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The EQL0D fuel cycle procedure and its application to the transition to equilibrium of selected molten salt reactor designs
Hombourger, B., Křepel, J., & Pautz, A. (2020). The EQL0D fuel cycle procedure and its application to the transition to equilibrium of selected molten salt reactor designs. Annals of Nuclear Energy, 144, 107504 (18 pp.). https://doi.org/10.1016/j.anucene.2020.107504
Evaporation of materials from the molten salt reactor fuel under elevated temperatures
Kalilainen, J., Nichenko, S., & Krepel, J. (2020). Evaporation of materials from the molten salt reactor fuel under elevated temperatures. Journal of Nuclear Materials, 533, 152134 (13 pp.). https://doi.org/10.1016/j.jnucmat.2020.152134
Statistical burnup distribution of moving pebbles in the HTR-PM reactor
Vitullo, F., Krepel, J., Kalilainen, J., Prasser, H. M., & Pautz, A. (2020). Statistical burnup distribution of moving pebbles in the HTR-PM reactor. Journal of Nuclear Engineering and Radiation Science, 6(2), 021108 (14 pp.). https://doi.org/10.1115/1.4044910
Breed-and-burn fuel cycle in molten salt reactors
Hombourger, B., Křepel, J., & Pautz, A. (2019). Breed-and-burn fuel cycle in molten salt reactors. EPJ Nuclear Sciences and Technologies, 5, 15 (10 pp.). https://doi.org/10.1051/epjn/2019026
Closed U-Pu and Th-U cycle in sixteen selected reactors: comparison of major equilibrium features
Krepel, J., & Losa, E. (2019). Closed U-Pu and Th-U cycle in sixteen selected reactors: comparison of major equilibrium features. Annals of Nuclear Energy, 128, 341-357. https://doi.org/10.1016/j.anucene.2019.01.013
Simulations of advanced reactor cores in research light water reactor LR-0
Losa, E., Košťál, M., Jánský, B., Novák, E., Rypar, V., Chvála, O., & Křepel, J. (2019). Simulations of advanced reactor cores in research light water reactor LR-0. Nuclear Engineering and Design, 342, 205-209. https://doi.org/10.1016/j.nucengdes.2018.12.007
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
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.
Comparison of fast reactors performance in the closed U-Pu and Th-U cycle
Krepel, J. (2018). Comparison of fast reactors performance in the closed U-Pu and Th-U cycle. 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.
Core safety measures in ESFR-SMART
Rineiski, A., Meriot, C., Marchetti, M., & Krepel, J. (2018). Core safety measures in ESFR-SMART. In Proceedings of the PHYSOR 2018. Cancun, Mexico.
Statistical burnup distribution of moving pebbles in HTR-PM reactor
Vitullo, F., Krepel, J., Kalilainen, J., Prasser, H. M., & Pautz, A. (2018). Statistical burnup distribution of moving pebbles in HTR-PM reactor. In Proceedings of the 26th international conference on nuclear engineering (ICONE26). Student Paper Competition. https://doi.org/10.1115/ICONE26-81082
Worldwide activities
Edwards, L., LeBlanc, D., Rodenburg, C., Uhlíř, J., Dai, Z., Lauritzen, B., … Sajo-Bohus, L. (2017). Worldwide activities. In T. J. Dolan (Ed.), Molten salt reactors and thorium energy. https://doi.org/10.1016/B978-0-08-101126-3.00026-9
Recent research activities on high temperature pebble bed reactors at PSI
Kalilainen, J., Prasser, H. M., Lind, T., Krepel, J., & Schenler, W. (2016). Recent research activities on high temperature pebble bed reactors at PSI. In International topical meeting on high temperature reactor technology (HTR 2016). Illinois: American Nuclear Society.
The EQL0D procedure for fuel cycle studies in molten salt reactor
Krepel, J., Mikityuk, K., & Pautz, A. (2016). The EQL0D procedure for fuel cycle studies in molten salt reactor. In ICAPP 2016: Proceedings of the International Congress on Advances in Nuclear Power Plants 2016.
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 ICAPP 2015: proceedings of the international congress on advances in nuclear power plants 2015.
Extension of the FAST code system for the modelling and simulation of MSR dynamics
Krepel, J., & Mikityuk, K. (2015). Extension of the FAST code system for the modelling and simulation of MSR dynamics. In ICAPP 2015: proceedings of the international congress on advances in nuclear power plants 2015.
Fuel cycle analysis of a molten salt reactor for breed-and-burn mode
Krepel, J., Mikityuk, K., & Pautz, A. (2015). Fuel cycle analysis of a molten salt reactor for breed-and-burn mode. In ICAPP 2015: proceedings of the international congress on advances in nuclear power plants 2015.
Mapping of Sodium Void Worth and Doppler Effect for Sodium-cooled Fast Reactor
Krepel, J., Pelloni, S., & Mikityuk, K. (2015). Mapping of Sodium Void Worth and Doppler Effect for Sodium-cooled Fast Reactor. In ICAPP 2015: proceedings of the international congress on advances in nuclear power plants 2015.
Sodium Void Map Preparation for the Safety Analysis of Sodium-cooled Fast Reactors by Using the Monte Carlo Code Serpent
Pelloni, S., Krepel, J., Mikityuk, K., & Pautz, A. (2015). Sodium Void Map Preparation for the Safety Analysis of Sodium-cooled Fast Reactors by Using the Monte Carlo Code Serpent. In ICAPP 2015: proceedings of the international congress on advances in nuclear power plants 2015.