., Mikityuk, K., & Pautz, A. (2018). On the feasibility of Breed-and-Burn fuel cycles in Molten Salt Reactors. In Proceedings series (International Atomic Energy Agency): Vol. CN245. Fast reactors and related fuel cycles: next generation nuclear systems for sustainable development (FR17). Proceedings of an international conference organized by the International Atomic Energy Agency, hosted by the government of the Russian Federation through the state atomic energy corporation "Rosatom" and held in Yekaterinburg, Russian Federation, 26–29 June 2017. Vienna: International Atomic Energy Agency.
Chugging boiling in low-void SFR core: new phenomenology of unprotected loss of flow
Mambelli, S., Mikityuk, K., & Panadero, A. L. (2018). Chugging boiling in low-void SFR core: new phenomenology of unprotected loss of flow. In Proceedings series (International Atomic Energy Agency): Vol. CN245. Fast reactors and related fuel cycles: next generation nuclear systems for sustainable development (FR17). Proceedings of an international conference organized by the International Atomic Energy Agency, hosted by the government of the Russian Federation through the state atomic energy corporation "Rosatom" and held in Yekaterinburg, Russian Federation, 26–29 June 2017. Vienna: International Atomic Energy Agency.
ESFR-SMART: new Horizon-2020 project on SFR safety
Mikityuk, K., Girardi, E., Krepel, J., Bubelis, E., Fridman, E., Rineiski, A., … Garnier, J. C. (2018). ESFR-SMART: new Horizon-2020 project on SFR safety. In Proceedings series (International Atomic Energy Agency): Vol. CN245. Fast reactors and related fuel cycles: next generation nuclear systems for sustainable development (FR17). Proceedings of an international conference organized by the International Atomic Energy Agency, hosted by the government of the Russian Federation through the state atomic energy corporation "Rosatom" and held in Yekaterinburg, Russian Federation, 26–29 June 2017. Vienna: International Atomic Energy Agency.
New safety measures proposed for European Sodium Fast Reactor in Horizon-2020 ESFR-SMART project
Mikityuk, K. (2018). New safety measures proposed for European Sodium Fast Reactor in Horizon-2020 ESFR-SMART project. Presented at the GIF Symposium. Paris, France.
Use of CAD models in ESFR-SMART project
Mikityuk, K., & Ponomarev, A. (2018). Use of CAD models in ESFR-SMART project. Presented at the GIF Symposium. Paris, France.
GEN IV education and training initiative via public webinars
Paviet, P., Alekseev, P., Fazio, C., Fratoni, M., Hwang, I., Kelly, J., … Sun, J. (2018). GEN IV education and training initiative via public webinars. In Vol. CN245. Fast reactors and related fuel cycles: next generation nuclear systems for sustainable development (FR17). Proceedings of an international conference organized by the International Atomic Energy Agency, hosted by the government of the Russian Federation through the state atomic energy corporation "Rosatom" and held in Yekaterinburg, Russian Federation, 26–29 June 2017. Vienna: International Atomic Energy Agency.
Low-void-effect sodium-cooled core: uncertainty of local sodium void reactivity as a result of nuclear data uncertainties
Pelloni, S., Panadero, A. L., Mikityuk, K., & Pautz, A. (2018). Low-void-effect sodium-cooled core: uncertainty of local sodium void reactivity as a result of nuclear data uncertainties. In Proceedings series (International Atomic Energy Agency): Vol. CN245. Fast reactors and related fuel cycles: next generation nuclear systems for sustainable development (FR17). Proceedings of an international conference organized by the International Atomic Energy Agency, hosted by the government of the Russian Federation through the state atomic energy corporation "Rosatom" and held in Yekaterinburg, Russian Federation, 26–29 June 2017. Vienna: International Atomic Energy Agency.
New sodium fast reactor neutronics benchmark
Ponomarev, A., Bednarova, A., & Mikityuk, K. (2018). New sodium fast reactor neutronics benchmark. In Proceedings of the PHYSOR 2018. LaGrange Park, IL, USA: American Nuclear Society.
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. New York: American Society of Mechanical Engineers (ASME).
Objectives and status of the OECD/NEA sub-group on Uncertainty Analysis in Modelling (UAM) for Design, Operation and Safety Analysis of SFRs (SFR-UAM)
Rimpault, G., Buiron, L., Stauff, N. E., Kim, T. K., Taiwo, T. A., Lee, Y. K., … Ivanova, T. (2018). Objectives and status of the OECD/NEA sub-group on Uncertainty Analysis in Modelling (UAM) for Design, Operation and Safety Analysis of SFRs (SFR-UAM). In Proceedings series (International Atomic Energy Agency): Vol. CN245. Fast reactors and related fuel cycles: next generation nuclear systems for sustainable development (FR17). Proceedings of an international conference organized by the International Atomic Energy Agency, hosted by the government of the Russian Federation through the state atomic energy corporation "Rosatom" and held in Yekaterinburg, Russian Federation, 26–29 June 2017. Vienna: International Atomic Energy Agency.
Analytical solutions to a coupled fluid dynamics and neutron transport problem with application to GeN-Foam verification
de Oliveira, R. G. G., & Mikityuk, K. (2018). Analytical solutions to a coupled fluid dynamics and neutron transport problem with application to GeN-Foam verification. Annals of Nuclear Energy, 121, 446-451. https://doi.org/10.1016/j.anucene.2018.07.036
System codes benchmarking on a low sodium void effect SFR heterogeneous core under ULOF conditions
Bubelis, E., Tosello, A., Pfrang, W., Schikorr, M., Mikityuk, K., Panadero, A. L., … Wallenius, J. (2017). System codes benchmarking on a low sodium void effect SFR heterogeneous core under ULOF conditions. Nuclear Engineering and Design, 320, 325-345. https://doi.org/10.1016/j.nucengdes.2017.06.015
 

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