Na FER-u postoji više zaposlenika s imenom




    prof. dr. sc. Davor Grgić

    Redoviti profesor, Zavod za visoki napon i energetiku

    Small break LOCA studies for different layouts of passive safety systems in the IRIS reactor

    Šadek, Siniša; Grgić, Davor; Družijanić, Paulina
    izvorni znanstveni rad, 2025.
    Nuclear engineering and design

    Gamma Dose Rate Calculations for RCC4 and RCC8 Containers using Monte Carlo Codes

    Družijanić, Paulina; Grgić, Davor; Ječmenica, Radomir; Šadek, Siniša
    izvorni znanstveni rad, 2024.

    Calculation and Uncertainty Quantification of the QUENCH-03 Experiment Simulation Using the ASYST Code

    Strmečki, Petra; Šadek, Siniša; Grgić, Davor
    izvorni znanstveni rad, 2024.

    Benchmark Calculation of FHR Fuel Assembly Phase I-C Depletion Exercises

    Ječmenica, Radomir; Grgić, Davor; Družijanić, Paulina
    izvorni znanstveni rad, 2024.

    Radiation dose rate analysis of conceptual solution for the Croatian low- and intermediate-level radioactive waste

    Grgić, Davor; Družijanić, Paulina; Ječmenica, Radomir; Šadek, Siniša; Matijević, Mario
    izvorni znanstveni rad, 2024.

    Development of the Numerical Model of the IRIS Reactor for Severe Accident Analysis

    Šadek, Siniša; Grgić, Davor; Strmečki, Petra
    izvorni znanstveni rad, 2024.

    Dose Rate Assessment Around the PCFV Release Line During Severe Accident Conditions in Nuclear Power Plant Krsko

    Grgić, Davor; Dučkić, Paulina; Benčik, Vesna; Šadek, Siniša
    izvorni znanstveni rad, 2024.
    Journal of nuclear engineering and radiation science

    Uncertainty and Sensitivity Evaluation of the QUENCH-02 Experiment Simulation Using the ASYST Code

    Šadek, Siniša; Pavlinac, Renato; Ivanjko, Karlo; Grgić, Davor
    izvorni znanstveni rad, 2024.
    Journal of nuclear engineering and radiation science

    NPP Krško Steam Generator Tube Rupture (SGTR) Accident Analysis using MELCOR Code

    Benčik, Vesna; Grgić, Davor; Šadek, Siniša; Družijanić, Paulina
    izvorni znanstveni rad, 2024.

    Natural Heat Transfer Performance of Helium Filled Spent Fuel Multi Purpose Container Calculated for Different Initial Pressures

    Grgić, Davor; Novosel, Nikola; Družijanić, Paulina; Strmečki, Petra
    izvorni znanstveni rad, 2024.

    Calculation of Unmitigated Small Break Loss of Coolant Accident for the IRIS Reactor

    Šadek, Siniša; Grgić, Davor; Strmečki, Petra
    izvorni znanstveni rad, 2024.

    Analysis of Steam Generator Tube Rupture (SGTR) Accident using RELAP5/MOD 3.3 and TRACE 5.0p5 Codes

    Benčik, Vesna; Grgić, Davor; Šadek, Siniša
    izvorni znanstveni rad, 2023.

    Usage of Monte Carlo Code Serpent2 for Calculation of FHR Fuel Assembly

    Ječmenica, Radomir; Grgić, Davor; Dučkić, Paulina
    pregledni rad (znanstveni), 2023.

    Assessment of potential impact of combustible gases from reactor core damage on risk of outside containment spent fuel pool damage

    Bašić, Ivica; Vrbanić, Ivan; Grgić, Davor
    izvorni znanstveni rad, 2023.
    Nuclear engineering and design

    The Assessment of Dose Rates during MPC Loading and Drying in frame of the Nuclear Power Plant Krško First SFDS Loading Campaign

    Grgić, Davor; Dučkić, Paulina; Matijević, Mario; Šadek, Siniša
    pregledni rad (znanstveni), 2023.

    NEK 3 inch Cold Leg Break LOCA Calculation using TRACE 5.0p5 and RELAP5/MOD 3.3 Codes

    Benčik, Vesna ; Grgić, Davor ; Šadek, Siniša
    izvorni znanstveni rad, 2022.

    Dose Rate Assessment Around The PCFV Release Line During Severe Accident Conditions in Nuclear Power Plant Krsko

    Grgić, Davor ; Dučkić, Paulina ; Benčik, Vesna ; Šadek, Siniša
    izvorni znanstveni rad, 2022.

    Thermal Model of HI STORM FW Cask for COBRA-SFS Code

    Grgić, Davor; Dučkić, Paulina; Strmečki, Petra; Milobar, Juraj
    sažetak izlaganja sa skupa, 2022.

    Thermal Response of External Duct Piping in Case PCFV Actuation During Prolonged NEK SBO

    Grgić, Davor; Benčik, Vesna; Šadek, Siniša; Dučkić, Paulina
    sažetak izlaganja sa skupa, 2022.

    Influence of reactivity feedback modelling in RELAP5 NEK LONF ATWS calculation

    Grgić, Davor; Benčik, Vesna; Šadek, Siniša; Dučkić, Paulina
    sažetak izlaganja sa skupa, 2022.

    Estimation of Dose Rates Around Dry Storage Building During Campaign One Loading in Nuclear Power Plant Krsko

    Dučkić, Paulina ; Grgić, Davor ; Matijević, Mario ; Ječmenica Radomir
    izvorni znanstveni rad, 2022.

    Radiation shielding analysis of the HI-STORM FW storage cask

    Grgić, Davor ; Matijević, Mario ; Dučkić, Paulina ; Ječmenica, Radomir
    izvorni znanstveni rad, 2022.
    Nuclear engineering and design

    Assessment of extending operation of Nuclear Power Plant Krško from 2023 to 2043 – techno economic, ecological and power flow and system dynamics influence

    Tomšić, Željko ; Rajšl, Ivan , Herenčić, Lin ; Holjevac, Ninoslav ; Kuzle, Igor ; Grgić, Davor
    izvorni znanstveni rad, 2022.

    Uncertainty Study of the In-Vessel Phase of a Severe Accident in a Pressurized Water Reactor

    Šadek, Siniša ; Grgić, Davor ; Allison, Chris ; Perez-Ferragut, Marina
    izvorni znanstveni rad, 2022.
    Energies (Basel)

    Calculation of the QUENCH-02 Experiment with the ASYST Code Including the Uncertainty Evaluation

    Šadek, Siniša ; Pavlinac, Renato ; Ivanjko, Karlo ; Grgić, Davor
    izvorni znanstveni rad, 2022.

    Preliminary Uncertainty Assessment of a Severe Accident Scenario Using the ASYST Code

    Šadek, Siniša ; Grgić, Davor ; Allison, Chris
    izvorni znanstveni rad, 2021.

    Methodology to calculate radiological impact for NPP Krško life time extension environmental impact assessment

    Grgić, Davor ; Šadek, Siniša ; Dučkić, Paulina ; Mlakar, Primož ; Božnar, Marija Zlata ; Grašič, Boštjan
    izvorni znanstveni rad, 2021.

    Spent Fuel Dry Storage Loading Plan Based on Uniform Decay Heat Distribution among Casks

    Dučkić, Paulina ; Grgić, Davor ; Šadek, Siniša ; Vlahović, Štefica
    izvorni znanstveni rad, 2021.

    NPP Krško Large Break Loss of Coolant Accident using MELCOR Code

    Benčik, Vesna ; Grgić, Davor ; Šadek, Siniša
    izvorni znanstveni rad, 2021.

    Analysis of the HI-TRAC VW Transfer Cask Dose Rates During Nuclear Power Plant Krsko Spent Fuel Dry Storage Campaign One

    Grgić, Davor ; Matijević, Mario ; Dučkić, Paulina ; Ječmenica, Radomir
    izvorni znanstveni rad, 2021.
    Journal of nuclear engineering and radiation science

    Analysis of the upflow conversion modification and influence on selected LOCA accidents in a PWR plant

    Šadek, Siniša ; Grgić, Davor ; Benčik, Vesna ; Vlahović, Štefica
    izvorni znanstveni rad, 2020.
    Nuclear engineering and design

    Room Classification Based on EMC Conditions in Nuclear Power Plants

    Grganić, Hrvoje ; Grgić, Davor ; Šadek, Siniša
    izvorni znanstveni rad, 2020.
    Energies (Basel)

    Analysis of the HI-TRAC VW Transfer Cask Dose Rates During Nuclear Power Plant Krsko Spent Fuel Dry Storage Campaign One

    Dučkić, Paulina ; Grgić, Davor ; Matijević, Mario ; Ječmenica, Radomir
    izvorni znanstveni rad, 2020.

    A new heuristics for the event ordering in binary decision diagram applied in fault tree analysis

    Banov, Reni; Šimić, Zdenko; Grgić, Davor
    izvorni znanstveni rad, 2019.
    Proceedings of the Institution of Mechanical Engineers Part O-Journal of Risk and Reliability

    Hazard Assessment of NPP Krško for Republic of Croatia

    Medaković, Saša ; Rašeta, Davor ; Grgić, Davor
    izvorni znanstveni rad, 2019.
    Energija : časopis Hrvatske elektroprivrede

    Dose Calculation for Emergency Control Room HVAC Filter

    Grgić, Davor ; Vlahović, Štefica ; Matijević, Mario ; Dučkić, Paulina
    izvorni znanstveni rad, 2019.
    Energija : časopis Hrvatske elektroprivrede

    Influence of Spacer Grids Homogenization on Core Reactivity and Axial Power Distribution

    Ječmenica, Radomir ; Grgić, Davor ; Matijević, Mario
    izvorni znanstveni rad, 2019.
    Energija : časopis Hrvatske elektroprivrede

    Comparison of Measured and Calculated Data for NPP Krško CILR Test

    Vlahović, Štefica ; Šadek, Siniša ; Grgić, Davor ; Fancev, Tomislav ; Benčik, Vesna
    izvorni znanstveni rad, 2019.
    Energies (Basel)

    Point Kernel Modification Including Support Vector Regression Neutron Buildup Factor Models

    Dučkić, Paulina ; Trontl, Krešimir ; Grgić, Davor ; Matijević, Mario
    izvorni znanstveni rad, 2019.
    Energija : časopis Hrvatske elektroprivrede

    Reactor Vessel Modelling with the MELCOR Code

    Šadek, Siniša ; Grgić, Davor ; Vuković, Franjo ; Benčik, Vesna
    izvorni znanstveni rad, 2019.

    Application of Fractional Scaling Analysis for development and design of Integral Effects Test facility

    Dzodzo, Milorad B. ; Oriolo, Francesco ; Ambrosini, Walter ; Ricotti, Marco ; Grgić, Davor ; Ferri, Roberta ; Achilli, Andrea ; Bianchi, Fosco ; Meloni, Paride
    izvorni znanstveni rad, 2019.
    Journal of nuclear engineering and radiation science

    ENERGETSKA TRANZICIJA PREMA TRANSFORMACIJI ENERGETIKE

    Tomšić, Željko ; Krajcar, Slavko ; Kuzle, Igor ; Grgić, Davor
    sažetak izlaganja sa skupa, 2019.

    Evaluation of the NEK SFDS Cask Model Using Hybrid Shielding Methodology

    Grgić, Davor ; Matijević, Mario ; Ječmenica, Radomir ; Dučkić, Paulina
    izvorni znanstveni rad, 2019.

    Contribution of FER to the WP4: summary report for the first year, TA2/SARNET ASCOM Technical report

    Šadek, Siniša ; Grgić, Davor
    izvještaj, 2019.

    Calculation of Radioactive Inventory for Severe Accident and Consequence Codes

    Grgić, Davor ; Vlahović, Štefica ; Ječmenica, Radomir ; Bašić, Ivica
    izvorni znanstveni rad, 2018.

    Hybrid Shielding Methods Validation Using Graphite Shielding Measurements

    Matijević, Mario ; Trontl, Krešimir ; Dučkić, Paulina ; Grgić, Davor
    izvorni znanstveni rad, 2018.

    Point Kernel Modification Including Support Vector Regression Neutron Buildup Factor Models

    Dučkić, Paulina ; Trontl, Krešimir ; Grgić, Davor ; Matijević, Mario
    izvorni znanstveni rad, 2018.

    NPP Krško 3 inch Cold Leg Break LOCA Calculation using RELAP5/MOD 3.3 and MELCOR 1.8.6 Codes

    Benčik, Vesna ; Grgić, Davor ; Šadek, Siniša ; Vlahović, Štefica
    izvorni znanstveni rad, 2018.

    Fuel Handling Building Response to SFP Loss of Cooling

    Grgić, Davor ; Fancev, Tomislav ; Šadek, Siniša ; Špalj, Srđan
    sažetak izlaganja sa skupa, 2018.

    Influence of Detailed PCFV Model on Containment Behaviour During SBO

    Šadek, Siniša ; Grgić, Davor ; Benčik, Vesna ; Mileta, Kristina ; Špalj, Srđan
    izvorni znanstveni rad, 2018.

    Dose Calculation for Emergency Control Room HVAC Filter

    Grgić, Davor ; Vlahović, Štefica ; Matijević, Mario ; Dučkić, Paulina ; Špalj, Srđan
    izvorni znanstveni rad, 2018.

    Effectiveness of SFP Spray Cooling during Loss of Coolant Accidents

    Vlahović, Štefica ; Grgić, Davor ; Đaković, Josip ; Šadek, Siniša ; Bašić, Ivica
    izvorni znanstveni rad, 2018.

    NPP Krsko IB Modelling with GOTHIC and MELCOR Codes

    Grgić, Davor ; Vlahović, Štefica ; Fancev, Tomislav ; Šadek, Siniša ; Benčik, Vesna
    sažetak izlaganja sa skupa, 2018.

    Comparison of Measured and Calculated Data for NPP Krško CILR Test

    Vlahović, Štefica ; Grgić, Davor ; Šadek, Siniša ; Fancev, Tomislav ; Benčik, Vesna
    sažetak izlaganja sa skupa, 2018.

    Comparison Between ORIGEN2.2 and ORIGEN-S Calculated Source Term

    Grgić, Davor ; Ječmenica, Radomir ; Vlahović, Štefica ; Šadek, Siniša ; Bašić, Ivica
    sažetak izlaganja sa skupa, 2018.

    Influence of Spacer Grids Homogenization on Core Reactivity and Axial Power Distribution

    Ječmenica, Radomir ; Grgić, Davor ; Matijević, Mario
    izvorni znanstveni rad, 2018.

    Radioactive Inventory Data for Severe Accident and Consequence Calculation Codes

    Grgić, Davor ; Ječmenica, Radomir ; Vlahović, Štefica ; Bašić, Ivica
    sažetak izlaganja sa skupa, 2017.

    Application of ASTEC, MELCOR, and MAAP Computer Codes for Thermal Hydraulic Analysis of a PWR Containment Equipped with the PCFV and PAR Systems

    Šadek, Siniša ; Grgić, Davor ; Šimić, Zdenko
    izvorni znanstveni rad, 2017.
    Science and technology of nuclear installations

    Calculation of NEK CILR Test Using GOTHIC Code

    Grgić, Davor ; Šadek, Siniša ; Fancev, Tomislav ; Benčik, Vesna
    sažetak izlaganja sa skupa, 2017.

    Operation and Performance Analysis of Steam Generators in Nuclear Power Plants

    Šadek, Siniša ; Grgić, Davor
    izvorni znanstveni rad, 2017.

    I2S-LWR Concept Update

    Petrovic, Bojan ; Rahnema, Farzad ; Deo, Chaitanya ; Garimella, Srinivas ; Singh, Preet ; Oh, KkochNim ; Yi, Ce ; Zhang, Dingkang ; Manera, Annalisa ; Lee, John ; Downar, Thomas ; Ward, Andrew ; Ferroni, Paolo ; Franceschini, Fausto ; Salazar, David, Upadhyaya, Belle ; Lish, Matt ; Charit, Indrajit ; Haghighat, Alireza ; Memmott, Matthew ; Boy, Guy ; Ougouag Abderrafi ; Parks, Geoffrey ; Kotlyar, Dan ; Ricotti, Marco ; Čavlina, Nikola ; Grgić, Davor ; Pevec, Dubravko ; Matijević, Mario ; Irvin, Nick
    izvorni znanstveni rad, 2017.

    Analysis of Spent Fuel Pool Loss of Coolant Inventory Accident Progression

    Đaković, Josip ; Grgić, Davor
    izvorni znanstveni rad, 2017.
    Energija : časopis Hrvatske elektroprivrede

    Spent Fuel Pool Dose Rate Calculations Using Point Kernel and Hybrid Deterministic-Stochastic Shielding Methods

    Matijević, Mario ; Ječmenica, Radomir ; Grgić, Davor
    izvorni znanstveni rad, 2016.

    Nuclear and thermal hydraulic calculation of a representative I2S-LWR first core

    Ječmenica, Radomir ; Grgić, Davor ; Matijević, Mario ; Petrović, Bojan
    izvorni znanstveni rad, 2016.
    Energija : časopis Hrvatske elektroprivrede

    Proceedings of the 11th International Conference of the Croatian Nuclear Society


    zbornik radova s konferencije, 2016.

    Spent Fuel Pool Dose Rate Calculations Using Point Kernel and Hybrid Deterministic-Stochastic Shielding Methods

    Matijević, Mario ; Ječmenica, Radomir ; Grgić, Davor
    izvorni znanstveni rad, 2016.
    Energija : časopis Hrvatske elektroprivrede

    Neutron Buildup Factors Calculation for Support Vector Regression Application in Shielding Analysis

    Dučkić, Paulina ; Matijević, Mario ; Grgić, Davor
    izvorni znanstveni rad, 2016.

    Preparation of Radioactive Inventory Data for Severe Accident and Consequence Calculation Codes

    Pavić, Matea ; Grgić, Davor ; Tomšić, Željko
    sažetak izlaganja sa skupa, 2016.

    NPP Krško Post-UFC Transient Response during MSLB

    Vlahović, Štefica ; Grgić, Davor ; Benčik, Vesna
    izvorni znanstveni rad, 2016.

    NPP Krško Station Blackout Analysis after Safety Upgrade Using MELCOR Code

    Šadek, Siniša ; Grgić, Davor ; Benčik, Vesna
    izvorni znanstveni rad, 2016.

    Verification of GOTHIC Multivolume Containment Model during NPP Krško DBA LOCA

    Fancev, Tomislav ; Grgić, Davor ; Šadek, Siniša
    izvorni znanstveni rad, 2016.

    Nuclear and thermal hydraulic calculation of a representative I2S-LWR first core

    Ječmenica, Radomir ; Grgić, Davor ; Matijević, Mario ; Petrović, Bojan
    izvorni znanstveni rad, 2016.

    Independent Review of NPP Modifications and Safety Upgrades

    Grgić, Davor ; Benčik, Vesna ; Šadek, Siniša ; Bašić, Ivica
    stručni rad, 2015.
    International journal of contemporary energy

    Posljedice ispusta plinovitog radioaktivnog materijala iz nuklearne elektrane na okoliš

    Filipović, Matea
    diplomski rad (sveučilišni), 2015.

    Severe accident gamma dose distribution through NPP Krško containment and auxiliary building calculated using SCALE6/MAVRIC sequence

    Matijević, Mario ; Grgić, Davor ; Pevec, Dubravko
    izvorni znanstveni rad, 2015.

    NPP Krško DVI LOCA Calculation using RELAP5/mod 3.3 and FRAPTRAN to Assess UFC Modification Influence

    Benčik, Vesna ; Grgić, Davor ; Šadek, Siniša ; Čavlina, Nikola
    izvorni znanstveni rad, 2015.

    Optimization of OPDT Protection for Overcooling Accidents

    Benčik, Vesna ; Grgić, Davor ; Šadek, Siniša ; Čavlina , Nikola
    izvorni znanstveni rad, 2014.

    Fuel Depletion Modeling of Reconstituted NEK Fuel Assembly Using Lattice Cell Programs

    Ječmenica, Radomir ; Matijević, Mario ; Grgić, Davor
    izvorni znanstveni rad, 2014.

    Decay Heat Calculation for Spent Fuel Pool Application

    Grgić, Davor ; Šadek, Siniša ; Benčik, Vesna ; Konjarek , Damir
    izvorni znanstveni rad, 2014.

    Razvoj modela primarnog kruga NE Krško za program TRACE

    Dučkić, Paulina
    diplomski rad (sveučilišni), 2014.

    Hot Leg Streaming Calculation for Two-Loop PWR Plant

    Grgić, Davor ; Fancev, Tomislav ; Benčik, Vesna ; Šadek, Siniša
    izvorni znanstveni rad, 2014.

    Calculation of Hydrogen Concentration in Containment during LOCA Accident

    Grgić, Davor ; Fancev, Tomislav ; Šadek, Siniša
    izvorni znanstveni rad, 2014.

    NPP Krško Containment Modelling with the ASTEC Code

    Šadek, Siniša ; Grgić, Davor
    izvorni znanstveni rad, 2014.

    Radiation Doses Estimation For Hypothetical NPP Krško Accidents Without And With PCFV Using RASCAL Software

    Vuković, Josip ; Konjarek, Damir ; Grgić, Davor
    izvorni znanstveni rad, 2014.

    Spatial Distribution of Hydrogen in NEK Containment

    Grgić, Davor ; Fancev, Tomislav ; Šadek, Siniša ; Benčik, Vesna
    izvorni znanstveni rad, 2014.

    Coupled code calculation of rod withdrawal at power accident

    Grgić, Davor ; Benčik, Vesna ; Šadek, Siniša
    izvorni znanstveni rad, 2013.
    Nuclear engineering and design

    Severe Accident Analysis in a Two-Loop PWR Nuclear Power Plant with the ASTEC Code

    Šadek, Siniša ; Amižić, Milan ; Grgić, Davor
    izvorni znanstveni rad, 2013.
    Atw-internationale zeitschrift fur kernenergie

    Severe Accident Analysis in the NPP Krško with the ASTEC Code

    Šadek, Siniša ; Amižić, Milan ; Grgić, Davor
    izvorni znanstveni rad, 2013.

    Radiation heat transfer in a pressurized water reactor lower head filled with molten corium

    Šadek, Siniša ; Grgić, Davor ; Debrecin, Nenad
    izvorni znanstveni rad, 2013.
    Nuclear engineering and design

    Liquid-salt-cooled Reactor Start-up with Natural Circulation

    Gros, Emilien ; Petrović, Bojan ; Grgić, Davor
    izvorni znanstveni rad, 2012.

    SPES3 Facility RELAP5 Sensitivity Analyses on the Containment System for Design Review

    Achilli, Andrea ; Congiu, Cinzia ; Ferri, Roberta ; Bianchi, Fosco ; Meloni, Paride ; Grgić, Davor ; Dzodzo, Milorad
    izvorni znanstveni rad, 2012.
    Science and technology of nuclear installations

    Prediction of Local Hydrogen Concentrations in PWR Containment Using GOTHIC Code

    Grgić, Davor ; Šimić, Zdenko ; Glaser, Bruno
    izvorni znanstveni rad, 2012.

    Analysis of Steam Generator Tube Rupture (SGTR) Accident for NPP Krško

    Benčik, Vesna ; Grgić, Davor ; Čavlina, Nikola
    izvorni znanstveni rad, 2012.

    Program kondicijske pripreme vrhunske juniorske tenisačice u pripremnom periodu

    Novak, Dario ; Felgate, David ; Grgić, Davor ; Nikolić, Milan ; Vekić, Brankica ; Vekić, Igor
    stručni rad, 2012.
    Kondicijski trening

    Uncertainty Evaluation of the Rod Withdrawal at Power Accident Analysis including 3D Neutron Kinetics

    Bajs, Tomislav ; Petruzzi, Alessandro ; Grgić, Davor
    izvorni znanstveni rad, 2012.

    Lattice Codes Pin Power Prediction Comparison

    Grgić, Davor ; Ječmenica, Radomir ; Pevec, Dubravko
    izvorni znanstveni rad, 2012.
    Nuclear engineering and design

    Analysis of Rod Withdrawal at Power (RWAP) Accident using ATHLET Mod 2.2 Cycle A and RELAP5/mod 3.3 Codes

    Benčik, Vesna ; Čavlina, Nikola ; Grgić, Davor
    izvorni znanstveni rad, 2012.

    Xenon Correction in Homogenized Neutron Cross Sections

    Grgić, Davor ; Ječmenica, Radomir ; Pevec, Dubravko
    izvorni znanstveni rad, 2012.

    Testing of an Integral Layout SMR on the SPES3 Facility: BDBE Simulation and Influence of the PCC Actuation Delay on the Accident Recovery

    Roberta Ferri ; Andrea Achilli ; Cinzia Congiu ; Gustavo Cattadori ; Fosco Bianchi ; Paride Meloni ; Stefano Monti ; Alfredo Luce ; Marco Enrico Ricotti ; Davide Papini ; Grgić, Davor
    izvorni znanstveni rad, 2011.

    Analysis of Different Containment Models for IRIS Small Break LOCA using GOTHIC and RELAP5 codes

    Papini, Davide ; Grgić, Davor ; Cammi, Antonio ; Ricotti, Marco E.
    izvorni znanstveni rad, 2011.
    Nuclear engineering and design

    Coupled Code Calculation of Rod Withdrawal at Power Accident

    Grgić, Davor ; Benčik, Vesna ; Čavlina, Nikola ; Šadek, Siniša
    izvorni znanstveni rad, 2011.

    Precursor Based PTS Screening Methodology of the EOP Operator Actions for PWR Plant

    Bajs, Tomislav ; Iveković, Ilijana ; Bašić, Ivica ; Grgić, Davor
    izvorni znanstveni rad, 2011.

    Prediction Capabilities of Spectral Codes DRAGON, FA2D, NEWT

    Ječmenica, Radomir ; Grgić, Davor ; Pevec, Dubravko
    izvorni znanstveni rad, 2010.

    Condensation within Small Compartments during Design Basis Accidents

    Grgić, Davor ; Čavlina, Nikola ; Antolovič, Aleksandra
    izvorni znanstveni rad, 2010.

    RELAP5 Modeling of PWR Reactor RTD Bypass

    Grgić, Davor ; Benčik, Vesna ; Šadek, Siniša ; Čavlina, Nikola
    izvorni znanstveni rad, 2010.

    Upgrade of the FUMACS 2005 Code Package

    Pevec, Dubravko ; Trontl, Krešimir ; Ječmenica, Radomir ; Matijević, Mario ; Grgić, Davor ; Belavić, Tomislav
    izvorni znanstveni rad, 2010.

    Corium Behaviour and the Lower Head Thermal Response after a Core Meltdown

    Šadek, Siniša ; Grgić, Davor ; Debrecin, Nenad
    izvorni znanstveni rad, 2010.

    Comparison of R5G Coupled Code and Classical “Two-steps” Containment Calculation

    Grgić, Davor ; Benčik, Vesna ; Šadek, Siniša
    izvorni znanstveni rad, 2010.

    ORIGEN2.1 Cycle Specific Calculation of Krško Nuclear Power Plant Decay Heat and Core Inventory

    Vuković, Josip ; Grgić, Davor ; Konjarek, Damir
    izvorni znanstveni rad, 2010.

    Spectral Codes Pin Power Prediction Comparison

    Grgić, Davor ; Ječmenica, Radomir ; Pevec, Dubravko
    izvorni znanstveni rad, 2010.

    SPES3 Facility and IRIS Reactor Numerical Simulations For The SPES3 Final Design

    R. Ferri ; A. Achilli ; C. Congiu ; G. Cattadori ; M. Greco ; F. Bianchi ; P. Meloni ; S. Monti ; A. Luce ; M.E. Ricotti ; Grgić, Davor ; G. D. Storrick ; M. Dzodzo ; M.D. Carelli
    izvorni znanstveni rad, 2010.

    Analysis of OECD/CSNI ISP-42 Phase A PANDA Experiment Using RELAP5/mod3.3 and GOTHIC 7.2a Codes

    Benčik, Vesna ; Debrecin, Nenad ; Grgić, Davor
    izvorni znanstveni rad, 2009.

    Analysis of Different Containment Models for IRIS Small Break LOCA, using GOTHIC and RELAP5 Codes

    Papini, Davide ; Cammi, Antonio ; Ricotti, Marco ; Grgić, Davor
    izvorni znanstveni rad, 2009.

    Upgrade of FUMACS Code Package for Modeling of NGF and Gadolinium, Final Report

    Pevec, Dubravko ; Šmuc, Tomislav ; Grgić, Davor ; Trontl, Krešimir ; Ječmenica, Radomir ; Gergeta, Kristijan ; Matijević, Mario
    elaborat/studija, 2009.

    Pristup prostorno ovisnom proracunu jezgre tlakovodnog rekatora

    Iveković, Ilijana
    magistarski rad (znanstveni), 2009.

    The SPES3 Experimental Facility Design for the IRIS Reactor Simulation

    Carelli, Mario ; Conway, Lawrence ; Dzodzo, Milorad ; Maioli, Andrea ; Oriani, Luca ; Storrick, Gary ; Petrović, Bojan ; Achilli, Andrea ; Cattadori, Gustavo ; Congiu, Cinzia ; Ferri, Roberta ; Ricotti, Marco ; Papini, Davide ; Bianchi, Fosco ; Meloni, Paride ; Monti, Stefano ; Berra, Fabio ; Grgić, Davor ; Yoder, Graydon ; Alemberti, Alessandro
    ostalo, 2009.
    Science and technology of nuclear installations

    Sensitivity Studies of Fuel Pin Temperature for PWR Fuel Assemblies Containing Burnable Absorbers

    Grgić, Davor ; Ječmenica, Radomir ; Pevec, Dubravko
    izvorni znanstveni rad, 2009.

    Analysis of In-Vessel Severe Accident Phenomena in NPP Krško

    Šadek, Siniša ; Grgić, Davor ; Čavlina, Nikola
    izvorni znanstveni rad, 2008.

    Verification of FA2D Prediction Capability Using Fuel Assembly Benchmark

    Ječmenica, Radomir ; Pevec, Dubravko ; Grgić, Davor ; Konjarek, Damir
    izvorni znanstveni rad, 2008.

    Modelling of Condensation in Vertical Tubes for Passive Safety Systems

    Papini, Davide ; Ricotti, Marco ; Santini, Lorenzo ; Grgić, Davor
    izvorni znanstveni rad, 2008.

    Influence of Thermal-Hydraulic Model to Fuel Management Core Calculation

    Iveković, Ilijana ; Grgić, Davor ; Nemec, Tomaž
    izvorni znanstveni rad, 2008.

    Influence of NPP Krško Core Nuclear Characteristics on RCCA Ejection Accident

    Iveković, Ilijana ; Grgić, Davor ; Pevec, Dubravko ; Vuković, Josip
    izvorni znanstveni rad, 2008.

    Potential advantages and disadvantages of sequential building small nuclear units instead of a large nuclear power plant

    Feretić, Danilo ; Čavlina, Nikola ; Grgić, Davor
    izvorni znanstveni rad, 2008.
    Kerntechnik

    Comparison of economy and emissions of nuclear power plants and combined gas and wind electricty generators

    Feretić, Danilo ; Grgić Davor
    izvorni znanstveni rad, 2007.
    Kerntechnik

    Analiza osjetljivosti akcidenta izbacivanja kontrolnog sklopa na nuklearne karakteristike jezgre NE Krško

    Vuković, Josip
    diplomski rad (sveučilišni), 2007.

    Visokonaponski nadzemni elektroenergetski vodovi i primjena Pravilnika o zaštiti od elektromagnetskih polja

    Pavić, Armin ; Grgić, Davor ; Stanić, Zoran ; Delonga, Ante
    izvorni znanstveni rad, 2007.

    Neutronic model development for calculus of a PWR reflector

    Matijević, Mario
    diplomski rad (sveučilišni), 2007.

    NPP Krško Core Calculations to Improve Operational Safety

    Iveković, Ilijana ; Grgić, Davor ; Nemec, Tomaž
    izvorni znanstveni rad, 2007.

    Evaluation of Accident Sequences in IRIS Relevant for Revising the Need for Relocation and Evacuation Measures Unique to NPPs for Innovative SMRs

    Grgić, Davor ; Špalj, Srđan ; Šadek, Siniša ; Iveković, Ilijana
    izvještaj, 2006.

    Priprema ulaznih podataka za NE Krško za program TRACE

    Konjarek, Damir
    diplomski rad (sveučilišni), 2006.

    Anticipated Transient Without Scram Analysis for NPP Krško using Point Kinetics Option and Coupled Code

    Iveković, Ilijana ; Čavlina, Nikola ; Grgić, Davor
    izvorni znanstveni rad, 2006.

    Hydrogen Behaviour in NEK Containment Calculated Using GOTHIC Lumped and Distributed Volume Options

    Keco, Mario ; Grgić, Davor ; Bilić-Zabric, Tea
    izvorni znanstveni rad, 2006.

    Main Steam Line Break – Hot Full Power Analysis for NPP Krško Using RELAP5/PARCS Coupled Code

    Grgić, Davor ; Špalj, Srđan ; Bajs, Tomislav
    izvorni znanstveni rad, 2006.

    3D Simulation of a High Pressure Water Injection Into a Circular Cold Leg Pipe Flow

    Bašić, Ivica ; Grgić, Davor
    izvorni znanstveni rad, 2006.

    IRIS – Progress in Licensing and Toward Deployment

    Petrović, Bojan ; Carelli, M.D. ; Čavlina, Nikola ; Grgić, Davor
    izvorni znanstveni rad, 2006.

    Moguća uloga naprednog nuklearnog reaktora IRIS u hrvatskom elektroenergetskom sustavu

    Čavlina, Nikola ; Tomšić, Željko ; Grgić, Davor ; Petrović, Bojan ; Carelli, Mario D.
    ostalo, 2006.
    Elektroenergetika (Zagreb)

    Applicability of Coupled Code RELAP5/GOTHIC to NPP Krško MSLB Calculation

    Keco, Mario ; Debrecin, Nenad ; Grgić, Davor
    izvorni znanstveni rad, 2005.

    IRIS - Napredni integralni nuklearni reaktor modularne izvedbe

    Čavlina, Nikola ; Grgić, Davor ; Pevec, Dubravko ; Carelli, Mario ; Petrović, Bojan
    pregledni rad (znanstveni), 2005.
    Energija : časopis Hrvatske elektroprivrede

    3D Simulation of a High Pressure Water Injection Into a Circular Cold Leg Pipe Flow

    Bašić, Ivica ; Grgić, Davor
    izvorni znanstveni rad, 2005.

    IRIS (International Reactor Innovative and Secure) - Design Overview and Deployment Prospects

    Carelli, M.D. ; Petrović, Bojan ; Čavlina, Nikola ; Grgić, Davor
    izvorni znanstveni rad, 2005.

    IRIS - napredni nuklearni reaktor srednje snage s poboljšanom sigurnošću i ekonomičnošću

    Čavlina, Nikola ; Grgić, Davor ; Tomšić, Željko ; Petrović, Bojan ; Carelli, Mario D.
    izvorni znanstveni rad, 2005.

    IRIS - napredni nuklearni reaktor srednje snage s poboljšanom sigurnošću i ekonomičnošću

    Čavlina, Nikola ; Grgić, Davor ; Tomšić, Željko ; Petrović, Bojan ; Carelli, Mario D.
    sažetak izlaganja sa skupa, 2005.

    IRIS Design Overview and Status Update

    Carelli, M.D. ; Petrović, B. ; Conway, L.E. ; Oriani, L. ; Kling, C.L. ; Miller, V ; Lombardi, C.V. ; Ricotti, M.E. ; Barroso, A.C.O. ; Collado, J.M. ; Cinotti, L. ; Storai, S. ; Berra, F. ; Todreas, N.E. ; Ninokata, H. ; Čavlina, N. ; Grgić, D. ; Oriolo, F. ; Moraes, M.M. ; Frederico, C. ; Henning, F. ; Griffith, W. ; Love, J. ; Ingersoll, D.T. ; Wood, R. ; Alonso, G. ; Kodochigov, N. ; Polunichev, V. ; Augutis, J. ; Alzbutas, R. ; Boroughs, R.D. ; Naviglio, A. ; Panella, B.
    ostalo, 2005.

    IRIS - NAPREDNI NUKLEARNI REAKTOR SREDNJE SNAGE S POBOLJŠANOM SIGURNOŠĆU I EKONOMIČNOŠĆU

    Čavlina , Nikola ; Grgić , Davor ; Tomšić , Željko ; Petrović , Bojan ; Carelli , Mario D.
    izvorni znanstveni rad, 2005.

    Analysis of future nuclear power plants competitive investment costs with stochastic methods

    Feretić, Danilo ; Čavlina, Nikola ; Grgić, Davor
    izvorni znanstveni rad, 2005.
    Kerntechnik

    Radiation Dose Specification for Equipment Qulaification

    Špalj, Srđan ; Grgić, Davor ; Čavlina, Nikola
    stručni rad, 2004.

    Use of the Deterministic Safety Analyses in Support to the NPP Krško Modifications

    Feretić, Danilo ; Čavlina, Nikola ; Debrecin, Nenad ; Grgić, Davor ; Bajs, Tomislav ; Špalj, Srđan
    izvorni znanstveni rad, 2004.

    Three-Batch Reloading Scheme for IRIS Reactor Extended Cycles

    Pevec, Dubravko ; Ječmenica, Radomir ; Grgić, Davor
    izvorni znanstveni rad, 2004.

    The design and safety features of the IRIS reactor

    Carelli, Mario D. ; Conway, L.E. ; Oriani, L. ; Petrovic, Bojan ; Lombardi, C.V. ; Ricotti, M.E. ; Barroso, A.C.O. ; Collado, J.M. ; Cinotti, L. ; Todreas, N.E. ; Grgic, Davor ; Moraes, M.M. ; Boroughs, R.D. ; Ninokata, H. ; Ingersoll, D.T. ; Oriolo, F.
    stručni rad, 2004.
    Nuclear engineering and design

    Calculation of local thermal-hydraulic conditions for qualification of safety class electrical equipment

    Sučić, Boris
    magistarski rad (znanstveni), 2004.

    IRIS Small Break LOCA Phenomena Identification and Ranking Table (PIRT) Addendum 1 - IRIS Small Break LOCA Sensitivity Report for PIRT Development

    Grgić, Davor ; Oriani, L. ; Conway, L.E.
    elaborat/studija, 2004.

    Modeling of CHASHMA NPP Reactor Core Using FUMACS Computer Code Package

    Chughtai, M. Kamran ; Manan, Abdul ; Pevec, Dubravko ; Grgić, Davor
    izvorni znanstveni rad, 2004.

    Modeliranje gubitaka topline u industrijskim objektima s kontroliranom temperaturom okoline

    Bančak, Jasna
    diplomski rad (sveučilišni), 2004.

    Coupled RELAP5/GOTHIC Model for IRIS SBLOCA Analysis

    Grgić, Davor ; Čavlina, Nikola ; Bajs, Tomislav ; Oriani, L. ; Conway, L.E.
    izvorni znanstveni rad, 2004.

    Small Break Loss of Cooloant Accident Analysis for the International Reactor Innovative and Secure (IRIS)

    Oriani, L. ; Conway, L.E. ; Grgić, Davor
    izvorni znanstveni rad, 2004.

    Modelling of Chashma NPP Reactor Core Using FUMACS Computer Code Package

    Chughtai, M. Kamran ; Manan, Abdul ; Pevec, Dubravko ; Grgić, Davor
    stručni rad, 2004.

    IRIS RELAP 5 mod 3.3 Nodalization and Steady State Qualification

    Grgić, Davor ; Bajs, Tomislav ; Šegon, Velimir ;
    elaborat/studija, 2003.

    IRIS Core Criticality Calculations

    Ječmenica, Radomir ; Trontl, Krešimir ; Pevec, Dubravko ; Grgić, Davor
    izvorni znanstveni rad, 2003.

    Neutroničko modeliranje jezgre IRIS reaktora

    Pevec, Dubravko ; Petrović, Bojan ; Grgić, Davor ; Ječmenica, Radomir ; Trontl, Krešimir
    sažetak izlaganja sa skupa, 2003.

    Development of RELAP5 Nodalization for IRIS Non-LOCA Transient Analyses

    Bajs, Tomislav ; Grgić, Davor ; Šegon, Velimir ; Oriani, Luca ; Conway, Lawrence E. ;
    izvorni znanstveni rad, 2003.

    Three Mile Island Unit 1 Main Steam Line Break Three-Dimensional Neutronics-Thermal-Hydraulics Analysis

    D'Auria, Francesco ; Gago Moreno, Jose Luis ; Galassi, Giorgio Maria ; Grgić, Davor ; Spadoni, Antonio
    izvorni znanstveni rad, 2003.
    Nuclear technology

    Coupled RELAP5/GOTHIC Model for IRIS Reactor SBLOCA Analysis

    Grgić, Davor ; Bajs, Tomislav ; Oriani, Luca ; Conway, Lawrence E. ;
    izvorni znanstveni rad, 2003.

    The Design and Safety Features of the IRIS Reactor

    Carelli, M. D. ; , Conway, L. ; Oriani, L. ; Lombardi, C. ; Ricotti, M. ; Barroso, A. ; Collado, J. ; Cinotti, L. ; Moraes, M. ; Kozuch, J. ; Grgić, Davor ; Ninokata, H. ; Boroughs, R. ; Ingersoll, D. ; Oriolo, F. ;
    izvorni znanstveni rad, 2003.

    Overview of Computational Challenges in the Development of Evaluation Models for the IRIS Reactor

    Oriani, Luca ; Conway, Lawrence E. ; Grgić, Davor ; Bajs, Tomislav ; Ricotti, Marco E. ; Barroso, Antonio ;
    ostalo, 2003.

    LOCA Analysis of the IRIS Reactor

    Bajs, Tomislav ; Grgić, Davor ; Čavlina, Nikola
    stručni rad, 2003.

    Calculation of Core Design Benchmark 44 for IRIS Reactor Using Modified CORD-2 Code Package

    Pevec, Dubravko ; Grgić, Davor ; Ječmenica, Radomir
    izvorni znanstveni rad, 2002.

    Analysis of Environmental Conditions for NPP Krško DC Battery and Battery Charger Rooms Following SG Blowdown Processing System Line Break

    Grgić, Davor ; Špalj, Srđan ; Fancev, Tomislav
    izvorni znanstveni rad, 2002.

    Design Of A Four-Year Straight-Burn Core For The Generation-IV Iris Reactor

    Grgić, Davor ; Pevec, Dubravko ; Petrović, Bojan ; Carelli, Mario ; Padovani, Enrico ; Lombardi, Carlo ; Ganda, Francesco ; Milošević, Miodrag ; Greenspan, Ehud ; Vujić, Jasmina
    izvorni znanstveni rad, 2002.

    Upgrade Of The Fumacs Code Package

    Pevec, Dubravko ; Grgić, Davor ; Ječmenica, Radomir ; Trontl, Krešimir ; Gergeta, Kristijan
    stručni rad, 2002.

    Core Design Calculations of IRIS Reactor Using Modified CORD-2 Code Package

    Pevec, Dubravko ; Grgić, Davor ; Ječmenica, Radomir ; Petrović, Bojan
    izvorni znanstveni rad, 2002.

    Design of a Four-Year Straight-Burn Core for the Generation IV IRIS Reactor

    Grgić, Davor ; Pevec, Dubravko ; Petrović, Bojan ; Carelli, Mario D. ; Ganda, Francesco ; Padovani, Enrico ; Lombardi, Carlo ; Franceschini, Fausto ; Ambrosini, Walter ; Oriolo, Francesco ; Milošević, Miodrag ; Greespan, Ehud ; Vujić, Jasmina
    izvorni znanstveni rad, 2002.

    Design Of A Four-Year Straight-Burn Core For The Generation-IV Iris Reactor

    Grgić, Davor ; Pevec, Dubravko ; Petrović, Bojan ; Carelli, Mario ; Padovani, Enrico ; Lombardi, Carlo ; Ganda, Francesco ; Milošević, Miodrag ; Greenspan, Ehud ; Vujić, Jasmina
    izvorni znanstveni rad, 2002.

    Upgrade of the FUMACS Code Package

    Pevec, Dubravko ; Grgić, Davor ; Ječmenica, Radomir ; Trontl, Krešimir ; Gergeta, Kristijan ; Šmuc, Tomislav
    izvorni znanstveni rad, 2001.

    PROVJERE OSNOVNIH ELEKTRIČKIH I MEHANIČKIH SVOJSTAVA KOMPAKTIRANIH GLAVA DALEKOVODNIH STUPOVA

    UGLEŠIĆ, Ivo ; FANCEV, Tomislav ; GRGIĆ Davor
    stručni rad, 2001.

    Benchmark Performed by Different Coupled 3-D Neutronics Thermal-Hydraulic Codes

    D'Auria, Francesco ; Spadoni, A ; Gago, Jose Luis ; Grgić, Davor ; Galassi, Giorgio Maria
    izvorni znanstveni rad, 2001.

    Influence of Reactor Vessel Nodalizations in the Coupled Code Analysis of Asymmetric Main Feedwater Isolation

    Benčik, Vesna ; Feretić, Danilo ; Grgić, Davor
    stručni rad, 2001.

    Evaluation of a Multisource Option Introduced into QAD-CGGP Code

    Baće, Mile ; Trontl, Krešimir ; Grgić, Davor
    izvorni znanstveni rad, 2001.

    Metoda za analizu nesimetričnih kvarova u nuklearnim elektranama

    Grgić Davor
    doktorski rad, 2001.

    Evaluation Of A Multisource Option Introduced Into Qad-Cggp Code

    Baće, Mile ; Trontl, Krešimir ; Grgić, Davor ;
    izvorni znanstveni rad, 2001.

    Status of CAMP Activities in Croatia

    Bajs, Tomislav ; Debrecin, Nenad ; Grgić, Davor ; Špalj, Srđan ; Benčik, Vesna
    sažetak izlaganja sa skupa, 2001.

    THERMAL-HYDRAULIC MODELING OF RERACKED SPENT FUEL POOL

    Grgić, Davor ; Ječmenica, Radomir ; Pevec, Dubravko
    stručni rad, 2000.

    NPP KRSKO STEAM LINE BREAK ANALYSIS BY MEANS OF COUPLED CODE RELAP5-QUABOX/CUBBOX

    Bajs, Tomislav ; Grgić, Davor ; Špalj, Srđan
    stručni rad, 2000.

    CORE-WIDE DNBR CALCULATION FOR NPP KRŠKO MSLB

    Jurković, Ines-Ana ; Grgić, Davor ; Debrecin, Nenad
    stručni rad, 2000.

    VERIFICATION OF THE COUPLED CODE RELAP5-QUABOX/CUBBOX BY LARGE LOAD REJECTION ANALYSIS FOR NPP KRŠKO

    Benčik, Vesna ; Feretić, Danilo ; Grgić, Davor
    stručni rad, 2000.

    Thermal-Hydraulic Modeling of Reracked Spent Fuel Pool

    Grgić, Davor ; Ječmenica, Radomir ; Pevec, Dubravko
    izvorni znanstveni rad, 2000.

    Modernizacija paketa računalskih programa FUMACS

    Pevec, Dubravko ; Baće, Mile ; Ječmenica, Radomir ; Trontl, Krešimir ; Šmuc, Tomislav ; Grgić, Davor
    elaborat/studija, 2000.

    SLB Analysis of NPP Krško Using Coupled RELAP5/MOD3.2-QUABOX/CUBBOX CODE

    Bajs, Tomislav ; Grgić, Davor ; Špalj, Srđan
    stručni rad, 2000.

    ANALYSIS OF INADVERTENT CONTAINMENT SPRAY ACTUATION FOR NPP KRŠKO

    Grgić, Davor ; Špalj, Srđan ; Fancev, Tomislav
    stručni rad, 2000.

    NPP KRŠKO CONTAINMENT RESPONSE FOLLOWING MAIN STEAM LINE BREAK

    Špalj, Srđan ; Grgić, Davor ; Čavlina, Nikola
    stručni rad, 2000.

    ASSESSMENT OF THE MSLB ACCIDENT SAFETY MARGINS FOR NPP KRŠKO

    Bajs, Tomislav ; Grgić, Davor ; Špalj, Srđan
    stručni rad, 2000.

    APPLICATION OF THE COUPLED CODE RELAP5-QUABOX/CUBBOX IN BEST-ESTIMATE ANALYSES OF NUCLEAR POWER PLANTS

    Benčik, Vesna ; Grgić, Davor ; Feretić, Danilo
    stručni rad, 2000.

    Application of the coupled code RELAP5- QUABOX/CUBBOX in Best-Estimate Analyses of Nuclear Power Plants

    Benčik, Vesna ; Grgić, Davor ; Feretić, Danilo
    izvorni znanstveni rad, 2000.

    TMI-1 MSLB COUPLED 3-D NEUTRONICS/THERMALHYDRAULICS ANALYSIS: APPLICATION OF RELAP5-3D AND COMPARISON WITH DIFFERENT CODES

    D'Auria, F. ; Gago, J.L. ; Galassi, G.M. ; Grgić, Davor ; Spadoni, A.,
    izvještaj, 2000.

    DEVELOPMENT OF POWER REACTOR SAFETY ANALYSES COUPLED SYSTEM FOR PERSONAL COMPUTER ENVIRONMENT

    Pevec, Dubravko ; Grgić, Davor ; Špalj, Srđan ; Bajs, Tomislav ; Benčik, Vesna ; Ječmenica, Radomir
    izvještaj, 2000.

    DEVELOPMENT OF POWER REACTOR SAFETY ANALYSES COUPLED SYSTEM FOR PERSONAL COMPUTER ENVIRONMENT

    Pevec, Dubravko ; Grgić, Davor ; Špalj, Srđan ; Bajs, Tomislav ; Benčik, Vesna
    izvještaj, 1999.

    Croatian Experience in the Use of Coupled 3D Code With RELAP5

    Grgić, Davor ; Bajs, Tomislav
    sažetak izlaganja sa skupa, 1999.

    Role of the Exercises in the Training of the Technical Support Center Members in Croatia

    Jurković, Ines-Ana ; Grgić, Davor ; Škanata, Dejan
    stručni rad, 1999.

    RELAP5/mod3.2 - QUABOX/CUBBOX-HYCA Coupling

    Grgić, Davor ; Špalj, Srđan ; Bajs, Tomislav ; Čavlina, Nikola ; Pevec, Dubravko
    stručni rad, 1998.

    Kakvoća u izobrazbi i izobrazba o kakvoći u Hrvatskoj

    Marušić, Ante ; Grgić, Davor ; Šundrica, Jadran
    stručni rad, 1998.

    Proračun termohidrauličkih parametara bazena za istrošeno gorivo NE Krško uz pretpostavku gušćeg smještaja goriva i odgora istrošenog goriva

    Pevec, Dubravko ; Baće, Mile ; Grgić, Davor ; Ječmenica, Radomir ; Trontl, Krešimir
    elaborat/studija, 1998.

    RELAP5/mod2 Code for Win95/NT Environment with F90 Capabilities

    Grgić, Davor ; Čavlina, Nikola ; Špalj, Srđan ; Bajs, Tomislav
    izvorni znanstveni rad, 1997.

    RELAP5/MOD2 Code for Win95/NT Environment with F90 Capabilities

    Grgić, Davor ; Špalj, Srđan ; Prah, Matjaž
    sažetak izlaganja sa skupa, 1997.

    RELAP5/Mod3.2 - Quabox/Cubbox-Hyca Coupled Code

    Grgić, Davor ; Čavlina, Nikola ; Pevec, Dubravko ; Špalj, Srđan ; Bajs, Tomislav ; Langebuch, Siegfried ; Velkov, Kiril
    izvorni znanstveni rad, 1997.

    Plan i program postupaka za slučaj nesreće u NE Krško i NE Paks

    Strohal, Petar ; Lulić, Stjepan ; Franić, Zdenko ; Subašić, Damir ; Jurković, Ines-Ana ; Grgić, Davor ; Bajs, Tomislav ; Šinka, Davor
    elaborat/studija, 1997.

    Use of GOTHIC Code for Assessment of Equipment Environmental Qualification

    Čavlina, Nikola ; Feretić, Danilo ; Grgić, Davor ; Špalj, Srđan
    izvorni znanstveni rad, 1996.

    NISA FEM Support in Seismic Qualification of Small Class 1E Electric Motors

    Fancev, Tomislav ; Grgić, Davor ; Šaban, Ivka
    izvorni znanstveni rad, 1996.

    RELAP5/mod2 Analysis of Inadvertent Closing of the Main Steam Isolation Valve in NPP Krško

    Čavlina, Nikola ; Debrecin, Nenad ; Grgić, Davor ; Aralica, Marin
    izvorni znanstveni rad, 1996.

    Capability of the QUABOX/CUBBOX-ATHLET Coupled Code System

    Langenbuch, Siegfried ; Velkov, Kiril ; Pevec, Dubravko ; Grgić, Davor
    izvorni znanstveni rad, 1996.

    Concrete Spent Fuel Cask Criticality Calculation

    Božić, Helena ; Baće, Mile ; Grgić, Davor
    izvorni znanstveni rad, 1996.

    The Development of the Safety Related Valve Class 1E Electric Motor, the Target and the Results

    Šaban, Ivka ; Novosel, Nevenka ; Grgić, Davor ; Fancev, Tomislav ; Flegar, Ljerka
    izvorni znanstveni rad, 1996.

    Konceptualna studija privremenog odlagališta istrošenog goriva na lokaciji nuklearne elektrane

    Baće, Mile ; Grgić, Davor ; Knapp, Vladimir ; Pevec, Dubravko
    elaborat/studija, 1995.

    Transient Temperature Behaviour Of The MO Suger Arrester Aged By Repeated Application Of Current Impulses And Analyzed By Means Of Computer Aided Thermal Modelling

    Uglešić, Ivo ; Grgić, Davor ; Babuder Maks
    izvorni znanstveni rad, 1995.

    Modelling of Transient Temperature Fields in Structures with System Transfer Function

    Feretić, Danilo ; Čavlina, Nikola ; Grgić, Davor
    izvorni znanstveni rad, 1994.
    International journal for engineering modelling

    Procjena ekoloških posljedica zatvaranja NE Krško

    Feretić, Danilo ; Mikuličić, Vladimir ; Čavlina, Nikola ; Pevec, Dubravko ; Grgić, Davor ; Bajs, Tomislav ; Špalj, Srđan ; Šimić, Zdenko
    elaborat/studija, 1992.

    Investigation of intermediate conversion pressurized water reactor for small or medioum nuclear systems

    Knapp, Vladimir ; Pevec, Dubravko ; Grgić, Davor
    izvorni znanstveni rad, 1992.

    Razmatranje mogućnosti suhog skladištenja istrošenog goriva na lokaciji NE

    Baće, Mile ; Grgić, Davor ; Knapp, Vladimir ; Pevec, Dubravko
    stručni rad, 1991.

    Analiza, provjera i proračun štitova za odlaganje radioaktivnog otpada

    Baće, Mile ; Grgić, Davor ; Jakopec, S. ; Knapp, Vladimir ; Kulišić, Petar ; Petković, Tomislav ; Pevec, Dubravko ; Šmuc, Tomislav
    elaborat/studija, 1989.

    Modeliranje prelazne pojave nekontroliranog smanjenja koncentracije borne kiseline za NE Krško

    Baće, Mile ; Grgić, Davor ; Jurčević, Marijan ; Knapp, Vladimir ; Pevec, Dubravko ; Prokopec, Tomislav
    izvorni znanstveni rad, 1988.

    Analiza prijelazne pojave nekontroliranog smanjenja koncentracije borne kiseline

    Baće, Mile ; Grgić, Davor ; Jurčević, Marijam ; Knapp, Vladimir ; Pevec, Dubravko ; Prokopec, Tomislav
    elaborat/studija, 1987.

    A case study of the effect of advanced fuel cycles and improvements in PWR and PHWR reactors on the resource requirements within small or medium nuclear power programme

    Knapp, Vladimir ; Grgić, Davor ; Pevec, Dubravko ; Popović, I. ; Vojvodić, Ratko
    izvještaj, 1986.

    IAEA Coordinated research programme on requirements for application of advanced reactors, Second annual progress report

    Knapp, Vladimir ; Grgić, Davor ; Pevec, Dubravko ; Popović, Ignac ; Vojvodić, Ratko
    izvještaj, 1986.

    Analiza prijelaznih pojava brzog povećanja reaktivnosti

    Baće, Mile ; Grgić, Davor ; Jurčević, Marijan ; Knapp, Vladimir ; Krčmar, Milica ; Macek, Mario ; Pevec, Dubravko ; Pisk, Krunoslav
    elaborat/studija, 1986.

    IAEA Coordinated research programme on requirements for future application of advanced reactors, Progress Report, September 1985

    Knapp, Vladimir ; Grgić, Davor ; Kulišić, Petar ; Pevec, Dubravko ; Popović, Ignac ; Vojvodić, Ratko
    izvještaj, 1985.

    Analiza prijelazne pojave nekontroliranog izvlačenja banke kontrolnih štapova PWR reaktora pri punoj snazi

    Baće, Mile ; Grgić, Davor ; Jurčević, Marijan ; Knapp, Vladimir ; Krčmar, Milica ; Pevec, Dubravko ; Pisk, Kruno
    izvorni znanstveni rad, 1985.

    Analiza prijelaznih pojava nekontroliranog izvlačenja banke kontrolnih štapova na punoj snazi i izbacivanja snopa kontrolnih štapova

    Baće, Mile ; Grgić, Davor ; Jurčević, Marijan ; Knapp, Vladimir ; Krčmar, Milica ; Pevec, Dubravko ; Pisk, Krunoslav
    elaborat/studija, 1984.

    Nastava

    Sveučilišni preddiplomski

    Kompetencije

    • Nuclear and plasma sciences
      Accelerator magnets Radiation effects Biological effects of radiation Gamma-ray effects Ion radiation effects Neutron radiation effects Total ionizing dose Radiation monitoring Radiation dosage Radiation safety Radiation protection Reactor instrumentation
    • Industry applications
      Electrical accidents Industrial accidents Fuel cells Heat engines Pollution control Renewable energy sources Nuclear facility regulation Conductors Fires Flammability Hazardous materials Health and safety Radiation protection Radiation safety
    • Instrumentation and measurement
      Electromagnetic modeling Nuclear measurements Radiation monitoring
    • Materials, elements, and compounds
      Radioactive materials Nuclear fuels Radioactive decay Radioactive waste
    • Power engineering and energy
      Fuel cells Energy efficiency Geothermal energy Nuclear fuels Solar energy Wind energy Energy storage Geothermal power generation Hydroelectric power generation Nuclear power generation Fission reactors Wind power generation Power system reliability

    Osobni podaci

    Godina diplomiranja:
    1981.
    Godina magistriranja:
    1989.
    Godina doktoriranja:
    2001.
    Na zavodu od:
    1990.