Pristupačnost
Dynamics for Sustainable Nuclear Buildup Based on LWR and FBR Technologies and Its Impact on CO2 Emission Reduction
Radioactive waste management in Croatia - public opinion, legal framework, and policy
Point Kernel Modification Including Support Vector Regression Neutron Buildup Factor Models
PCA Benchmark Analysis with ADVANTG3.0.1. and MCNP6.1.1b Codes
Student opinion survey on nuclear energy and radioactive waste
Total Ambient Dose Equivalent Neutron Buildup Factor Calculation Using TART
Point Kernel Modification Including Support Vector Regression Neutron Buildup Factor Models
PCA Benchmark Analysis with ADVANTG3.0.1. and MCNP6.1.1b Codes
Hybrid Shielding Methods Validation Using Graphite Shielding Measurements
Public opinion survey in Republic of Croatia on nuclear energy and radioactive waste
Public position on nuclear energy and radioactive waste
Draft Version of the Computational Module for Simplified Radiological Analyses
Draft Version of the DOCPAGANSA GUI and Control Module
National Survey on Nuclear Energy and Radioactive Waste in Croatia
Public Opinion Survey - Energy - The Present and the Future – 2015.
PWR Containment Shielding Calculations with SCALE6.1 using Hybrid Deterministic-Stochastic Methodology
I2S-LWR Pressure Vessel Fast Fluence Calculations
Survey and analysis of public opinion on energy sources
Dose rates modeling of pressurized water reactor primary loop components with SCALE6.0
SCALE6.1 HYBRID SHIELDING METHODOLOGY FOR THE SPENT FUEL DRY STORAGE
RESEARCH AND DEVELOPMENT OF POINT-KERNEL METHOD APPLICATION IN RADIATION SHIELDING
Boration modeling of the PWR biological shield using SCALE6.1 hybrid shielding methodology
Active learning for support vector regression in radiation shielding design
Application of Support Vector Regression on Neutron Buildup Factors
Upgrade of the NEMIS portal 2014
Public Opinion Survey - Energy – The Present and the Future – 2012/2013
SCALE6 Hybrid Deterministic-Stochastic Shielding Methodology for PWR Containment Calculations
Modeling of PWR Biological Shield Boration Using SCALE6.1 Hybrid Shielding Methodology
Preliminary Techno-Economical Analysis of the Advanced PV/Thermal System for the Household Energy Supply
Transferring an Old Mill Into Micro Hydro Power Plant - Preliminary Techno-Economic Anylsis
Preliminary Analyses of the V2G Technology Role – Case Study Croatia
Three Years’ Experience of the Web Site NEMIS
Modeling of the ORNL PCA benchmark using SCALE6.0 hybrid deterministic-stochastic methodology
Dose Rates Modeling of Pressurized Water Reactor Primary Loop Components with SCALE6.0
Continued Research and Analysis of Public Opinion on Nuclear Energy
Monte Carlo Codes for Neutron Buildup Factors
24-Month Operating Cycle Containing Gadolinium Integral Burnable Absorbers for NPP Krško
Full Core Criticality Modeling of Gas-Cooled Fast Reactor using the SCALE6.0 and MCNP5 Code Packages
Long Term Sustainability of Nuclear Fuel Resources
Full Core Criticality Modeling of Gas-Cooled Fast Reactor Using the SCALE6.0 and MCNP5 Code Packages
Monte Carlo Codes for Neutron Buildup Factors
PWR Pressure Vessel and Biological Shield Dose Rates Modelling Using SCALE6/FW-CADIS Methodology
Sustainability of Nuclear Fuel Resources
Upgrade of NEMIS Portal
Modeling of H.B.Robinson-2 Pressure Vessel Benchmark
Fuel Depletion Modeling of a Gas-cooled Fast Reactor Using the SCALE6.0 Code Package
Two Years Experience of the Web Site NEMIS - “Nuclear Energy – Mysticism and Reality”
Problem of Computer Programming Education for Technical Engineers
Learning Support Vector Regression Models for Fast Radiation Dose Rate
Upgrade of the FUMACS 2005 Code Package
Upgrade of FUMACS Code Package for Modeling of NGF and Gadolinium, Final Report
Upgrade of the web portal NEMIS - Nuclear energy mysticism and reality
Zero electric energy island concept in Croatia - preliminary study for the island of Vis
On Input Vector Representation for the SVR Model of Reactor Core Loading Pattern Critical Parameters
Public Opinion Survey - Energy - The Present and the Future
Public Opinion Survey : "Energy – The Present and the Future"
Machine learning of the reactor core loading pattern critical parameters
Application of Support Vector Regression Model in Reactor Shielding Calculations
Public opinion survey on nuclear energy
Support vector regression model for the estimation of γ -ray buildup factors for multi-layer shields
Neutronic modelling of nuclear fuel containing integral burnable absorbers
An overview of the status of nuclear energy in the EU and the USA, and the suitability of certain technologies for the Republic of Croatia
New Features Implemented in FUMACS 2005 Code Package and Future Perspectives in Development of the New Versions
Analysis of nuclear fuel procurement for NPP Krško
Application of Support Vector Regression in Estimation of Buildup Factors for Double-Layered Shields
2003/04 Public Opinion Survey "Nuclear Energy - the Present and the Future"
Valorisation of Spectral Influence and Reflection on Photovoltaic Modules - Contribution to Optimisation of Modules Position
Radiation Dose rates in the Vicinity of the NPP Krško Reracked Spent Fuel Pool in Real Case Scenarios
Radiological Analyses of Intermediate and Low Level Supercompacted Waste Drums by VQAD Code
Techno-Economical Aspects of Ultra Long Working Cycles
2002/03 Public Opinion Survey “ Nuclear Energy – the Present and the Future
IRIS Core Criticality Calculations
Modeling of NPP Krško Transient Operating Cycles for Uprated Conditions
Techno-economical Aspects of Ultra-long Working Cycles
IRIS Core Neutronics Modeling
FUMACS-G, a Graphical User Interface for FUMACS Code Package
Techno-economical Analysis of High Level Waste Storage and Disposal Options
Continued Public Opinion Survey "Nuclear Energy - the Present and the Future"
Upgrade Of The Fumacs Code Package
Radiation Dose Evaluation for Hypothetical Accident with Transport Package Containing Iridium-192 Source
Improvment of the optimization approach of positioning of photovoltaic modules and the effective radiation surfaces of the module
Upgrade of the 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
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
Development of methodes and programs for nuclear radiation shields computation
Incorporation of multi-layer option into QAD-CGGP code
Incorporation of multi-layer option into QAD-CGGP code
Consolidation of spent fuel rods as an option to increase the capacity of spent fuel pool
Concrete spent fuel storage casks dose rates
Extended Burnup Impact on the TN24 Spent Fuel Storage Cask Main Parameters
Validation of QAD-CGGP for Shielding Analyses of Intermediate and Low Level Waste Drums
Analysis of the 24-month operating cycle of the NPP Krško under uprated power conditions
Calculation of thermohydraulic parameters of the spent fuel pool of the NPP Krško with the assumption of denser fuel storage and spent fuel burnup
Generation of cross sections for normal operation and safety analysis of the Krško Nuclear Power Plant
Analysis of storage of the spent fuel accumulated during the entire working life of NPP Krško in the existing spent fuel pool
Teaching duties
University undergraduate
- Technology Basics of Renewable Energy Exploitation (Lecturer in charge)
- Technology Basics of Renewable Energy Exploitation (Lecturer in charge)
- BSc Thesis (Lectures)
- BSc Thesis (Lectures)
- BSc Thesis (Lectures)
- Final BSc Thesis (Lectures)
- Introduction to Programming (Lectures)
- Knowledge Management (Lectures)
- Knowledge Management (Lectures)
- Physics 1 (Lecturers)
- Physics 2R (Lecturers)
- Project (Lectures)
- Project (Lectures)
- Project C (Lectures)
- Software Design Project (Lectures)
- Software Design Project (Lectures)
University graduate
- Fundamentals of Radiation Protection (Lecturer in charge)
- Nuclear Fuel Cycle and Reactor Materials (Lecturer in charge)
- Radiation Effects and Radiation Protection (Lecturer in charge)
- Renewable Resources and Advanced Technology (Lecturer in charge)
- Graduation Thesis (Lectures)
- Graduation Thesis (Lectures)
- Knowledge Management (Lectures)
- Knowledge Management (Lectures)
- Project (Lectures)
- Project (Lectures)
- Project (Lectures)
- Seminar 1 (Lectures)
Postgraduate doctoral study programme
- New Energy Sources (Lecturer in charge)
- Nuclear Reactor Theory (Lecturer in charge)
Competences
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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