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Slika profila

Davor Grgić

15756

Davor

Grgić

prof. dr. sc.

Naziv Uloga Akcije
Razvoj niza četverousisnih ventilatora za industrijska postrojenja voditelj
Razvoj digitalne platforme za izgradnju sustava zaštite kritičnih infrastruktura u pametnim industrijama – CIP 4 SI suradnik
Naziv Akcije
Šadek, Siniša; Pavlinac, Renato; Ivanjko, Karlo; Grgić, Davor Uncertainty and Sensitivity Evaluation of the QUENCH-02 Experiment Simulation Using the ASYST Code // Journal of nuclear engineering and radiation science, 10 (2024), 1; 011301, 11. doi: 10.1115/1.4062799
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
Ječmenica, Radomir; Grgić, Davor; Dučkić, Paulina Usage of Monte Carlo Code Serpent2 for Calculation of FHR Fuel Assembly // Proceedings of the 32nd International Conference Nuclear Energy for New Europe. Ljubljana: Nuclear Society of Slovenia, 2023. str. 429.1-429.11
Bašić, Ivica; Vrbanić, Ivan; Grgić, Davor Assessment of potential impact of combustible gases from reactor core damage on risk of outside containment spent fuel pool damage // Nuclear engineering and design, 2023 (2023), 407; 112268, 18. doi: https://doi.org/10.1016/j.nucengdes.2023.112268
Grgić, Davor; Dučkić, Paulina; Matijević, Mario; Šadek, Siniša The Assessment of Dose Rates during MPC Loading and Drying in frame of the Nuclear Power Plant Krško First SFDS Loading Campaign // Proceedings of the 32nd International Conference Nuclear Energy for New Europe. Ljubljana: Nuclear Society of Slovenia, 2023. str. 612.1-612.11
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; Dučkić, Paulina; Strmečki, Petra; Milobar, Juraj Thermal Model of HI STORM FW Cask for COBRA-SFS Code // Proceedings of the 13th International Conference of the Croatian Nuclear Society. Zagreb: Hrvatsko nuklearno društvo, 2022
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
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
Šadek, Siniša ; Pavlinac, Renato ; Ivanjko, Karlo ; Grgić, Davor Calculation of the QUENCH-02 Experiment with the ASYST Code Including the Uncertainty Evaluation // NENE 2022 Conference Proceedings / Jenčič, Igor (ur.). Ljubljana: Nuclear Society of Slovenia, 2022. str. 1-10
Naziv Uloga Akcije
Ansys licenca odgovorna osoba
nije evidentirano