doc. dr. sc. Siniša Šadek

Assistant professor, Department of Energy and Power Systems

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

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

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

Šadek, Siniša ; Grgić, Davor
2019.

Reactor Vessel Modelling with the MELCOR Code

Šadek, Siniša ; Grgić, Davor ; Vuković, Franjo ; Benčik, Vesna
2019.
International Conference Nuclear Energy for New Europe 2019

Comparison of Measured and Calculated Data for NPP Krško CILR Test

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

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.
11th Mediterranean Conference on Power Generation, Transmission, Distribution and Energy Conversion

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.
11th Mediterranean Conference on Power Generation, Transmission, Distribution and Energy Conversion

Comparison of Measured and Calculated Data for NPP Krško CILR Test

Vlahović, Štefica ; Grgić, Davor ; Šadek, Siniša ; Fancev, Tomislav ; Benčik, Vesna
2018.
MEDPOWER2018 - Mediterranean Conference on Power Generation, Transmission, distribution and Energy Conversion

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

Grgić, Davor ; Ječmenica, Radomir ; Vlahović, Štefica ; Šadek, Siniša ; Bašić, Ivica
2018.
27th International Conference Nuclear Energy for New Europe NENE2018

NPP Krsko IB Modelling with GOTHIC and MELCOR Codes

Grgić, Davor ; Vlahović, Štefica ; Fancev, Tomislav ; Šadek, Siniša ; Benčik, Vesna
2018.
27th International Conference Nuclear Energy for New Europe NENE2018

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


2018.

Effectiveness of SFP Spray Cooling during Loss of Coolant Accidents

Vlahović, Štefica ; Grgić, Davor ; Đaković, Josip ; Šadek, Siniša ; Bašić, Ivica
2018.
12th International Conference of the Croatian Nuclear Society

Influence of Detailed PCFV Model on Containment Behaviour During SBO

Šadek, Siniša ; Grgić, Davor ; Benčik, Vesna ; Mileta, Kristina ; Špalj, Srđan
2018.
12th International Conference of the Croatian Nuclear Society

Fuel Handling Building Response to SFP Loss of Cooling

Grgić, Davor ; Fancev, Tomislav ; Šadek, Siniša ; Špalj, Srđan
2018.
12th International Conference of the Croatian Nuclear Society

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.
12th International Conference of the Croatian Nuclear Society

Calculation of NEK CILR Test Using GOTHIC Code

Grgić, Davor ; Šadek, Siniša ; Fancev, Tomislav ; Benčik, Vesna
2017.
26th International Conference Nuclear Energy for New Europe NENE2017

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

Pošta, Borna ; Šadek, Siniša
2017.
Journal of Energy

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.

Verification of GOTHIC Multivolume Containment Model during NPP Krško DBA LOCA

Fancev, Tomislav ; Grgić, Davor ; Šadek, Siniša
2016.
11th International Conference of the Croatian Nuclear Society

NPP Krško Station Blackout Analysis after Safety Upgrade Using MELCOR Code

Šadek, Siniša ; Grgić, Davor ; Benčik, Vesna
2016.
11th International Conference of the Croatian Nuclear Society

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.
International Conference Nuclear Energy for New Europe 2015

Independent Review of NPP Modifications and Safety Upgrades

Grgić, Davor ; Benčik, Vesna ; Šadek, Siniša ; Bašić, Ivica
2015.
International Journal of Contemporary Energy

Spatial Distribution of Hydrogen in NEK Containment

Grgić, Davor ; Fancev, Tomislav ; Šadek, Siniša ; Benčik, Vesna
2014.
International Conference Nuclear Energy for New Europe 2014

NPP Krško Containment Modelling and Calculation with the ASTEC Code

Šadek, Siniša
2014.

Decay Heat Calculation for Spent Fuel Pool Application

Grgić, Davor ; Šadek, Siniša ; Benčik, Vesna ; Konjarek , Damir
2014.
10th International Conference on Nuclear Option in Countries with Small and Medium Electricity Grids

Optimization of OPDT Protection for Overcooling Accidents

Benčik, Vesna ; Grgić, Davor ; Šadek, Siniša ; Čavlina , Nikola
2014.
10th International Conference on Nuclear Option in Countries with Small and Medium Electricity Grids

Calculation of Hydrogen Concentration in Containment during LOCA Accident

Grgić, Davor ; Fancev, Tomislav ; Šadek, Siniša
2014.
10th International Conference on Nuclear Option in Countries with Small and Medium Electricity Grids

NPP Krško Containment Modelling with the ASTEC Code

Šadek, Siniša ; Grgić, Davor
2014.
10th International Conference on Nuclear Option in Countries with Small and Medium Electricity Grids

Hot Leg Streaming Calculation for Two-Loop PWR Plant

Grgić, Davor ; Fancev, Tomislav ; Benčik, Vesna ; Šadek, Siniša
2014.
10th International Conference on Nuclear Option in Countries with Small and Medium Electricity Grids

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

Šadek, Siniša ; Amižić, Milan ; Grgić, Davor
2013.
atw - International journal for nuclear power

Severe Accident Analysis in the NPP Krško with the ASTEC Code

Šadek, Siniša ; Amižić, Milan ; Grgić, Davor
2013.
International Conference Nuclear Energy for New Europe 2013

ASTEC Computer Code Application to NPP Krško

Šadek, Siniša
2013.

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

Coupled Code Calculation of Rod Withdrawal at Power Accident

Grgić, Davor ; Benčik, Vesna ; Čavlina, Nikola ; Šadek, Siniša
2011.
International Conference Nuclear Energy for New Europe 2011

RELAP5 Modeling of PWR Reactor RTD Bypass

Grgić, Davor ; Benčik, Vesna ; Šadek, Siniša ; Čavlina, Nikola
2010.
8th International Conference on Nuclear Option in Countries with Small and Medium Electricity Grids

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

Šadek, Siniša ; Grgić, Davor ; Debrecin, Nenad
2010.
8th International Conference on Nuclear Option in Countries with Small and Medium Electricity Grids

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

Grgić, Davor ; Benčik, Vesna ; Šadek, Siniša
2010.
International Conference Nuclear Energy for New Europe 2010

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

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

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.
TopSafe 2008 Conference

QUENCH-11 Experiment Analysis with RELAP5/SCDAPSIM Code

Šadek, Siniša ; Debrecin, Nenad ; Špalj, Srđan
2008.
7th International Conference on Nuclear Option in Countries with Small and Medium Electricity Grids

Analysis of In-Vessel Severe Accident Phenomena in NPP Krško

Šadek, Siniša ; Grgić, Davor ; Čavlina, Nikola
2008.
7th International Conference on Nuclear Option in Countries with Small and Medium Electricity Grids

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.
2nd European Review Meeting on Severe Accident Research (ERMSAR-2007)

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

Šadek, Siniša ; Špalj, Srđan ; Bajs, Tomislav
2007.
International Conference Nuclear Energy for New Europe 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.
International Youth Nuclear Congress 2006

RCP Seal Leakage Analysis During Station Blackout for NPP Krško

Šadek, Siniša ; Špalj, Srđan ; Čavlina, Nikola
2005.
International Conference Nuclear Energy for New Europe 2005

Analysis of Phebus FPT1 Experiment with RELAP5/SCDAPSIM Computer Code

Šadek, Siniša
2004.

Evaluation of the Safety Margins during Shutdown for NPP Krško

Benčik, Vesna ; Šadek, Siniša ; Bajs, Tomislav
2004.
International Conference Nuclear Energy for New Europe 2004

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

Šadek, Siniša ; Špalj, Srđan ; Debrecin, Nenad
2004.
5th International Conference on Nuclear Option in Countries with Small and Medium Electricity Grids

ISP-46 Analysis with RELAP/SCDAPSIM Computer Code

Šadek, Siniša ; Špalj, Srđan ; Debrecin, Nenad
2003.
International Conference Nuclear Energy for New Europe 2003

QUENCH-06 RELAP5/SCDAPSIM Nodalization Notebook

Šadek, Siniša
2003.

RELAP5/SCDAPSIM Analysis of the QUENCH-06 Experiment

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.
4th International Conference on Nuclear Option in Countries with Small and Medium Electricity Grids

Teaching duties

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