prof. dr. sc. Davor Grgić

Full professor, Department of Energy and Power Systems

Location:
Public phone number:
6129-994
Internal phone number:
494

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

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

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
2024.
Journal of nuclear engineering and radiation science

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

Benčik, Vesna; Grgić, Davor; Šadek, Siniša
2023.

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

Ječmenica, Radomir; Grgić, Davor; Dučkić, Paulina
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
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
2023.

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

Grgić, Davor; Dučkić, Paulina; Strmečki, Petra; Milobar, Juraj
2022.

Influence of reactivity feedback modelling in RELAP5 NEK LONF ATWS calculation

Grgić, Davor; Benčik, Vesna; Šadek, Siniša; Dučkić, Paulina
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
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
2022.
Energies (Basel)

Radiation shielding analysis of the HI-STORM FW storage cask

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

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

Benčik, Vesna ; Grgić, Davor ; Šadek, Siniša
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
2022.

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

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

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

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

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

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

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

Šadek, Siniša ; Grgić, Davor ; Allison, Chris
2021.

NPP Krško Large Break Loss of Coolant Accident using MELCOR Code

Benčik, Vesna ; Grgić, Davor ; Šadek, Siniša
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
2021.
Journal of nuclear engineering and radiation science

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
2020.

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

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

Room Classification Based on EMC Conditions in Nuclear Power Plants

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

Hazard Assessment of NPP Krško for Republic of Croatia

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

ENERGY TRANSITION TOWARDS ENERGY TRANSFORMATION

Tomšić, Željko ; Krajcar, Slavko ; Kuzle, Igor ; Grgić, Davor
2019.

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

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

Evaluation of the NEK SFDS Cask Model Using Hybrid Shielding Methodology

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

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

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

Dose Calculation for Emergency Control Room HVAC Filter

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

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

Šadek, Siniša ; Grgić, Davor
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
2019.
Journal of nuclear engineering and radiation science

Point Kernel Modification Including Support Vector Regression Neutron Buildup Factor Models

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

Reactor Vessel Modelling with the MELCOR Code

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

Comparison of Measured and Calculated Data for NPP Krško CILR Test

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

Effectiveness of SFP Spray Cooling during Loss of Coolant Accidents

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

Comparison of Measured and Calculated Data for NPP Krško CILR Test

Vlahović, Štefica ; Grgić, Davor ; Šadek, Siniša ; Fancev, Tomislav ; Benčik, Vesna
2018.

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

Grgić, Davor ; Ječmenica, Radomir ; Vlahović, Štefica ; Šadek, Siniša ; Bašić, Ivica
2018.

NPP Krsko IB Modelling with GOTHIC and MELCOR Codes

Grgić, Davor ; Vlahović, Štefica ; Fancev, Tomislav ; Šadek, Siniša ; Benčik, Vesna
2018.

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

Ječmenica, Radomir ; Grgić, Davor ; Matijević, Mario
2018.

Hybrid Shielding Methods Validation Using Graphite Shielding Measurements

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

Point Kernel Modification Including Support Vector Regression Neutron Buildup Factor Models

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

Influence of Detailed PCFV Model on Containment Behaviour During SBO

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

Dose Calculation for Emergency Control Room HVAC Filter

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

Fuel Handling Building Response to SFP Loss of Cooling

Grgić, Davor ; Fancev, Tomislav ; Šadek, Siniša ; Špalj, Srđan
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
2018.

Calculation of Radioactive Inventory for Severe Accident and Consequence Codes

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

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
2017.

Radioactive Inventory Data for Severe Accident and Consequence Calculation Codes

Grgić, Davor ; Ječmenica, Radomir ; Vlahović, Štefica ; Bašić, Ivica
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
2017.
Science and technology of nuclear installations

Analysis of Spent Fuel Pool Loss of Coolant Inventory Accident Progression

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

Calculation of NEK CILR Test Using GOTHIC Code

Grgić, Davor ; Šadek, Siniša ; Fancev, Tomislav ; Benčik, Vesna
2017.

Operation and Performance Analysis of Steam Generators in Nuclear Power Plants

Šadek, Siniša ; Grgić, Davor
2017.

Verification of GOTHIC Multivolume Containment Model during NPP Krško DBA LOCA

Fancev, Tomislav ; Grgić, Davor ; Šadek, Siniša
2016.

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

Dučkić, Paulina ; Matijević, Mario ; Grgić, Davor
2016.

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

Pavić, Matea ; Grgić, Davor ; Tomšić, Željko
2016.

NPP Krško Station Blackout Analysis after Safety Upgrade Using MELCOR Code

Šadek, Siniša ; Grgić, Davor ; Benčik, Vesna
2016.

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

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

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

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

NPP Krško Post-UFC Transient Response during MSLB

Vlahović, Štefica ; Grgić, Davor ; Benčik, Vesna
2016.

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

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

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


2016.

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

Matijević, Mario ; Ječmenica, Radomir ; Grgić, Davor
2016.

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

Matijević, Mario ; Grgić, Davor ; Pevec, Dubravko
2015.

Environmental Consequences of Radioactive Gas Effluent Release from Nuclear Power Plants

Filipović, Matea
2015.

Independent Review of NPP Modifications and Safety Upgrades

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

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
2015.

Hot Leg Streaming Calculation for Two-Loop PWR Plant

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

Development of NPP Krško Primary Loop Model for TRACE code

Dučkić, Paulina
2014.

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

Ječmenica, Radomir ; Matijević, Mario ; Grgić, Davor
2014.

Optimization of OPDT Protection for Overcooling Accidents

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

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

Vuković, Josip ; Konjarek, Damir ; Grgić, Davor
2014.

Spatial Distribution of Hydrogen in NEK Containment

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

NPP Krško Containment Modelling with the ASTEC Code

Šadek, Siniša ; Grgić, Davor
2014.

Decay Heat Calculation for Spent Fuel Pool Application

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

Calculation of Hydrogen Concentration in Containment during LOCA Accident

Grgić, Davor ; Fancev, Tomislav ; Šadek, Siniša
2014.

Coupled code calculation of rod withdrawal at power accident

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

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

Šadek, Siniša ; Grgić, Davor ; Debrecin, Nenad
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
2013.
Atw-internationale zeitschrift fur kernenergie

Severe Accident Analysis in the NPP Krško with the ASTEC Code

Šadek, Siniša ; Amižić, Milan ; Grgić, Davor
2013.

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

Gros, Emilien ; Petrović, Bojan ; Grgić, Davor
2012.

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

Bajs, Tomislav ; Petruzzi, Alessandro ; Grgić, Davor
2012.

Xenon Correction in Homogenized Neutron Cross Sections

Grgić, Davor ; Ječmenica, Radomir ; Pevec, Dubravko
2012.

Lattice Codes Pin Power Prediction Comparison

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

Prediction of Local Hydrogen Concentrations in PWR Containment Using GOTHIC Code

Grgić, Davor ; Šimić, Zdenko ; Glaser, Bruno
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
2012.
Science and technology of nuclear installations

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
2012.

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

Benčik, Vesna ; Grgić, Davor ; Čavlina, Nikola
2012.

Physical conditioning programme of the top junior tennis player during preparation period

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

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

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

Coupled Code Calculation of Rod Withdrawal at Power Accident

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

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

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

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
2011.

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

Grgić, Davor ; Benčik, Vesna ; Šadek, Siniša
2010.

Upgrade of the FUMACS 2005 Code Package

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

RELAP5 Modeling of PWR Reactor RTD Bypass

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

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

Vuković, Josip ; Grgić, Davor ; Konjarek, Damir
2010.

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

Šadek, Siniša ; Grgić, Davor ; Debrecin, Nenad
2010.

Spectral Codes Pin Power Prediction Comparison

Grgić, Davor ; Ječmenica, Radomir ; Pevec, Dubravko
2010.

Prediction Capabilities of Spectral Codes DRAGON, FA2D, NEWT

Ječmenica, Radomir ; Grgić, Davor ; Pevec, Dubravko
2010.

Condensation within Small Compartments during Design Basis Accidents

Grgić, Davor ; Čavlina, Nikola ; Antolovič, Aleksandra
2010.

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
2009.

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
2009.

NA

Iveković, Ilijana
2009.

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

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

Verification of FA2D Prediction Capability Using Fuel Assembly Benchmark

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

Modelling of Condensation in Vertical Tubes for Passive Safety Systems

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

Analysis of In-Vessel Severe Accident Phenomena in NPP Krško

Šadek, Siniša ; Grgić, Davor ; Čavlina, Nikola
2008.

Influence of NPP Krško Core Nuclear Characteristics on RCCA Ejection Accident

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

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

Feretić, Danilo ; Čavlina, Nikola ; Grgić, Davor
2008.
Kerntechnik

Influence of Thermal-Hydraulic Model to Fuel Management Core Calculation

Iveković, Ilijana ; Grgić, Davor ; Nemec, Tomaž
2008.

High voltage overhead lines and application of the ordinance for protection from electromagnetic fields

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

NPP Krško Core Calculations to Improve Operational Safety

Iveković, Ilijana ; Grgić, Davor ; Nemec, Tomaž
2007.

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

Feretić, Danilo ; Grgić Davor
2007.
Kerntechnik

Neutronic model development for calculus of a PWR reflector

Matijević, Mario
2007.

Sensitivity analysis of control assembly ejection accident on NPP Krško core nuclear characteristics

Vuković, Josip
2007.

IRIS – Progress in Licensing and Toward Deployment

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

Possible Role of Advanced Nuclear Reactor IRIS in Croatian Power System

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

Preparation of NPP Krško input data for program TRACE

Konjarek, Damir
2006.

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
2006.

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

Bašić, Ivica ; Grgić, Davor
2006.

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

Grgić, Davor ; Špalj, Srđan ; Bajs, Tomislav
2006.

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

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

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

Iveković, Ilijana ; Čavlina, Nikola ; Grgić, Davor
2006.

IRIS - Advanced Medium Power Nuclear Reactor with Improved Safety and Economy

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

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

Feretić, Danilo ; Čavlina, Nikola ; Grgić, Davor
2005.
Kerntechnik

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

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

IRIS - advanced medium power nuclear reactor with advanced security and econimics

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

IRIS - Advanced Integral Nuclear Reactor with Modular Construction

Čavlina, Nikola ; Grgić, Davor ; Pevec, Dubravko ; Carelli, Mario ; Petrović, Bojan
2005.
Energija : časopis Hrvatske elektroprivrede

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.
2005.

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

Bašić, Ivica ; Grgić, Davor
2005.

IRIS – ADVANCED MEDIUM POWER NUCLEAR REACTOR WITH IMPROVED SAFETY AND ECONOMY

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

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

Keco, Mario ; Debrecin, Nenad ; Grgić, Davor
2005.

Coupled RELAP5/GOTHIC Model for IRIS SBLOCA Analysis

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

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

Sučić, Boris
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.
2004.
Nuclear engineering and design

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

Oriani, L. ; Conway, L.E. ; Grgić, Davor
2004.

Modeling of CHASHMA NPP Reactor Core Using FUMACS Computer Code Package

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

Modelling of Chashma NPP Reactor Core Using FUMACS Computer Code Package

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

Modelling of thermal energy losses in industrial facilities with controlled environmental temperature

Bančak, Jasna
2004.

Three-Batch Reloading Scheme for IRIS Reactor Extended Cycles

Pevec, Dubravko ; Ječmenica, Radomir ; Grgić, Davor
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
2004.

Radiation Dose Specification for Equipment Qulaification

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

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. ;
2003.

Development of RELAP5 Nodalization for IRIS Non-LOCA Transient Analyses

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

IRIS RELAP 5 mod 3.3 Nodalization and Steady State Qualification

Grgić, Davor ; Bajs, Tomislav ; Šegon, Velimir ;
2003.

LOCA Analysis of the IRIS Reactor

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

Coupled RELAP5/GOTHIC Model for IRIS Reactor SBLOCA Analysis

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

IRIS Core Criticality Calculations

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

IRIS Core Neutronics Modeling

Pevec, Dubravko ; Petrović, Bojan ; Grgić, Davor ; Ječmenica, Radomir ; Trontl, Krešimir
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
2003.
Nuclear technology

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
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
2002.

Upgrade Of The Fumacs Code Package

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

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

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

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

Pevec, Dubravko ; Grgić, Davor ; Ječmenica, Radomir
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
2002.

Method for Analysis of Asymmetric Accidents in Nuclear Power Plants

Grgić Davor
2001.

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

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

Upgrade of the FUMACS Code Package

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

Status of CAMP Activities in Croatia

Bajs, Tomislav ; Debrecin, Nenad ; Grgić, Davor ; Špalj, Srđan ; Benčik, Vesna
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
2001.

Evaluation Of A Multisource Option Introduced Into Qad-Cggp Code

Baće, Mile ; Trontl, Krešimir ; Grgić, Davor ;
2001.

VERIFICATIONS OF ELECTRICAL AND MECHANICAL PROPERTIES FOR COMPACT TRANSMISSION LINE TOWER HEAD DESIGN

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

Evaluation of a Multisource Option Introduced into QAD-CGGP Code

Baće, Mile ; Trontl, Krešimir ; Grgić, Davor
2001.

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

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

ASSESSMENT OF THE MSLB ACCIDENT SAFETY MARGINS FOR NPP KRŠKO

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

Thermal-Hydraulic Modeling of Reracked Spent Fuel Pool

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

NPP KRŠKO CONTAINMENT RESPONSE FOLLOWING MAIN STEAM LINE BREAK

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

ANALYSIS OF INADVERTENT CONTAINMENT SPRAY ACTUATION FOR NPP KRŠKO

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

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

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

CORE-WIDE DNBR CALCULATION FOR NPP KRŠKO MSLB

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

THERMAL-HYDRAULIC MODELING OF RERACKED SPENT FUEL POOL

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

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

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

Modernization of the FUMACS code package

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

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

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

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

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

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

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

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

Grgić, Davor ; Bajs, Tomislav
1999.

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

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

Calculation of thermohydraulic parameters of the spent fuel pool of the NPP Krško with the assumption of denser fuel storage and spent fuel burnup

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

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

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

Quality of Education and Education of Quality in Croatia

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

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

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

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

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

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

Grgić, Davor ; Špalj, Srđan ; Prah, Matjaž
1997.

Nije dostupan

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

Concrete Spent Fuel Cask Criticality Calculation

Božić, Helena ; Baće, Mile ; Grgić, Davor
1996.

Capability of the QUABOX/CUBBOX-ATHLET Coupled Code System

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

Use of GOTHIC Code for Assessment of Equipment Environmental Qualification

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

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

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

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

Fancev, Tomislav ; Grgić, Davor ; Šaban, Ivka
1996.

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
1995.

Conceptual study of the spent fuel intermediate storage on the NPP site

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

Modelling of Transient Temperature Fields in Structures with System Transfer Function

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

Evaluation of ecological consequences of closing NP Krško

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

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

Knapp, Vladimir ; Pevec, Dubravko ; Grgić, Davor
1992.

A study of spent fuel storage at the nuclear power plant site

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

Analysis, calculation and testing of shielding for radioactive waste deposition

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

Modelling transient from uncontrolled reduction of boric acid concentration for NPS Krško

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

Analysis of the transient caused by uncontrolled reduction of boric acid concentration

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

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
1986.

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
1986.

Analysis of transients caused by fast reactivity increase

Baće, Mile ; Grgić, Davor ; Jurčević, Marijan ; Knapp, Vladimir ; Krčmar, Milica ; Macek, Mario ; Pevec, Dubravko ; Pisk, Krunoslav
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
1985.

Analysis of a transient resulting from uncontrolled withdrawal of a group of control rods of PWR reactor at full power

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

Analysis of transients following uncontrolled retraction of the bank of control rods and ejection of a group of control rods

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

Teaching

University undergraduate

University graduate

Postgraduate doctoral study programme

Competences

  • 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

Personal data

Graduation year:
1981.
mr.sc. graduation year:
1989.
PhD graduation year:
2001.
Employed in this institution since:
1990.