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Davor Grgic
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Journal Articles

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

Davor Grgic, Paulina Duckic, Vesna Bencik, Sinisa Sadek
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2024, 10(1): 011701.
Paper No: NERS-23-1019
https://doi.org/10.1115/1.4062797
Published Online: October 20, 2023
View Article titled, Dose Rate Assessment Around the PCFV Release Line During Severe Accident Conditions in Nuclear Power Plant Krsko
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Topics: Accidents, Containment, Ducts, Nuclear power stations, Fluids
Journal Articles

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

Siniša Šadek, Renato Pavlinac, Karlo Ivanjko, Davor Grgić
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2024, 10(1): 011301.
Paper No: NERS-23-1016
https://doi.org/10.1115/1.4062799
Published Online: October 20, 2023
View Article titled, Uncertainty and Sensitivity Evaluation of the QUENCH-02 Experiment Simulation Using the ASYST Code
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Topics: Cladding systems (Building), Electricity (Physics), Flow (Dynamics), Hydrogen, Oxidation, Steam, Temperature, Uncertainty, Water, Boundary-value problems
Journal Articles

Analysis of the HI-TRAC VW Transfer Cask Dose Rates for Spent Fuel Assemblies Loaded in Nuclear Power Plant Krsko Storage Campaign One

Davor Grgić, Mario Matijević, Paulina Dučkić, Radomir Ječmenica
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041902.
Paper No: NERS-21-1029
https://doi.org/10.1115/1.4051447
Published Online: March 16, 2022
View Article titled, Analysis of the HI-TRAC VW Transfer Cask Dose Rates for Spent Fuel Assemblies Loaded in Nuclear Power Plant Krsko Storage Campaign One
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Topics: Accidents, Fuels, Hardware, Neutrons, Nuclear power stations, Particulate matter, Spent nuclear fuels, Storage, Uncertainty, Manufacturing
Journal Articles

Application of Fractional Scaling Analysis for Development and Design of Integral Effects Test Facility

Milorad B. Dzodzo, Francesco Oriolo, Walter Ambrosini, Marco Ricotti, Davor Grgic, Roberta Ferri, Andrea Achilli, Fosco Bianchi, Paride Meloni
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2019, 5(4): 041208.
Paper No: NERS-18-1027
https://doi.org/10.1115/1.4042496
Published Online: September 3, 2019
View Article titled, Application of Fractional Scaling Analysis for Development and Design of Integral Effects Test Facility
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Topics: Containment vessels, Engineering prototypes, Pressure, Reactor vessels, Test facilities, Transients (Dynamics), Water, Design, Heat, Containment
Proceedings Papers

Xenon Correction in Homogenized Neutron Cross Sections

Davor Grgić, Radomir Ječmenica, Dubravko Pevec
Proc. ASME. ICONE20-POWER2012, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle, and Balance of Plant; Component Reliability and Materials Issues; Steam Generator Technology Applications and Innovations; Advanced Reactors and Near-Term Deployment; Reactor Physics, Neutronics, and Transport Theory; Nuclear Education, Human Resources, and Public Acceptance, 767-775, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54878
https://doi.org/10.1115/ICONE20-POWER2012-54878
View Paper titled, Xenon Correction in Homogenized Neutron Cross Sections
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Topics: Cross section (Physics), Neutrons, Pressurized water reactors, Absorption, Boron, Fuels, Nuclear fission, Nuclear power stations
Proceedings Papers

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

Tomislav Bajs, Alessandro Petruzzi, Davor Grgić
Proc. ASME. ICONE20-POWER2012, Volume 3: Thermal-Hydraulics; Turbines, Generators, and Auxiliaries, 665-672, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-55011
https://doi.org/10.1115/ICONE20-POWER2012-55011
View Paper titled, Uncertainty Evaluation of the Rod Withdrawal at Power Accident Analysis Including 3D Neutron Kinetics
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Topics: Accidents, Neutrons, Uncertainty, Coolants, Nucleate boiling, Temperature, Temperature measurement, Delays, Fuels, Heat flux
Proceedings Papers

The SPES3 Facility for Testing an Integral Layout SMR: BDBE Simulation Analysis

Roberta Ferri, Andrea Achilli, Cinzia Congiu, Gustavo Cattadori, Fosco Bianchi, Paride Meloni, Stefano Monti, Alfredo Luce, Marco Enrico Ricotti, Davide Papini, Davor Grgic´
Proc. ASME. SMR2011, ASME 2011 Small Modular Reactors Symposium, 269-278, September 28–30, 2011
Publisher: American Society of Mechanical Engineers
Paper No: SMR2011-6614
https://doi.org/10.1115/SMR2011-6614
View Paper titled, The SPES3 Facility for Testing an Integral Layout SMR: BDBE Simulation Analysis
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Topics: Accidents, Condensers (steam plant), Containment, Containment systems, Coolants, Design, Engineering simulation, Feedback, Fluids, Nuclear fission