Pristupačnost
Point-Kernel Code Development for Gamma-Ray Shielding Applications
Contributon-Informed Approach to RPV Irradiation Study Using Hybrid Shielding Methodology
Proceedings of the 14th International Conference of the Croatian Nuclear Society
Marine Applications of Floating Solar Photovoltaic Systems
Proceedings of the 13th International Conference of the Croatian Nuclear Society
Development of the WinMod web application for wind power system analysis
Development of a user support centre based on microfrontend and microservices architecture
Exploring the Factors Influencing Expansion of Nuclear Energy in Croatia
Progressive web application for events
Web platform for small garden planning, management, and design storage
Mobile application for analyses of gamma ray photos
Development of the SolMod web application for photovoltaic power system analysis
Current status and perspective of renewable energy sources development in Croatia
Održivi razvoj nuklearne energetike utemeljen na raspoloživim količinama plutonija za pogon brzih oplodnih reaktora
Radioactive waste management in Croatia - public opinion, legal framework, and policy
Dynamics for Sustainable Nuclear Buildup Based on LWR and FBR Technologies and Its Impact on CO2 Emission Reduction
Mobile application for ridding school planning and management
PCA Benchmark Analysis with ADVANTG3.0.1. and MCNP6.1.1b Codes
Android application for project management
Point Kernel Modification Including Support Vector Regression Neutron Buildup Factor Models
FIZLer web application for learning physics
Point Kernel Modification Including Support Vector Regression Neutron Buildup Factor Models
Development of modern software support for existing computer code for neutron and gamma dose rate calculations
COINvestigator - web application for e-currency analysis
Modeliranje ukupnoga neutronskoga faktora nakupljanja metodom potpornih vektora
Student opinion survey on nuclear energy and radioactive waste
Student Polling on Nuclear Energy and Radioactive Waste Management
Hybrid Shielding Methods Validation Using Graphite Shielding Measurements
PCA Benchmark Analysis with ADVANTG3.0.1. and MCNP6.1.1b Codes
Total Ambient Dose Equivalent Neutron Buildup Factor Calculation Using TART
Web application and database for connecting e-gamers
Techno-Economical Analysis of Urban Wind Generator
Public opinion survey in Republic of Croatia 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 position on nuclear energy and radioactive waste
Techno-economical analysis of the photovoltaic system for household energy supply
Techno-economical analysis of the roof mounted on-grid photovoltaic system for the household electricity supply
I2S-LWR Pressure Vessel Fast Fluence Calculations
The small photovoltaic installation for the self-sustaining house
Safety Comparison of Molten Salt Reactors with Light-water and Heavy-water Nuclear Reactors
Public Opinion Survey - Energy - The Present and the Future – 2015.
Build up the PV-RO membrane system for brackish water desalination
PWR Containment Shielding Calculations with SCALE6.1 using Hybrid Deterministic-Stochastic Methodology
Techno-economical analysis of the roof mounted off-grid photovoltaic system for the household electricity supply
Energy Storage in Electric Power System
Techno-economical Analysis of the Integrated Solar Power Plant
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
Boration modeling of the PWR biological shield using SCALE6.1 hybrid shielding methodology
Survey and analysis of public opinion on energy sources
Integration of renewable energy sources in smart buildings to increase energy efficiency
Techno-economical analysis of the zero-net energy commercial building
Modelling and simulation of a PV/T system using LabVIEW programming language
Preliminary solar mapping of the Veruda settlement in Pula
Application of Support Vector Regression on Neutron Buildup Factors
Active learning for support vector regression in radiation shielding design
Transformation of old mill to micro hydro power plant
Advanced hybrid renewable systems for 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
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
Upgrade of the NEMIS portal 2014
Preliminary Techno-Economical Analysis of the Advanced PV/Thermal System for the Household Energy Supply
24-Month Operating Cycle Containing Gadolinium Integral Burnable Absorbers for NPP Krško
Continued Research and Analysis of Public Opinion on Nuclear Energy
Modeling of the ORNL PCA benchmark using SCALE6.0 hybrid deterministic-stochastic methodology
Full Core Criticality Modeling of Gas-Cooled Fast Reactor using the SCALE6.0 and MCNP5 Code Packages
Monte Carlo Codes for Neutron Buildup Factors
Dose Rates Modeling of Pressurized Water Reactor Primary Loop Components with SCALE6.0
Three Years’ Experience of the Web Site NEMIS
Techno-economic analysis of a solar photovoltaic power plant with installed capacity of 1 MW
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
Upgrade of NEMIS Portal
Construction of a standalone hybrid system for electricity supply of a larger family house
Sustainability of Nuclear Fuel Resources
Long Term Sustainability of Nuclear Fuel Resources
Two Years Experience of the Web Site NEMIS - “Nuclear Energy – Mysticism and Reality”
Modeling of H.B.Robinson-2 Pressure Vessel Benchmark
Fuel Depletion Modeling of a Gas-cooled Fast Reactor Using the SCALE6.0 Code Package
Learning Support Vector Regression Models for Fast Radiation Dose Rate
Upgrade of the FUMACS 2005 Code Package
Problem of Computer Programming Education for Technical Engineers
Upgrade of FUMACS Code Package for Modeling of NGF and Gadolinium, Final Report
Zero electric energy island concept in Croatia - preliminary study for the island of Vis
Upgrade of the web portal NEMIS - Nuclear energy mysticism and reality
Nuclear Energy Information Portal NEMIS - nuclear energy; mysticism and reality
Machine learning of the reactor core loading pattern critical parameters
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"
Application of Support Vector Regression Model in Reactor Shielding Calculations
Support vector regression model for the estimation of γ -ray buildup factors for multi-layer shields
Public opinion survey on nuclear energy
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
Valorisation of Spectral Influence and Reflection on Photovoltaic Modules - Contribution to Optimisation of Modules Position
Radiological Analyses of Intermediate and Low Level Supercompacted Waste Drums by VQAD Code
2003/04 Public Opinion Survey "Nuclear Energy - the Present and the Future"
Analysis of long-term storage of low and intermediate level waste in NPP Krško
Radiation Dose rates in the Vicinity of the NPP Krško Reracked Spent Fuel Pool in Real Case Scenarios
Economic and energy justification and technical possibilities of introducing an 18-month operating cycle for NPP Krško
Techno-economical Aspects of Ultra-long Working Cycles
Modeling of NPP Krško Transient Operating Cycles for Uprated Conditions
IRIS Core Neutronics Modeling
IRIS Core Criticality Calculations
2002/03 Public Opinion Survey “ Nuclear Energy – the Present and the Future
Techno-Economical Aspects of Ultra Long Working Cycles
Techno-economic optimization of spent fuel storage in NPP Krško during regular and extended life time
Continued Public Opinion Survey "Nuclear Energy - the Present and the Future"
Upgrade Of The Fumacs Code Package
Techno-economical Analysis of High Level Waste Storage and Disposal Options
FUMACS-G, a Graphical User Interface for FUMACS Code Package
Improvment of the optimization approach of positioning of photovoltaic modules and the effective radiation surfaces of the module
Analysis of transit operating cycles of Krško NPP in conditions of power uprate
Radiation Dose Evaluation for Hypothetical Accident with Transport Package Containing Iridium-192 Source
Evaluation Of A Multisource Option Introduced Into Qad-Cggp Code
Upgrade of the FUMACS Code Package
The impact of technical and financial constraints of high radioactive waste disposal on the development of nuclear energy
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
Modernization of the FUMACS code package
Impact of the possibility of increasing the capacity of the spent fuel pool of the NPP Krško with the assumption of denser fuel storage and burnup of spent fuel at dose rates
Calculation of the storage shield for temporary storage of replaced steam generators of NPP Krško
Radiation Dose Rates in the Vicinity of the NPP Krško Spent Fuel Pool
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
Generation of cross sections for normal operation and safety analysis of the Krško Nuclear Power Plant
Calculation of thermohydraulic parameters of the spent fuel pool of the NPP Krško with the assumption of denser fuel storage and spent fuel burnup
Analysis of the 24-month operating cycle of the NPP Krško under uprated power conditions
Development of methodes and programs for nuclear radiation shields computation
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
Analysis of storage of the spent fuel accumulated during the entire working life of NPP Krško in the existing spent fuel pool
Teaching
University undergraduate
- Research of public opinion in acceptance of new technologies (Lecturer in charge, Lecturer in charge)
- Research of public opinion in acceptance of new technologies (Lecturer in charge, Lecturer in charge)
- Technology Basics of Renewable Energy Exploitation (Lecturer in charge)
- Technology Basics of Renewable Energy Exploitation (Lecturer in charge)
- BSc Thesis (Lecturers)
- Final BSc Thesis (Lecturers)
- Project (Lecturers)
- Project C (Lecturers)
- Project E (Lecturers)
University graduate
- Fundamentals of Radiation Protection (Lecturer in charge)
- Fundamentals of Radiation Protection (Lecturer in charge)
- Nuclear Fuel Cycle and Reactor Materials (Lecturer in charge)
- Diploma thesis (Lecturers)
- Graduation Thesis (Lecturers)
- Graduation Thesis (Lecturers)
- Master Project (Lecturers)
- Mentorship Seminar (Lecturers)
- Mentorship Seminar (Lecturers)
- Presentation Seminar (Lecturers)
- Project (Lecturers)
- Project (Lecturers)
Postgraduate doctoral study programme
- Reaktorska analiza (Lecturer in charge)
Competences
-
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
Professional memberships
Member of the Croatian Nuclear Society
Member of the European Nuclear Society