Search Results - Šadek, Siniša

  • Showing 1 - 9 results of 9
Refine Results
  1. 1
    Uncertainty Study of the In-Vessel Phase of a Severe Accident in a Pressurized Water Reactor

    Uncertainty Study of the In-Vessel Phase of a Severe Accident in a Pressurized Water Reactor by Šadek, Siniša, Grgić, Davor, Allison, Chris, Perez-Ferragut, Marina

    Published in Energies (Basel)
    Get full text
    Items that this one cites
    Items that cite this one
    Article
    Save to List
    Saved in:
  2. 2
    Room Classification Based on EMC Conditions in Nuclear Power Plants

    Room Classification Based on EMC Conditions in Nuclear Power Plants by Grganić, Hrvoje, Grgić, Davor, Šadek, Siniša

    Published in Energies (Basel)
    Get full text
    Items that this one cites
    Items that cite this one
    Article
    Save to List
    Saved in:
  3. 3
    Comparison of Measured and Calculated Data for NPP Krško CILR Test

    Comparison of Measured and Calculated Data for NPP Krško CILR Test by Vlahović, Štefica, Šadek, Siniša, Grgić, Davor, Fancev, Tomislav, Benčik, Vesna

    Published in Energies (Basel)
    Get full text
    Article
    Save to List
    Saved in:
  4. 4
    Application of ASTEC, MELCOR, and MAAP Computer Codes for Thermal Hydraulic Analysis of a PWR Containment Equipped with the PCFV and PAR Systems

    Application of ASTEC, MELCOR, and MAAP Computer Codes for Thermal Hydraulic Analysis of a PWR Containment Equipped with the PCFV and PAR Systems by Sadek, Sinisa, Grgic, Davor, Simic, Zdenko

    Get full text
    Items that this one cites
    Items that cite this one
    Article
    Save to List
    Saved in:
  5. 5
    Influence of Modelling Options in RELAP5/SCDAPSIM and MAAP4 Computer Codes on Core Melt Progression and Reactor Pressure Vessel Integrity

    Influence of Modelling Options in RELAP5/SCDAPSIM and MAAP4 Computer Codes on Core Melt Progression and Reactor Pressure Vessel Integrity by Šadek, Siniša, Glaser, Bruno, Špalj, Srđan

    Get full text
    Items that this one cites
    Items that cite this one
    Article
    Save to List
    Saved in:
  6. 6
    Small break LOCA studies for different layouts of passive safety systems in the IRIS reactor

    Small break LOCA studies for different layouts of passive safety systems in the IRIS reactor by Šadek, Siniša, Grgić, Davor, Družijanić, Paulina

    Get full text
    Article
    Save to List
    Saved in:
  7. 7
    Analysis of the upflow conversion modification and influence on selected LOCA accidents in a PWR plant

    Analysis of the upflow conversion modification and influence on selected LOCA accidents in a PWR plant by Šadek, Siniša, Grgić, Davor, Benčik, Vesna, Vlahović, Štefica

    Get full text
    Items that this one cites
    Items that cite this one
    Article
    Save to List
    Saved in:
  8. 8
    Radiation heat transfer in a pressurized water reactor lower head filled with molten corium

    Radiation heat transfer in a pressurized water reactor lower head filled with molten corium by Šadek, Siniša, Grgić, Davor, Debrecin, Nenad

    Get full text
    Items that this one cites
    Items that cite this one
    Article
    Save to List
    Saved in:
  9. 9
    Coupled code calculation of rod withdrawal at power accident

    Coupled code calculation of rod withdrawal at power accident by Grgic, Davor, Benfrk, Vesna, Sadek, Sinisa

    Get full text
    Items that this one cites
    Items that cite this one
    Article
    Save to List
    Saved in:

Search Tools: