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Extension of the DYN3D/ATHLET code system to SFR applications: models description and initial validation
Fridman, E., Nikitin, E., Ponomarev, A., Di Nora, A., Kliem, S., & Mikityuk, K. (2023). Extension of the DYN3D/ATHLET code system to SFR applications: models description and initial validation. Annals of Nuclear Energy, 182, 109619 (10 pp.). https://doi.org/10.1016/j.anucene.2022.109619
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
Review of Euratom projects on design, safety assessment, R&D and licensing for ESNII/Gen-IV reactor systems
Mikityuk, K., Ferreira, M., Hatala, B., Kloosterman, J. L., & Šípová, M. (2023). Review of Euratom projects on design, safety assessment, R&D and licensing for ESNII/Gen-IV reactor systems. EPJ Nuclear Sciences and Technologies, 9, 18 (15 pp.). https://doi.org/10.1051/epjn/2022048
Simulation of flow and heat transfer in a differentially heated cubical cavity using coarse Large Eddy Simulation
Sayed, M. A., Hadžiabdić, M., Dehbi, A., Ničeno, B., & Mikityuk, K. (2023). Simulation of flow and heat transfer in a differentially heated cubical cavity using coarse Large Eddy Simulation. International Journal of Thermal Sciences, 183, 107892 (12 pp.). https://doi.org/10.1016/j.ijthermalsci.2022.107892
Professor Igor Leonardovich Pioro on his 65th birthday
Antoshko, Y., Bereznai, G., Bobyr, M. I., Bromley, B. P., Fialko, N., Huang, Y., … Zvorykin, C. (2022). Professor Igor Leonardovich Pioro on his 65th birthday. Journal of Nuclear Engineering and Radiation Science, 8(1), 010304 (2 pp.). https://doi.org/10.1115/1.4052785
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
Evaluation of the passive reactor shutdown system performance in European sodium fast reactor
Bubelis, E., Schikorr, M., & Mikityuk, K. (2022). Evaluation of the passive reactor shutdown system performance in European sodium fast reactor. Journal of Nuclear Engineering and Radiation Science, 8(1), 011309 (8 pp.). https://doi.org/10.1115/1.4050563
Neutronic analysis of the European Sodium Fast Reactor: part I - fresh core results
Fridman, E., Álvarez Velarde, F., Romojaro Otero, P., Tsige-Tamirat, H., Jiménez Carrascosa, A., García Herranz, N., … Mikityuk, K. (2022). Neutronic analysis of the European Sodium Fast Reactor: part I - fresh core results. Journal of Nuclear Engineering and Radiation Science, 8(1), 011301 (10 pp.). https://doi.org/10.1115/1.4048905
Neutronic analysis of the European sodium fast reactor: part II - burnup results
Fridman, E., Álvarez Velarde, F., Romojaro Otero, P., Tsige-Tamirat, H., Jiménez Carrascosa, A., García Herranz, N., … Mikityuk, K. (2022). Neutronic analysis of the European sodium fast reactor: part II - burnup results. Journal of Nuclear Engineering and Radiation Science, 8(1), 011302 (10 pp.). https://doi.org/10.1115/1.4048765
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
Burn-up dependent modeling of fuel-to-clad gap conductance and temperature predictions for mixed-oxide fuel in the ESFR-SMART core
Lavarenne, J., Bubelis, E., Davies, U., Gianfelici, S., Gicquel, S., Krepel, J., … Van Uffelen, P. (2022). Burn-up dependent modeling of fuel-to-clad gap conductance and temperature predictions for mixed-oxide fuel in the ESFR-SMART core. Journal of Nuclear Engineering and Radiation Science, 8(1), 011306 (11 pp.). https://doi.org/10.1115/1.4050479
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
Special issue: EU ESFR-SMART project word from the Horizon: 2020 EU ESFR-SMART project coordinator
Mikityuk, K. (2022). Special issue: EU ESFR-SMART project word from the Horizon: 2020 EU ESFR-SMART project coordinator. Journal of Nuclear Engineering and Radiation Science, 8(1), 010305 (2 pp.). https://doi.org/10.1115/1.4052641
Evaluation of sodium boiling models using KNS-37 loss of flow experiments
Perez-Martin, S., Anderhuber, M., Laborde, L., Girault, N., Lombardo, C., Ammirabile, L., … Pfrang, W. (2022). Evaluation of sodium boiling models using KNS-37 loss of flow experiments. Journal of Nuclear Engineering and Radiation Science, 8(1), 011310 (15 pp.). https://doi.org/10.1115/1.4050769
 

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