PristupačnostNa FER-u postoji više zaposlenika s imenom
Small break LOCA studies for different layouts of passive safety systems in the IRIS reactor
Point-Kernel Code Development for Gamma-Ray Shielding Applications
TRACE/RELAP5 Calculation of NPP Krško SGTR Accident Under Realistic and SRP Conditions
Benchmark Calculation of FHR Fuel Assembly Phase I-C Depletion Exercises
Natural Heat Transfer Performance of Helium Filled Spent Fuel Multi Purpose Container Calculated for Different Initial Pressures
Radiation dose rate analysis of conceptual solution for the Croatian low- and intermediate-level radioactive waste
NPP Krško Steam Generator Tube Rupture (SGTR) Accident Analysis using MELCOR Code
Gamma Dose Rate Calculations for RCC4 and RCC8 Containers using Monte Carlo Codes
Dose Rate Assessment Around the PCFV Release Line During Severe Accident Conditions in Nuclear Power Plant Krsko
Usage of Monte Carlo Code Serpent2 for Calculation of FHR Fuel Assembly
The Assessment of Dose Rates during MPC Loading and Drying in frame of the Nuclear Power Plant Krško First SFDS Loading Campaign
Radiation shielding analysis of the HI-STORM FW storage cask
Estimation of Dose Rates Around Dry Storage Building During Campaign One Loading in Nuclear Power Plant Krsko
Dose Rate Assessment Around The PCFV Release Line During Severe Accident Conditions in Nuclear Power Plant Krsko
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
Influence of reactivity feedback modelling in RELAP5 NEK LONF ATWS calculation
Analysis of the HI-TRAC VW Transfer Cask Dose Rates During Nuclear Power Plant Krsko Spent Fuel Dry Storage Campaign One
Spent Fuel Dry Storage Loading Plan Based on Uniform Decay Heat Distribution among Casks
Methodology to calculate radiological impact for NPP Krško life time extension environmental impact assessment
Analysis of the HI-TRAC VW Transfer Cask Dose Rates During Nuclear Power Plant Krsko Spent Fuel Dry Storage Campaign One
Evaluation of the NEK SFDS Cask Model Using Hybrid Shielding Methodology
Point Kernel Modification Including Support Vector Regression Neutron Buildup Factor Models
Dose Calculation for Emergency Control Room HVAC Filter
Total Ambient Dose Equivalent Neutron Buildup Factor Calculation Using TART
TOTAL AMBIENT DOSE EQUIVALENT BUILDUP FACTORS FOR PORTLAND CONCRETE
Total ambient dose equivalent builldup factors determination for NbS04 Concrete
Total neutron buildup factor modelling using support vector machines
Student Polling on Nuclear Energy and Radioactive Waste Management
Ispitivanje studentskog mnijenja o nuklearnoj energiji i radioaktivnom otpadu
Hybrid Shielding Methods Validation Using Graphite Shielding Measurements
Point Kernel Modification Including Support Vector Regression Neutron Buildup Factor Models
Dose Calculation for Emergency Control Room HVAC Filter
National Survey on Nuclear Energy and Radioactive Waste in Croatia
Draft Version of the Computational Module for Simplified Radiological Analyses
Ispitivanje i analiza javnog mnijenja u Republici Hrvatskoj o nuklearnoj energiji i radioaktivnom otpadu
Ispitivanje i analiza javnog mnijenja o izvorima energije
Razvoj modela primarnog kruga NE Krško za program TRACE
Nastava
Sveučilišni preddiplomski
- Elektroenergetika (Predavanja, Auditorne vježbe)
- Elektroenergetika (Predavanja, Auditorne vježbe)
Sveučilišni diplomski
- Dinamika fluida i prijenos topline (Predavanja, Auditorne vježbe, Laboratorijske vježbe)
- Dinamika fluida i prijenos topline (Predavanja)
- Nuklearna sigurnost (Predavanja, Auditorne vježbe, Laboratorijske vježbe)
- Nuklearna sigurnost (Predavanja)
- Nuklearno inženjerstvo (Predavanja, Auditorne vježbe, Laboratorijske vježbe)
- Obnovljivi izvori i pohrana energije (Predavanja, Auditorne vježbe, Laboratorijske vježbe)
- Obnovljivi izvori i pohrana energije (Predavanja, Auditorne vježbe, Laboratorijske vježbe)
- Proizvodnja električne energije (Predavanja, Auditorne vježbe, Laboratorijske vježbe)
- Proizvodnja električne energije (Predavanja, Auditorne vježbe, Laboratorijske vježbe)
Kompetencije
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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