Na FER-u postoji više zaposlenika s imenom
Hybrid Shielding Methods Validation Using Graphite Shielding Measurements
PCA Benchmark Analysis with ADVANTG3.0.1. and MCNP6.1.1b Codes
Point Kernel Modification Including Support Vector Regression Neutron Buildup Factor Models
Total Ambient Dose Equivalent Neutron Buildup Factor Calculation Using TART
National Survey on Nuclear Energy and Radioactive Waste in Croatia
Draft Version of the DOCPAGANSA GUI and Control Module
Draft Version of the Computational Module for Simplified Radiological Analyses
I2S-LWR Pressure Vessel Fast Fluence Calculations
PWR Containment Shielding Calculations with SCALE6.1 using Hybrid Deterministic-Stochastic Methodology
Public Opinion Survey - Energy - The Present and the Future – 2015.
Application of Support Vector Regression on Neutron Buildup Factors
Active learning for support vector regression in radiation shielding design
Boration modeling of the PWR biological shield using SCALE6.1 hybrid shielding methodology
RESEARCH AND DEVELOPMENT OF POINT-KERNEL METHOD APPLICATION IN RADIATION SHIELDING
SCALE6.1 HYBRID SHIELDING METHODOLOGY FOR THE SPENT FUEL DRY STORAGE
Dose rates modeling of pressurized water reactor primary loop components with SCALE6.0
Preliminary Analyses of the V2G Technology Role – Case Study Croatia
Transferring an Old Mill Into Micro Hydro Power Plant - Preliminary Techno-Economic Anylsis
Preliminary Techno-Economical Analysis of the Advanced PV/Thermal System for the Household Energy Supply
Modeling of PWR Biological Shield Boration Using SCALE6.1 Hybrid Shielding Methodology
SCALE6 Hybrid Deterministic-Stochastic Shielding Methodology for PWR Containment Calculations
Public Opinion Survey - Energy – The Present and the Future – 2012/2013
Nastavak ispitivanja i analize javnog mnijenja o nuklearnoj energiji
Dose Rates Modeling of Pressurized Water Reactor Primary Loop Components with SCALE6.0
Modeling of the ORNL PCA benchmark using SCALE6.0 hybrid deterministic-stochastic methodology
Three Years’ Experience of the Web Site NEMIS
Nadogradnja portala NEMIS
Sustainability of Nuclear Fuel Resources
PWR Pressure Vessel and Biological Shield Dose Rates Modelling Using SCALE6/FW-CADIS Methodology
Monte Carlo Codes for Neutron Buildup Factors
Full Core Criticality Modeling of Gas-Cooled Fast Reactor Using the SCALE6.0 and MCNP5 Code Packages
Long Term Sustainability of Nuclear Fuel Resources
Two Years Experience of the Web Site NEMIS - “Nuclear Energy – Mysticism and Reality”
Fuel Depletion Modeling of a Gas-cooled Fast Reactor Using the SCALE6.0 Code Package
Modeling of H.B.Robinson-2 Pressure Vessel Benchmark
Upgrade of the FUMACS 2005 Code Package
Learning Support Vector Regression Models for Fast Radiation Dose Rate Calculations
Problem of Computer Programming Education for Technical Engineers
Koncept elektroenergetski nezavisnog otoka u Hrvatskoj - preliminarna studija otoka Visa
Primjena regresijskog modela s potpornim vektorima u proračunu reaktorskog štita
Machine learning of the reactor core loading pattern critical parameters
Public Opinion Survey : "Energy – The Present and the Future"
Public Opinion Survey - Energy - The Present and the Future
On Input Vector Representation for the SVR Model of Reactor Core Loading Pattern Critical Parameters
Neutroničko modeliranje nuklearnog goriva koje sadrži integralne sagorive apsorbere
Support vector regression model for the estimation of γ -ray buildup factors for multi-layer shields
New Features Implemented in FUMACS 2005 Code Package and Future Perspectives in Development of the New Versions
Application of Support Vector Regression in Estimation of Buildup Factors for Double-Layered Shields
Radiological Analyses of Intermediate and Low Level Supercompacted Waste Drums by VQAD Code
Radiation Dose rates in the Vicinity of the NPP Krško Reracked Spent Fuel Pool in Real Case Scenarios
Valorisation of Spectral Influence and Reflection on Photovoltaic Modules - Contribution to Optimisation of Modules Position
2003/04 Public Opinion Survey "Nuclear Energy - the Present and the Future"
Neutroničko modeliranje jezgre IRIS reaktora
Tehno-ekonomski aspekti ultra dugih radnih ciklusa
Modeliranje prijelaznih radnih ciklusa NE Krško u uvjetima povećane snage
IRIS Core Criticality Calculations
2002/03 Public Opinion Survey “ Nuclear Energy – the Present and the Future
Techno-Economical Aspects of Ultra Long Working Cycles
Poboljšanje pristupa optimalizacije položaja fotonaponskog modula i izračun efektivne ozračenosti plohe modula
Radiation Dose Evaluation for Hypothetical Accident with Transport Package Containing Iridium-192 Source
Upgrade Of The Fumacs Code Package
Continued Public Opinion Survey "Nuclear Energy - the Present and the Future"
Techno-economical Analysis of High Level Waste Storage and Disposal Options
FUMACS-G, a Graphical User Interface for FUMACS Code Package
Evaluation Of A Multisource Option Introduced Into Qad-Cggp Code
Model of a Dry Storage Facility for a Medium Nuclear Power Plant
Evaluation of a Multisource Option Introduced into QAD-CGGP Code
Upgrade of the FUMACS Code Package
Double Tiering as an Option for Spent Fuel Pool Capacity Increase
Radiological Implications of Spent Fuel Pool Capacity Increase by Spent Fuel Consolidation
Double tiering as an option for spent fuel pool capacity increase
Radiation Dose Rates in the Vicinity of the NPP Krško Spent Fuel Pool
Validation of QAD-CGGP for Shielding Analyses of Intermediate and Low Level Waste Drums
Extended Burnup Impact on the TN24 Spent Fuel Storage Cask Main Parameters
Concrete spent fuel storage casks dose rates
Consolidation of spent fuel rods as an option to increase the capacity of spent fuel pool
Incorporation of multi-layer option into QAD-CGGP code
Incorporation of multi-layer option into QAD-CGGP code
Razvoj metoda i programa za proračun štitova od nuklearnog zračenja
Nastava
Sveučilišni preddiplomski
- Tehnološke osnove iskorištavanja obnovljivih izvora energije (Nositelj)
- Projekt (Predavanja)
- Projekt (Predavanja)
- Projekt iz programske potpore (Predavanja)
- Projekt iz programske potpore (Predavanja)
- Uvod u programiranje (Predavanja)
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- Fizika 1 (Laboratorijske vježbe)
- Fizika 2 (Laboratorijske vježbe)
- Fizika 2 (Laboratorijske vježbe)
- Fizika 2R (Laboratorijske vježbe)
Sveučilišni diplomski
- Djelovanje i zaštita od zračenja (Nositelj)
- Nuklearni gorivi ciklus i reaktorski materijali (Nositelj)
- Obnovljivi izvori i napredne tehnologije (Nositelj)
- Diplomski projekt (Predavanja)
- Diplomski projekt (Predavanja)
- Diplomski rad (Predavanja)
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Poslijediplomski doktorski
- Novi izvori energije (Nositelj)
- Teorija nuklearnog reaktora (Nositelj)
Kompetencije
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Nuclear and plasma sciences
Neutrons Gamma-rays Gamma-ray detection Gamma-ray effects Radiation effects Biological effects of radiation Gamma-ray effects Ion radiation effects Neutron radiation effects Scintillators -
Computational and artificial intelligence
Machine learning -
Computers and information processing
Programming -
Materials, elements, and compounds
Radioactive materials Nuclear fuels Radioactive decay Radioactive waste Radioactive waste -
Power engineering and energy
Geothermal energy Nuclear fuels Solar energy Wave power Wind energy Wind farms Energy storage Geothermal power generation Hydroelectric power generation Microhydro power Picohydro power Nuclear power generation Fission reactors Solar power generation Maximum power point trackers Photovoltaic systems Solar panels Wind energy generation Wind energy integration Wind power generation Hybrid power systems