Issue Date | Title | Author(s) |
2019 | Application of serpent code calculations: tritium production using fast neutrons | Vilímová, Eva; Mašata, David; Lovecký, Martin; Škoda, Radek |
2019 | Application of UWB1 code on tritium production calculations | Mašata, David; Vilímová, Eva; Škoda, Radek; Lovecký, Martin |
2020 | Basic design of the TEPLATOR core - construction | Závorka, Jiří; Lovecký, Martin; Škoda, Radek |
2018 | Burnable absorber layer in HTR coated particles for OTTO fuel cycle | Lovecký, Martin; Závorka, Jiří; Jiřičková, Jana; Škoda, Radek |
2020 | Development of neutron source for nuclear power plant decommissioning | Klímek Gincelová, Kristýna; Lovecký, Martin; Škoda, Radek |
2019 | Enhanced nuclear safety of spent fuel | Závorka, Jiří; Lovecký, Martin; Jiřičková, Jana; Škoda, Radek |
2023 | Experimental verification of new neutron absorbers concepts | Závorka, Jiří; Lovecký, Martin; Jiřičková, Jana; Škoda, Radek |
2019 | Feasibility of using erbium as burnable poison in VVER-1000 fuel assembly | Závorka, Jiří; Lovecký, Martin; Jiřičková, Jana; Škoda, Radek |
2018 | Fuel pebble optimization | Závorka, Jiří; Lovecký, Martin; Škoda, Radek |
2019 | Impact of burnable absobers on nuclear data uncertainty analysis for fuel assembly depletion | Lovecký, Martin; Závorka, Jiří; Jiřičková, Jana; Škoda, Radek |
2020 | Increasing efficiency of nuclear fuel using burnable absorbers | Lovecký, Martin; Závorka, Jiří; Jiřičková, Jana; Škoda, Radek |
2020 | Neutron absorber for VVER-1000 final disposal cask | Lovecký, Martin; Závorka, Jiří; Jiřičková, Jana; Škoda, Radek |
2021 | Neutron absorber for VVER-1000 storage, transport and final disposal facilities | Lovecký, Martin; Závorka, Jiří; Klímek Gincelová, Kristýna; Jiřičková, Jana; Škoda, Radek |
2020 | Performance of ENDF/B-VIII.0 library for VVER reactors criticality safety, fuel depletion and reactor dosimetry applications | Lovecký, Martin; Gincelová, Kristýna; Haroková, P.; Jiřičková, Jana; Smutný, Vladimír; Závorka, Jiří |
2021 | Potential of serpent-openFOAM coupled codes for spent nuclear fuel analysis | Kořínek, Tomáš; Závorka, Jiří; Lovecký, Martin; Škoda, Radek |
2020 | Radiation heating of VVER-4440 thermocouple | Lovecký, Martin; Šik, Jan |
2020 | Solution of full-core VVER-440 PK-3+calculation benchmark by serpent | Závorka, Jiří; Svobodová, Miroslava; Mikoláš, Pavel; Vimpel, Jan; Sprinzl, Daniel; Lovecký, Martin |
2020 | TEPLATOR: Nuclear district heating solution | Škoda, Radek; Fořtová, Anna; Mašata, David; Závorka, Jiří; Lovecký, Martin; Škarohlíd, Jan; Kolář, František; Vilímová, Eva; Peltan, Tomáš; Burian, Ondřej; Jiřičková, Jana |
2018 | VVER-1000 fuel assembly model in CAD-based unstructured mesh for MCNP6 | Lovecký, Martin; Závorka, Jiří; Vimpel, Jan |
2017 | Zvyšování účinnosti jaderného paliva použitím vyhořívajících absorbátorů | Lovecký, Martin |