izv. prof. dr. sc. Siniša Šadek

Associate professor, Department of Energy and Power Systems

Location:
Public phone number:
6129-985
Internal phone number:
485

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

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.

Graduate Geothermal training in the European Economic Area

Newson, Juliet ; Trullenque, Ghislain ; Bossennec, Claire ; Sass, Ingo ; Šadek, Siniša ; Gautason, B. ; Greene, R. Morgan
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.

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

Šadek, Siniša ; Pavlinac, Renato ; Ivanjko, Karlo ; Grgić, Davor
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)

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.

Thermal calculation of the lower plenum of a reactor vessel

Ilievski, Ivan
2020.

Calculation of thermo-hydraulic conditions inside containment of a nuclear power plant

Mileta, Kristina
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)

Modelling of fuel in the nuclear reactor using the ANSYS code

Vidić, Igor
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)

Reactor Vessel Modelling with the MELCOR Code

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

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

Šadek, Siniša ; Grgić, Davor
2019.

Overview of techno-economic issues of enhanced geothermal systems implementation and integration

Bilić, Tena ; Rajšl, Ivan ; Ilak, Perica ; Raos, Sara ; Šadek, Siniša ; Krajcar, Slavko ; Debrecin, Nenad ; Genter, Albert ; Leoutre, Eric
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.

Effectiveness of SFP Spray Cooling during Loss of Coolant Accidents

Vlahović, Štefica ; Grgić, Davor ; Đaković, Josip ; 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.

Comparison of Measured and Calculated Data for NPP Krško CILR Test

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

Fuel Handling Building Response to SFP Loss of Cooling

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

Proceedings of the 12th International Conference of the Croatian Nuclear Society


2018.

Influence of Detailed PCFV Model on Containment Behaviour During SBO

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

Economic and environmental assessment for enhanced geothermal systems integration into energy systems Decision-making support tool for optimal usage of geothermal energy

Ilak, Perica ; Raos, Sara ; Rajšl, Ivan ; Trullenque, Ghislain ; Bilić, Tena ; Šadek, Siniša ; Marušić, Ante
2018.

Mathematical model of the NPP Krško PCFV system for the RELAP5 computer code

Pošta, Borna ; Šadek, Siniša
2017.
Energija : časopis Hrvatske elektroprivrede

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

Operation and Performance Analysis of Steam Generators in Nuclear Power Plants

Šadek, Siniša ; Grgić, Davor
2017.

Calculation of NEK CILR Test Using GOTHIC Code

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

Verification of GOTHIC Multivolume Containment Model during NPP Krško DBA LOCA

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

NPP Krško Station Blackout Analysis after Safety Upgrade Using MELCOR Code

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

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.

Calculation of Hydrogen Concentration in Containment during LOCA Accident

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

NPP Krško Containment Modelling and Calculation with the ASTEC Code

Šadek, Siniša
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.

Spatial Distribution of Hydrogen in NEK Containment

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

Hot Leg Streaming Calculation for Two-Loop PWR Plant

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

Optimization of OPDT Protection for Overcooling Accidents

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

ASTEC Computer Code Application to NPP Krško

Šadek, Siniša
2013.

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

Coupled code calculation of rod withdrawal at power accident

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

Severe Accident Analysis in the NPP Krško with the ASTEC Code

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

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

Coupled Code Calculation of Rod Withdrawal at Power Accident

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

Calculational Model for In-Vessel Phase of Severe Accidents in Nuclear Power Plant

Šadek, Siniša
2010.

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

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

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

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

Influence of Modelling Options in RELAP5/SCDAPSIM and MAAP4 Computer Codes on Core Melt Progression and Reactor Pressure Vessel Integrity

Šadek, Siniša ; Špalj, Srđan ; Glaser, Bruno
2010.
Science and technology of nuclear installations

RELAP5 Modeling of PWR Reactor RTD Bypass

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

Analysis of In-Vessel Severe Accident Phenomena in NPP Krško

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

QUENCH-11 Experiment Analysis with RELAP5/SCDAPSIM Code

Šadek, Siniša ; Debrecin, Nenad ; Špalj, Srđan
2008.

Influence of Modelling Options in RELAP5/SCDAPSIM and MAAP4 Computer Codes on Core Melt Progression and Reactor Pressure Vessel Integrity

Šadek, Siniša ; Špalj, Srđan ; Glaser, Bruno
2008.

Benchmark Exercise on QUENCH-11 Experiment

Stefanova, A. ; Groudev, P. ; Sepold, L. ; Steinbrück, M. ; Stuckert, J. ; Hering, W. ; Homann, Ch. ; Guillard, G. ; Duspiva, J. ; Erdmann, W. ; Hollands, T. ; Drath, T. ; Negut, G. ; Vasiliev, A. ; Šadek, Siniša
2007.

Analysis of Small Break LOCA During Mode 3 and Mode 4 Operation for NPP Krško

Šadek, Siniša ; Špalj, Srđan ; Bajs, Tomislav
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
2006.

Core Degradation and Hydrogen Production During a Severe Accident

Šadek, Siniša ; Rašeta, Davor ; Keco, Mario
2006.

RCP Seal Leakage Analysis During Station Blackout for NPP Krško

Šadek, Siniša ; Špalj, Srđan ; Čavlina, Nikola
2005.

Analysis of Phebus FPT1 Experiment with RELAP5/SCDAPSIM Computer Code

Šadek, Siniša
2004.

Analysis of SBO Accident in NPP Krško using RELAP5/SCDAPSIM/MOD3.2

Šadek, Siniša ; Špalj, Srđan ; Debrecin, Nenad
2004.

Evaluation of the Safety Margins during Shutdown for NPP Krško

Benčik, Vesna ; Šadek, Siniša ; Bajs, Tomislav
2004.

ISP-46 Analysis with RELAP/SCDAPSIM Computer Code

Šadek, Siniša ; Špalj, Srđan ; Debrecin, Nenad
2003.

RELAP5/SCDAPSIM Analysis of the QUENCH-06 Experiment

Šadek, Siniša
2003.

QUENCH-06 RELAP5/SCDAPSIM Nodalization Notebook

Šadek, Siniša
2003.

Applicability Of Relap5/Scdapsim Code For Thermal-Hydraulic Analysis of Pakistan Research Reactor 1

Mahmood, T. ; Šadek, Siniša
2002.

Analysis of International Standard Problem ISP-45 on QUENCH Facility Using RELAP5/SCDAPSIM/MOD3.2 Computer Code

Špalj, Srđan ; Šadek, Siniša ; Honaiser, Eduardo
2002.

Teaching

University undergraduate

University graduate

Postgraduate doctoral study programme

Competences

  • Engineering – general
    Thermal engineering
  • Reliability
    Availability Reliability theory
  • Science – general
    Thermodynamics
  • Control systems
    Heating systems Thermal analysis
  • Industry applications
    Industrial accidents Heat engines Steam engines Renewable energy sources Sustainable development Radiation safety
  • Materials, elements, and compounds
    Fluid dynamics Radioactive materials Nuclear fuels Radioactive decay
  • Power engineering and energy
    Energy consumption Energy conversion Photovoltaic cells Energy resources Nuclear fuels Solar energy Geothermal power generation Nuclear power generation Solar power generation Power system reliability