| Coupled code calculation of rod withdrawal at power accident D Grgić, V Benčik, S Šadek Nuclear engineering and design 261, 285-305, 2013 | 9 | 2013 |
| Analysis of the upflow conversion modification and influence on selected LOCA accidents in a PWR plant S Šadek, D Grgić, V Benčik, Š Vlahović Nuclear engineering and design 369, 110854, 2020 | 5 | 2020 |
| Analysis of the NPP Krško Station Blackout Accident with PAR and PCFV Using MELCOR 1.8. 6 Code S Šadek, D Grgić, V Benčik FER-ZVNE/SA/DA-TR01/15-1, Revision 1, 2015 | 5 | 2015 |
| RELAP5 modeling of PWR reactor RTD bypass D Grgić, V Benčik, S Šadek, N Čavlina Proc. of the 8 th Int. Conf. on Nuclear Option in Countries with Small and …, 2010 | 5 | 2010 |
| NPP Krško Station Blackout Analysis after Safety Upgrade Using MELCOR Code S Šadek, D Grgić, V Benčik Journal of Energy: Energija 65 (3-4), 0-0, 2016 | 4 | 2016 |
| RELAP5/MOD3. 3 analysis of the Reactor Coolant Pump Trip event at NPP Krsko for different transient scenarios V Bencik, T Bajs, N Debrecin | 4 | 2005 |
| Spatial Distribution of Hydrogen in NEK Containment D Grgić, T Fancev, S Šadek, V Benčik Proc. 23rd Int. Conf. Nuclear Energy for New Europe (NENE2014), Portorož …, 2014 | 3 | 2014 |
| NPP Krsko RELAP5 Analysis of the Scaled Loss of RHR Experiment Scenario V Bencik, T Bajs, I Basic | 3 | 2002 |
| Independent review of NPP modifications and safety upgrades D Grgić, V Benčik, S Šadek, I Bašić International journal of contemporary energy 1 (1), 41-51, 2015 | 2 | 2015 |
| Tomislav Fancev D Grgic, S Šadek, V Benčik, I Bašić International Conference Nuclear Energy for New Europe, 2014 | 2 | 2014 |
| Hot Leg Streaming Calculation for Two-Loop PWR Plant D Grgić, T Fancev, V Benčik, S Šadek 10th International Conference on Nuclear Option in Countries with Small and …, 2014 | 2 | 2014 |
| Analysis of OECD/CSNI ISP-42 Phase A PANDA Experiment using RELAP5/mod3. 3 and GOTHIC 7.2 a Code V Benčik Book of Abstracts, 59, 2009 | 2 | 2009 |
| NEK 3 inch Cold Leg Break LOCA Calculation using TRACE 5.0 p5 and RELAP5/MOD 3.3 Codes V Benčik, D Grgić, S Šadek 13th International Conference of the Croatian Nuclear Society, 2022 | 1 | 2022 |
| NPP Krško Post-UFC Transient Response during MSLB Š Vlahović, D Grgić, V Benčik Journal of Energy: Energija 65 (1-2), 0-0, 2016 | 1 | 2016 |
| NPP Krško DVI LOCA Calculation using RELAP5/mod 3.3 and FRAPTRAN to Assess UFC Modification Influence V Benčik, D Grgić, S Šadek, N Čavlina International Conference Nuclear Energy for New Europe 2015, 207.1-207.12, 2015 | 1 | 2015 |
| Decay Heat Calculation for Spent Fuel Pool Application D Grgić, S Šadek, V Benčik, D Konjarek Proceedings of the 10th International Conference on Nuclear Option in …, 2014 | 1 | 2014 |
| Analysis of Steam Generator Tube Rupture (SGTR) Accident for NPP Krško V Benčik, D Grgić, N Čavlina International Conference Nuclear Energy for New Europe 2012, 521.1-521.9, 2012 | 1 | 2012 |
| RELAP5/MOD 3.3 Analysis of Reactor Coolant Pump Trip Event at NPP Krško V Benčik, N Debrecin, D Feretić Deterministic Analysis of Operational Events in Nuclear Power Plants, 91, 2007 | 1 | 2007 |
| Verification of the Coupled Code RELAP5-QUABOX/CUBBOX by Large Load Rejection Analysis for NPP Krško V Benčik, D Feretić, D Grgić 3rd International Conference on Nuclear Option in Countries with Small and …, 2000 | 1 | 2000 |
| Application of the coupled code RELAP5-QUABOX/CUBBOX in Best-Estimate Analyses of Nuclear Power Plants V Benčik, D Grgić, D Feretić ANS International Meeting on Best Estimate Methods in Nuclear Installations …, 2000 | 1 | 2000 |
