| Fluoride volatility method for reprocessing of LWR and FR fuels J Uhlíř, M Mareček Journal of fluorine chemistry 130 (1), 89-93, 2009 | 54 | 2009 |
| Validation of zirconium isotopes (n, g) and (n, 2n) cross sections in a comprehensive LR-0 reactor operative parameters set M Košťál, M Schulc, V Rypar, E Losa, N Burianová, J Šimon, M Mareček, ... Applied Radiation and Isotopes 128, 92-100, 2017 | 38 | 2017 |
| A reference neutron field for measurement of spectrum averaged cross sections M Košťál, M Schulc, E Losa, J Šimon, N Burianová, E Novák, M Mareček, ... Annals of Nuclear Energy 140, 107119, 2020 | 27 | 2020 |
| Measurement of 75As (n, 2n) cross section in well-defined spectrum of LR-0 special core M Košťál, V Rypar, M Schulc, E Losa, P Baroň, M Mareček, J Uhlíř Annals of Nuclear Energy 100, 42-49, 2017 | 21 | 2017 |
| Corrosion testing of nickel alloy for molten salt reactors P Slama, M Marecek Journal of Achievements in Materials and Manufacturing Engineering 70 (2), 78-85, 2015 | 18 | 2015 |
| Validation of differential cross sections by means of 252Cf spectral averaged cross sections M Schulc, M Košťál, S Simakov, V Rypar, D Harutyunyan, J Šimon, ... Applied Radiation and Isotopes 132, 29-37, 2018 | 14 | 2018 |
| Measurement of 89Y (n, 2n) spectral averaged cross section in LR-0 special core reactor spectrum M Košťál, E Losa, P Baroň, J Šolc, M Švadlenková, M Koleška, M Mareček, ... Radiation Physics and Chemistry 141, 22-28, 2017 | 13 | 2017 |
| Validation of IRDFF-II library by means of 252Cf spectral averaged cross sections M Schulc, M Košťál, J Šimon, E Novák, M Mareček, R Kubín Applied Radiation and Isotopes 155, 108937, 2020 | 12 | 2020 |
| Measurement of 23Na (n, 2n) cross section in well-defined reactor spectra M Košťál, M Švadlenková, P Baroň, J Milčák, M Mareček, J Uhlíř Applied Radiation and Isotopes 111, 1-7, 2016 | 11 | 2016 |
| Current progress in R&D of fluoride volatility method J Uhlíř, M Mareček, J Škarohlíd Procedia Chemistry 7, 110-115, 2012 | 11 | 2012 |
| R and D of pyrochemical reprocessing technologies dedicated to MSR fuel cycle J Uhlir, M Marecek | 7 | 2005 |
| Technological verification of fluoride volatility method for front-end of molten salt transmutation reactor fuel cycle M Marecek Proc. GLOBAL 2001, Paris, France, Sept. 9-13, 2001 | 7 | 2001 |
| Validation of IRDFF-II library in VR-1 reactor field using thin targets M Kostal, E Losa, M Schulc, J Simon, T Bily, V Rypar, M Mareček, J Uhlíř, ... Annals of Nuclear Energy 158, 108268, 2021 | 6 | 2021 |
| Progress in development of Fluoride volatility reprocessing technology J Uhlir, M Marecek, M Precek | 6 | 2008 |
| Development of fluoride reprocessing technologies devoted to molten-salt reactor systems J Uhlir, M Marecek, R Tulackova, K Chuchvalcova Bimova Global 2007, 9-13, 2007 | 6 | 2007 |
| Uranium recovery from LiF–CaF2–UF4–GdF3 system on Ni electrode M Straka, L Szatmáry, M Mareček, M Korenko Journal of Radioanalytical and Nuclear Chemistry 298, 393-397, 2013 | 5 | 2013 |
| Technological development of fluoride volatility method for front-end of molten salt transmutation reactor fuel cycle M Marecek, F Lisy, J Uhlir Proc. of “InWor for P&T and ADS, 6-8, 2003 | 5 | 2003 |
| Energy well: concept of 20 MW microreactor cooled by molten salts M Ruščák, T Melichar, J Syblík, O Frýbort, D Harut, E Losa, M Mareček, ... Journal of Nuclear Engineering and Radiation Science 7 (2), 021302, 2021 | 4 | 2021 |
| Comprehensive validation of silicon cross sections T Czakoj, M Košťál, J Šimon, J Šoltés, M Mareček, R Capote Nuclear Engineering and Technology 52 (12), 2717-2724, 2020 | 4 | 2020 |
| Research of materials and components for molten salt reactors M Koukolikova, P Slama, Z Novy, P Svoboda, P Toman, M Marecek, ... Transactions of the American Nuclear Society 116, 2017 | 4 | 2017 |
Evžen LosaEmail verificata su fjfi.cvut.cz
