doc. dr. sc. Siniša Šadek

Docent, Zavod za visoki napon i energetiku

  Poglavlja u knjizi
 
Operation and Performance Analysis of Steam Generators in Nuclear Power Plants // Heat Exchangers - Advanced Features and Applications / S M Sohel Murshed ; Manuel Matos Lopes (ur.).
 
  Izvorni znanstveni i pregledni radovi u CC časopisima
 
Application of ASTEC, MELCOR, and MAAP Computer Codes for Thermal Hydraulic Analysis of a PWR Containment Equipped with the PCFV and PAR Systems. // Science and Technology of Nuclear Installations. (2017) ; 8431934-1-8431934-16 (članak, znanstveni).
Coupled code calculation of rod withdrawal at power accident. // Nuclear engineering and design. 261 (2013) ; 285-305 (članak, znanstveni).
Severe Accident Analysis in a Two-Loop PWR Nuclear Power Plant with the ASTEC Code. // atw - International journal for nuclear power. 58 (2013) , 12; 694-700 (članak, znanstveni).
Radiation heat transfer in a pressurized water reactor lower head filled with molten corium. // Nuclear engineering and design. 254 (2013) ; 154-164 (članak, znanstveni).
Influence of Modelling Options in RELAP5/SCDAPSIM and MAAP4 Computer Codes on Core Melt Progression and Reactor Pressure Vessel Integrity. // Science and Technology of Nuclear Installations. (2010) ; 163279-1-163279-11 (članak, znanstveni).
 
  Ostali radovi u drugim časopisima
 
Independent Review of NPP Modifications and Safety Upgrades. // International Journal of Contemporary Energy. 1 (2015) , 1; 41-51 (članak, stručni).
 
  Znanstveni radovi u zbornicima skupova s međunar.rec.
 
Verification of GOTHIC Multivolume Containment Model during NPP Krško DBA LOCA // Proceedings of the 11th International Conference of the Croatian Nuclear Society / Šimić, Zdenko ; Tomšić, Željko ; Grgić, Davor (ur.).
NPP Krško Station Blackout Analysis after Safety Upgrade Using MELCOR Code // Proceedings of the 11th International Conference of the Croatian Nuclear Society / Šimić, Zdenko ; Tomšić, Željko ; Grgić, Davor (ur.).
NPP Krško DVI LOCA Calculation using RELAP5/mod 3.3 and FRAPTRAN to Assess UFC Modification Influence // Proceedings of the International Conference Nuclear Energy for New Europe 2015 / Jenčič, Igor (ur.).
Optimization of OPDT Protection for Overcooling Accidents // Proceedings of the 10th International Conference on Nuclear Option in Countries with Small and Medium Electricity Grids / Čavlina, Nikola ; Grgić, Davor ; Pevec, Dubravko (ur.).
Hot Leg Streaming Calculation for Two-Loop PWR Plant // Proceedings of the 10th International Conference on Nuclear Option in Countries with Small and Medium Electricity Grids / Čavlina, Nikola ; Grgić, Davor ; Pevec, Dubravko (ur.).
Calculation of Hydrogen Concentration in Containment during LOCA Accident // Proceedings of the 10th International Conference on Nuclear Option in Countries with Small and Medium Electricity Grids / Čavlina, Nikola ; Grgić, Davor ; Pevec, Dubravko (ur.).
Spatial Distribution of Hydrogen in NEK Containment // Proceedings of the International Conference Nuclear Energy for New Europe 2014 / Jenčič, Igor (ur.).
Decay Heat Calculation for Spent Fuel Pool Application // Proceedings of the 10th International Conference on Nuclear Option in Countries with Small and Medium Electricity Grids / Čavlina, Nikola ; Grgić, Davor ; Pevec, Dubravko (ur.).
NPP Krško Containment Modelling with the ASTEC Code // Proceedings of the 10th International Conference on Nuclear Option in Countries with Small and Medium Electricity Grids / Čavlina, Nikola ; Grgić, Davor ; Pevec, Dubravko (ur.).
Severe Accident Analysis in the NPP Krško with the ASTEC Code // Proceedings of the International Conference Nuclear Energy for New Europe 2013 / Cizelj, Leon ; Leskovar, Matjaž ; Uršič, Mitja (ur.).
Coupled Code Calculation of Rod Withdrawal at Power Accident // Proceedings of the International Conference Nuclear Energy for New Europe 2011.
Comparison of R5G Coupled Code and Classical “Two-steps” Containment Calculation // Proceedings of the International Conference Nuclear Energy for New Europe 2010 / Trkov, Andrej ; Lengar, Igor (ur.).
RELAP5 Modeling of PWR Reactor RTD Bypass // Proceedings of the 8th International Conference on Nuclear Option in Countries with Small and Medium Electricity Grids / Pevec, Dubravko ; Subašić, Damir ; Šimić, Zdenko (ur.).
Corium Behaviour and the Lower Head Thermal Response after a Core Meltdown // Proceedings of the 8th International Conference on Nuclear Option in Countries with Small and Medium Electricity Grids / Pevec, Dubravko ; Subašić, Damir ; Šimić, Zdenko (ur.).
QUENCH-11 Experiment Analysis with RELAP5/SCDAPSIM Code // Proceedings of the 7th International Conference on Nuclear Option in Countries with Small and Medium Electricity Grids / Čavlina, Nikola ; Pevec, Dubravko ; Bajs, Tomislav (ur.).
Analysis of In-Vessel Severe Accident Phenomena in NPP Krško // Proceedings of the 7th International Conference on Nuclear Option in Countries with Small and Medium Electricity Grids / Čavlina, Nikola ; Pevec, Dubravko ; Bajs, Tomislav (ur.).
Influence of Modelling Options in RELAP5/SCDAPSIM and MAAP4 Computer Codes on Core Melt Progression and Reactor Pressure Vessel Integrity // Proceedings of the TopSafe 2008 Conference / D'Auria, Francesco ; Čavlina, Nikola (ur.).
Analysis of Small Break LOCA During Mode 3 and Mode 4 Operation for NPP Krško // Proceedings of the International Conference Nuclear Energy for New Europe 2007 / Jenčič, Igor ; Lenošek, Melita (ur.).
Benchmark Exercise on QUENCH-11 Experiment // Proceedings of the 2nd European Review Meeting on Severe Accident Research (ERMSAR-2007).
RCP Seal Leakage Analysis During Station Blackout for NPP Krško // Proceedings of the International Conference Nuclear Energy for New Europe 2005.
Analysis of International Standard Problem ISP-45 on QUENCH Facility Using RELAP5/SCDAPSIM/MOD3.2 Computer Code // Proceedings of the 4th International Conference on Nuclear Option in Countries with Small and Medium Electricity Grids.
 
  Drugi radovi u zbornicima skupova s recenzijom
 
Core Degradation and Hydrogen Production During a Severe Accident // Conference Proceedings of the International Youth Nuclear Congress 2006.
Evaluation of the Safety Margins during Shutdown for NPP Krško // Proceedings of the International Conference Nuclear Energy for New Europe 2004 / Jenčič, Igor ; Tkavc, Marjan (ur.).
Analysis of SBO Accident in NPP Krško using RELAP5/SCDAPSIM/MOD3.2 // Proceedings of the 5th International Conference on Nuclear Option in Countries with Small and Medium Electricity Grids / Pevec, Dubravko ; Debrecin, Nenad (ur.).
ISP-46 Analysis with RELAP/SCDAPSIM Computer Code // Proceedings of the International Conference Nuclear Energy for New Europe 2003.
 
  Disertacije
 
Model izračuna reaktorske faze teških nesreća u nuklearnoj elektrani / doktorska disertacija.
 
  Druge vrste radova
 
NPP Krško Containment Modelling and Calculation with the ASTEC Code, 2014. (izvješće).
ASTEC Computer Code Application to NPP Krško, 2013. (izvješće).
Evaluation of Accident Sequences in IRIS Relevant for Revising the Need for Relocation and Evacuation Measures Unique to NPPs for Innovative SMRs, 2006. (izvješće).
Analysis of Phebus FPT1 Experiment with RELAP5/SCDAPSIM Computer Code, 2004. (interni izvještaj).
RELAP5/SCDAPSIM Analysis of the QUENCH-06 Experiment, 2003. (interni izvještaj).
QUENCH-06 RELAP5/SCDAPSIM Nodalization Notebook, 2003. (interni izvještaj).
Applicability Of Relap5/Scdapsim Code For Thermal-Hydraulic Analysis of Pakistan Research Reactor 1, 2002. (interni izvještaj).
 

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