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Grgić, Davor; Dučkić, Paulina; Benčik, Vesna; Šadek, Siniša
Dose Rate Assessment Around the PCFV Release Line During Severe Accident Conditions in Nuclear Power Plant Krsko // Journal of nuclear engineering and radiation science, 10 (2024), 1; 011701, 14. doi: 10.1115/1.4062797
Benčik, Vesna; Grgić, Davor; Šadek, Siniša
Analysis of Steam Generator Tube Rupture (SGTR) Accident using RELAP5/MOD 3.3 and TRACE 5.0p5 Codes // Proceedings of the 32nd International Conference Nuclear Energy for New Europe. Ljubljana: Nuclear Society of Slovenia, 2023
Grgić, Davor; Benčik, Vesna; Šadek, Siniša; Dučkić, Paulina
Influence of reactivity feedback modelling in RELAP5 NEK LONF ATWS calculation // Proceedings of the 13th International Conference of the Croatian Nuclear Society. Zagreb: Hrvatsko nuklearno društvo, 2022
Grgić, Davor ; Dučkić, Paulina ; Benčik, Vesna ; Šadek, Siniša
Dose Rate Assessment Around The PCFV Release Line During Severe Accident Conditions in Nuclear Power Plant Krsko // NENE 2022 Conference Proceedings / Jenčič, Igor (ur.). Ljubljana: Nuclear Society of Slovenia, 2022. str. 1-11
Grgić, Davor; Benčik, Vesna; Šadek, Siniša; Dučkić, Paulina
Thermal Response of External Duct Piping in Case PCFV Actuation During Prolonged NEK SBO // Proceedings of the 13th International Conference of the Croatian Nuclear Society. Zagreb: Hrvatsko nuklearno društvo, 2022
Benčik, Vesna ; Grgić, Davor ; Šadek, Siniša
NEK 3 inch Cold Leg Break LOCA Calculation using TRACE 5.0p5 and RELAP5/MOD 3.3 Codes // Proceedings of the 13th International Conference of the Croatian Nuclear Society / Vrbanić, Ivan ; Šadek, Siniša ; Trontl, Krešimir (ur.). Zagreb: Hrvatsko nuklearno društvo, 2022
Benčik, Vesna ; Grgić, Davor ; Šadek, Siniša
NPP Krško Large Break Loss of Coolant Accident using MELCOR Code // NENE2021 Conference Proceedings / Cizelj, Leon ; Tekavčič, Matej (ur.). Ljubljana: Društvo jedrskih strokovnjakov Slovenije | Nuclear Society of Slovenia, 2021. str. 420-1-420-9
Šadek, Siniša ; Grgić, Davor ; Benčik, Vesna ; Vlahović, Štefica
Analysis of the upflow conversion modification and influence on selected LOCA accidents in a PWR plant // Nuclear engineering and design, 369 (2020), 110854, 14. doi: 10.1016/j.nucengdes.2020.110854
Šadek, Siniša ; Grgić, Davor ; Vuković, Franjo ; Benčik, Vesna
Reactor Vessel Modelling with the MELCOR Code // Proceedings of the International Conference Nuclear Energy for New Europe 2019 / Smodiš, Borut ; Udir, Nina (ur.). Ljubljana: Nuclear Society of Slovenia, 2019
Vlahović, Štefica ; Šadek, Siniša ; Grgić, Davor ; Fancev, Tomislav ; Benčik, Vesna
Comparison of Measured and Calculated Data for NPP Krško CILR Test // Energies (Basel), 12 (2019), 11; 2176, 13. doi: 10.3390/en12112176