Pristupačnost
Web application for contracting connections to public water supply and drainage
Program development for criticality calculations using Monte Carlo method
Development of a graphical user interface for calculating the attenuation of gamma radiation from a line source
Mobile application for automatic gas meter pattern recognition using machine learning
Marine Applications of Floating Solar Photovoltaic Systems
Contributon-Informed Approach to RPV Irradiation Study Using Hybrid Shielding Methodology
Proceedings of the 14th International Conference of the Croatian Nuclear Society
Radiation dose rate analysis of conceptual solution for the Croatian low- and intermediate-level radioactive waste
Development of web-based social network
Design and implementation of a scalable software solution for apartment rental
Managing and processing of large amounts of data using Delta format
The Assessment of Dose Rates during MPC Loading and Drying in frame of the Nuclear Power Plant Krško First SFDS Loading Campaign
A Comparison of the Radioactive Waste Produced for Different Nuclear Energy Development Scenarios
Estimation of Dose Rates Around Dry Storage Building During Campaign One Loading in Nuclear Power Plant Krsko
Vjekoslav Parać. New acquisitions
Radiation shielding analysis of the HI-STORM FW storage cask
Monitoring of Plant Growth Using Soil Moisture and Temperature Sensor and Camera
Burnup simulation of optimized PWR fuel assembly
Exploring the Factors Influencing Expansion of Nuclear Energy in Croatia
Analysis of the HI-TRAC VW Transfer Cask Dose Rates During Nuclear Power Plant Krsko Spent Fuel Dry Storage Campaign One
Analysis of the HI-TRAC VW Transfer Cask Dose Rates During Nuclear Power Plant Krsko Spent Fuel Dry Storage Campaign One
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
Point Kernel Modification Including Support Vector Regression Neutron Buildup Factor Models
PCA Benchmark Analysis with ADVANTG3.0.1. and MCNP6.1.1b Codes
Dose Calculation for Emergency Control Room HVAC Filter
Influence of Spacer Grids Homogenization on Core Reactivity and Axial Power Distribution
Software development for visualization of Monte Carlo results based on the MCNP program
I2S-LWR Project: Integral Inherently Safe Light Water Reactor (Selected Shielding Analyses)
Nuclear Power Plant Pressurized Water Reactor Fuel Loading Patterns Analysis
Software Development for Visualization of Monte Carlo Results Based on the MCNP Program
Evaluation of the NEK SFDS Cask Model Using Hybrid Shielding Methodology
PARTISN5.97 Code Verification Using keff Analytical Benchmarks
Student Polling on Nuclear Energy and Radioactive Waste Management
Dose Calculation for Emergency Control Room HVAC Filter
Teaching the methods of object detection by robot vision
I2S-LWR pressure vessel fluence calculations using SCALE6.1.3 code package
Influence of Spacer Grids Homogenization on Core Reactivity and Axial Power Distribution
Hybrid Shielding Methods Validation Using Graphite Shielding Measurements
Student opinion survey on nuclear energy and radioactive waste
Point Kernel Modification Including Support Vector Regression Neutron Buildup Factor Models
Total Ambient Dose Equivalent Neutron Buildup Factor Calculation Using TART
PCA Benchmark Analysis with ADVANTG3.0.1. and MCNP6.1.1b Codes
Public opinion survey in Republic of Croatia on nuclear energy and radioactive waste
I2S-LWR Concept Update
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
Carbon Emission Impact for Energy Strategy in Which All Non-CCS Coal Power Plants Are Replaced by NPPs
Nuclear and thermal hydraulic calculation of a representative I2S-LWR first core
Nuclear and thermal hydraulic calculation of a representative I2S-LWR first core
PWR Containment Shielding Calculations with SCALE6.1 using Hybrid Deterministic-Stochastic Methodology
I2S-LWR Activation Analysis of Heat Exchangers Using Hybrid Shielding Methodology With SCALE6.1
Long Term Fuel Sustainable Fission Energy Perspective Relevant for Combating Climate Change
Public Opinion Survey - Energy - The Present and the Future – 2015.
Neutron Buildup Factors Calculation for Support Vector Regression Application in Shielding Analysis
Long Term Fuel Sustainable Fission Energy Perspective Relevant for Combating Climate Change
Spent Fuel Pool Dose Rate Calculations Using Point Kernel and Hybrid Deterministic-Stochastic Shielding Methods
Spent Fuel Pool Dose Rate Calculations Using Point Kernel and Hybrid Deterministic-Stochastic Shielding Methods
I2S-LWR Activation Analysis of Heat Exchangers Using Hybrid Shielding Methodology With SCALE6.1
I2S-LWR Pressure Vessel Fast Fluence Calculations
Carbon Emission Impact for Energy Strategy in which All Non-CCS Coal Power Plants Are Replaced by Nuclear Power Plants
Boration modeling of the PWR biological shield using SCALE6.1 hybrid shielding methodology
Dose rates modeling of pressurized water reactor primary loop components with SCALE6.0
Severe accident gamma dose distribution through NPP Krško containment and auxiliary building calculated using SCALE6/MAVRIC sequence
Active learning for support vector regression in radiation shielding design
SCALE6.1 Hybrid shielding methodology for the spent fuel dry storage
Survey and analysis of public opinion on energy sources
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
SCALE6 Hybrid Deterministic-Stochastic Shielding Methodology for PWR Containment Calculations
Public Opinion Survey - Energy – The Present and the Future – 2012/2013
Molten Salt Thorium Reactor - A Promising Nuclear Technology to Stop Global Warming
Fuel Depletion Modeling of Reconstituted NEK Fuel Assembly Using Lattice Cell Programs
Monte Carlo Codes for Neutron Buildup Factors
Continued Research and Analysis of Public Opinion on Nuclear Energy
Dose Rates Modeling of Pressurized Water Reactor Primary Loop Components with SCALE6.0
Full Core Criticality Modeling of Gas-Cooled Fast Reactor using the SCALE6.0 and MCNP5 Code Packages
Dose rates modelling of pressurized water reactor primary loop components by hybrid deterministic- stochastic methodology.
Modeling of the ORNL PCA benchmark using SCALE6.0 hybrid deterministic-stochastic methodology
Upgrade of NEMIS Portal
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
Modeling of H.B.Robinson-2 Pressure Vessel Benchmark
Manual and automatic variance reduction in Monte Carlo calculations of H.B.Robinson-2 benchmark
Fuel Depletion Modeling of a Gas-cooled Fast Reactor Using the SCALE6.0 Code Package
On the potential of nuclear fission energy for effective reduction of carbon emission under the constraint of uranium resources use without spent fuel reprocessing
Modeling of Pool Critical Assembly Pressure Vessel Facility Benchmark
Upgrade of the FUMACS 2005 Code Package
On the Potential of Nuclear Fission Energy for Effective Reduction of Carbon Emission Under the Constraint of Uranium Resources Use without Spent Fuel Reprocessing
The potential of fission nuclear power in resolving global climate change under the constraints of nuclear fuel resources and once-through fuel cycles
Upgrade of the web portal NEMIS - Nuclear energy mysticism and reality
Upgrade of FUMACS Code Package for Modeling of NGF and Gadolinium, Final Report
Laser ablation on the edge of Cu target
Surface edge of Cu target irradiated by means of pulse laser
Public Opinion Survey - Energy - The Present and the Future
Availability of nuclear fuel for long-term expansion of nuclear power
Edge of copper target irradiated by beam of impulse laser
Sufficiency of the Nuclear Fuel
Nuclear Energy Information Portal NEMIS - nuclear energy; mysticism and reality
Public Opinion Survey : "Energy – The Present and the Future"
Public opinion survey on nuclear energy
Neutronic model development for calculus of a PWR reflector
Teaching
University undergraduate
- Computational Methods in Modern Physics (Lecturer in charge, Lecturer in charge)
- Computational Methods in Modern Physics (Lecturer in charge)
- Fundamentals of Nuclear Physics (Lecturer in charge, Lecturer in charge)
- Fundamentals of Nuclear Physics (Lecturer in charge)
- 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)
- BSc Thesis (Lecturers)
- Project (Lecturers)
- Project C (Lecturers)
- Project E (Lecturers)
- Digital Logic (Laboratory exercises)
- Laser Physics (Laboratory exercises, Laboratory exercises)
- Physics 2R (Laboratory exercises)
University graduate
- Fundamentals of Radiation Protection (Lecturer in charge)
- Introduction to Nanoscience (Lecturer in charge)
- Nuclear Fuel Cycle and Reactor Materials (Lecturer in charge)
- Project (Lecturers)
- Seminar 1 (Lecturers)
Postgraduate doctoral study programme
- Reaktorska analiza (Lecturer in charge)
- Selected Topics in Nuclear Engineering (Lecturer in charge)
Competences
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Nuclear and plasma sciences
Nuclear physics Radiation effects Biological effects of radiation Gamma-ray effects Ion radiation effects Neutron radiation effects Radiation dosage Radiation safety Radiation protection -
Computers and information processing
Computer aided analysis Computer aided engineering Physics computing -
Industry applications
Radiation safety Radiation protection -
Power engineering and energy
Nuclear fuels Nuclear power generation Fission reactors -
Materials, elements, and compounds
Nuclear fuels Radioactive decay Radioactive waste