Pristupačnost
Point-Kernel Code Development for Gamma-Ray Shielding Applications
Supporting CFD thermal cycling and thermal stratification analyses in SI-53 line
TRACE/RELAP5 Calculation of NPP Krško SGTR Accident Under Realistic and SRP Conditions
Calculation of Limiting Radiological Consequences of NEK HP and LP SBO Sequences
Small break LOCA studies for different layouts of passive safety systems in the IRIS reactor
Ranking of Passive Safety Systems in an Integral Pressurized Water Reactor
Estimation of Radiation Dose rates within the New Central Storage of the Croatian Radioactive Waste Management Center
Natural Heat Transfer Performance of Helium Filled Spent Fuel Multi Purpose Container Calculated for Different Initial Pressures
Gamma Dose Rate Calculations for RCC4 and RCC8 Containers using Monte Carlo Codes
Benchmark Calculation of FHR Fuel Assembly Phase I-C Depletion Exercises
Radiation dose rate analysis of conceptual solution for the Croatian low- and intermediate-level radioactive waste
Dose Rate Assessment Around the PCFV Release Line During Severe Accident Conditions in Nuclear Power Plant Krsko
NPP Krško Steam Generator Tube Rupture (SGTR) Accident Analysis using MELCOR Code
The Assessment of Dose Rates during MPC Loading and Drying in frame of the Nuclear Power Plant Krško First SFDS Loading Campaign
Usage of Monte Carlo Code Serpent2 for Calculation of FHR Fuel Assembly
Estimation of Dose Rates Around Dry Storage Building During Campaign One Loading in Nuclear Power Plant Krsko
Radiation shielding analysis of the HI-STORM FW storage cask
Dose Rate Assessment Around The PCFV Release Line During Severe Accident Conditions in Nuclear Power Plant Krsko
Influence of reactivity feedback modelling in RELAP5 NEK LONF ATWS calculation
Thermal Response of External Duct Piping in Case PCFV Actuation During Prolonged NEK SBO
Thermal Model of HI STORM FW Cask for COBRA-SFS Code
Analysis of the HI-TRAC VW Transfer Cask Dose Rates During Nuclear Power Plant Krsko Spent Fuel Dry Storage Campaign One
Methodology to calculate radiological impact for NPP Krško life time extension environmental impact assessment
Spent Fuel Dry Storage Loading Plan Based on Uniform Decay Heat Distribution among Casks
Analysis of the HI-TRAC VW Transfer Cask Dose Rates During Nuclear Power Plant Krsko Spent Fuel Dry Storage Campaign One
Point Kernel Modification Including Support Vector Regression Neutron Buildup Factor Models
Dose Calculation for Emergency Control Room HVAC Filter
Evaluation of the NEK SFDS Cask Model Using Hybrid Shielding Methodology
Point Kernel Modification Including Support Vector Regression Neutron Buildup Factor Models
Hybrid Shielding Methods Validation Using Graphite Shielding Measurements
Modeliranje ukupnoga neutronskoga faktora nakupljanja metodom potpornih vektora
Total Ambient Dose Equivalent Neutron Buildup Factor Calculation Using TART
Student opinion survey on nuclear energy and radioactive waste
TOTAL AMBIENT DOSE EQUIVALENT BUILDUP FACTORS FOR PORTLAND CONCRETE
Dose Calculation for Emergency Control Room HVAC Filter
Total ambient dose equivalent builldup factors determination for NbS04 Concrete
Student Polling on Nuclear Energy and Radioactive Waste Management
Public opinion survey in Republic of Croatia on nuclear energy and radioactive waste
Draft Version of the Computational Module for Simplified Radiological Analyses
National Survey on Nuclear Energy and Radioactive Waste in Croatia
Survey and analysis of public opinion on energy sources
Development of NPP Krško Primary Loop Model for TRACE code
Teaching
University undergraduate
- Electric Power Engineering (Lecturer in charge, Lecturers)
- Electric Power Engineering (Lecturer in charge, Lecturers)
University graduate
- Fluid Dynamics and Heat Transfer (Lecturer in charge, Lecturers, Laboratory exercises)
- Nuclear Engineering (Lecturer in charge, Lecturers, Laboratory exercises)
- Nuclear Safety (Lecturer in charge, Lecturers, Laboratory exercises)
- Power Generation (Lecturer in charge, Lecturers, Laboratory exercises)
- Power Generation (Lecturer in charge, Lecturers, Laboratory exercises)
- Renewable Energy and Energy Storage (Lecturer in charge, Lecturers, Laboratory exercises)
- Renewable Energy and Energy Storage (Lecturer in charge, Lecturers, Laboratory exercises)
- Fluid Dynamics and Heat Transfer (Lecturers)
- Nuclear Safety (Lecturers)
Competences
-
Industry applications
Renewable energy sources Radiation safety Radiation protection -
Instrumentation and measurement
Radiation monitoring -
Materials, elements, and compounds
Radioactive materials Nuclear fuels Radioactive decay Radioactive waste -
Nuclear and plasma sciences
Biological effects of radiation Gamma-ray effects Neutron radiation effects Total ionizing dose Radiation dosage Radiation protection -
Power engineering and energy
Nuclear fuels Geothermal power generation Hydroelectric power generation Nuclear power generation Fission reactors Solar power generation Wind power generation Power system reliability