MAAP 4.07 Analysis of Long Term Containment Heat Removal After Reactor Vessel Failure (DEC-B) for Nuclear Power Plant Krško (NEK) von Jalovec, Robi, Špalj, Srđan

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RELAP5/mod3.3 Analysis of Natural Circulation Cooldown with One Inactive Loop for Nuclear Power Plant Krško (NEK) von Špalj, Srđan, Cizel, Franc

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

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External Reactor Vessel Cooling Evaluation for Severe Accident Mitigation in NPP Krško von Mihalina, Mario, Špalj, Srđan, Glaser, Bruno

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RELAP5/mod 3.3 Analysis of Natural Circulation Cooldown with One Inactive Loop for Nuclear Power Plant Krško (NEK) von Špalj, Srđan, Cizel, Franc

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Dose Calculation for Emergency Control Room HVAC Filter von Grgić, Davor, Vlahović, Štefica, Matijević, Mario, Dučkić, Paulina, Špalj, Srđan

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Dose Calculation for Emergency Control Room HVAC Filter von Grgić, Davor, Vlahović, Štefica, Matijević, Mario, Dučkić, Paulina, Špalj, Srđan

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External Reactor Vessel Cooling Evaluation for Severe Accident Mitigation in NPP Krško von Mihalina, Mario, Špalj, Srđan, Glaser, Bruno

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