| UWB1–Fast nuclear fuel depletion code M Lovecký, L Piterka, J Prehradný, R Škoda Annals of Nuclear Energy 71, 333-339, 2014 | 20 | 2014 |
| TEPLATOR: nuclear district heating solution R Skoda, A Fortova, D Masata, J Zavorka, M Lovecky, J Skarohlid, ... Proceedings of International Conference Nuclear Energy for New Europe, 221-228, 2020 | 19 | 2020 |
| Increasing efficiency of nuclear fuel using burnable absorbers M Lovecký, J Závorka, J Jiřičková, R Škoda Progress in Nuclear Energy 118, 103077, 2020 | 17 | 2020 |
| Performance of ENDF/B-VIII. 0 library for VVER reactors criticality safety, fuel depletion and reactor dosimetry applications M Lovecký, K Gincelová, P Haroková, J Jiřičková, V Smutný, J Závorka Annals of Nuclear Energy 148, 107736, 2020 | 10 | 2020 |
| Monte Carlo solver for UWB1 nuclear fuel depletion code M Lovecký, J Jiřičková, R Škoda Annals of nuclear energy 85, 778-787, 2015 | 10 | 2015 |
| UWB1 User’s Manual M Lovecký University of West Bohemia, 2015 | 10 | 2015 |
| Basic Design of the TEPLATOR Core—Construction J Závorka, M Lovecký, R Škoda Proc. 29th International Conference Nuclear Energy for New Europe (NENE 2020 …, 2020 | 9 | 2020 |
| Neutron absorber concept in spent fuel casks aiming at improved nuclear safety and better economics M Lovecký, J Závorka, R Škoda, J Jiřičková Proceedings of the 19th International Symposium on the Packaging and …, 2019 | 6 | 2019 |
| Assessment of burnable absorber fuel design by UWB1 depletion code M Lovecky, J Jirickova, R Skoda České vysoké učení technické v Praze, 2016 | 6 | 2016 |
| Moderator heat sources in Teplator district heating SMR M Lovecký, T Kořínek, J Závorka, J Jiřičková, R Škoda | 5 | 2022 |
| Criticality safety analysis of GBC-32 spent fuel cask with improved neutron absorber concept M Lovecký, J Závorka, J Jiřičková, R Škoda EPJ Web of Conferences 247, 17003, 2021 | 5 | 2021 |
| Potential of serpent-openFOAM coupled codes for spent nuclear fuel analysis T Korinek, J Zavorka, M Lovecky, R Skoda NENE, 8, 2021 | 5 | 2021 |
| The application of UWB1 nuclear fuel depletion code on a CANDU fuel bundle M Lovecký, R Škoda, MS Hussein, JJ Song, PK Chan Progress in Nuclear Energy 90, 127-139, 2016 | 5 | 2016 |
| Burnable Absorber Comparison Between VVER, PWR and SFR With UWB1 and SERPENT Codes J Prehradný, M Lovecký, R Škoda International Conference on Nuclear Engineering 45899, V001T02A022, 2014 | 5 | 2014 |
| Computational Fluid Dynamics Calculations of Moderator Heat and Fluid Flow of Small Modular Heavy Water Reactor T Korinek, R Skoda, M Lovecky, O Burian Journal of Nuclear Engineering and Radiation Science 10 (1), 2024 | 4 | 2024 |
| Fixed neutron absorbers for improved nuclear safety and better economics in nuclear fuel storage, transport and disposal M Lovecký, J Závorka, J Jiřičková, Z Ondráček, R Škoda Nuclear Engineering and Technology 55 (6), 2288-2297, 2023 | 4 | 2023 |
| Enhanced nuclear safety of spent fuel J Zavorka, M Lovecky, J Jirickova, R Skoda The Proceedings of the International Conference on Nuclear Engineering …, 2019 | 4 | 2019 |
| Burnable Absorber Selection With UWB1 Depletion Code M Lovecký, J Prehradný, R Škoda International Conference on Nuclear Engineering 45899, V001T02A020, 2014 | 4 | 2014 |
| Experimental verification of new neutron absorbers concepts J Závorka, M Lovecký, J Jiřičková, R Škoda Progress in Nuclear Energy 157, 104572, 2023 | 3 | 2023 |
| Influence of Relative Power Difference Weighting on Convergence of Coupled Neutronic Thermal-Hydraulic Calculations of Heavy Water Small Modular Reactor T Korinek, M Lovecky, R Skoda, J Zavorka Proceedings of 20th International Topical Meeting on Nuclear Reactor Thermal …, 2023 | 3 | 2023 |
