Pristupačnost
Estimation of Dose Rates Around Dry Storage Building During Campaign One Loading in Nuclear Power Plant Krsko
A Comparison of the Radioactive Waste Produced for Different Nuclear Energy Development Scenarios
Vjekoslav Parać. New acquisitions
Radiation shielding analysis of the HI-STORM FW storage cask
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
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
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)
Evaluation of the NEK SFDS Cask Model Using Hybrid Shielding Methodology
Dose Calculation for Emergency Control Room HVAC Filter
Influence of Spacer Grids Homogenization on Core Reactivity and Axial Power Distribution
Point Kernel Modification Including Support Vector Regression Neutron Buildup Factor Models
PCA Benchmark Analysis with ADVANTG3.0.1. and MCNP6.1.1b Codes
Student Polling on Nuclear Energy and Radioactive Waste Management
Student opinion survey on nuclear energy and radioactive waste
I2S-LWR pressure vessel fluence calculations using SCALE6.1.3 code package
Teaching the methods of object detection by robot vision
Dose Calculation for Emergency Control Room HVAC Filter
Influence of Spacer Grids Homogenization on Core Reactivity and Axial Power Distribution
PARTISN5.97 Code Verification Using keff Analytical Benchmarks
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
Carbon Emission Impact for Energy Strategy in Which All Non-CCS Coal Power Plants Are Replaced by NPPs
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
Neutron Buildup Factors Calculation for Support Vector Regression Application in Shielding Analysis
Spent Fuel Pool Dose Rate Calculations Using Point Kernel and Hybrid Deterministic-Stochastic Shielding Methods
Nuclear and thermal hydraulic calculation of a representative I2S-LWR first core
Spent Fuel Pool Dose Rate Calculations Using Point Kernel and Hybrid Deterministic-Stochastic Shielding Methods
Nuclear and thermal hydraulic calculation of a representative I2S-LWR first core
I2S-LWR Activation Analysis of Heat Exchangers Using Hybrid Shielding Methodology With SCALE6.1
Carbon Emission Impact for Energy Strategy in which All Non-CCS Coal Power Plants Are Replaced by Nuclear Power Plants
Long Term Fuel Sustainable Fission Energy Perspective Relevant for Combating Climate Change
Long Term Fuel Sustainable Fission Energy Perspective Relevant for Combating Climate Change
I2S-LWR Activation Analysis of Heat Exchangers Using Hybrid Shielding Methodology With SCALE6.1
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
Severe accident gamma dose distribution through NPP Krško containment and auxiliary building calculated using SCALE6/MAVRIC sequence
Dose rates modeling of pressurized water reactor primary loop components with SCALE6.0
SCALE6.1 HYBRID SHIELDING METHODOLOGY FOR THE SPENT FUEL DRY STORAGE
Boration modeling of the PWR biological shield using SCALE6.1 hybrid shielding methodology
Active learning for support vector regression in radiation shielding design
Upgrade of the NEMIS portal 2014
Fuel Depletion Modeling of Reconstituted NEK Fuel Assembly Using Lattice Cell Programs
Molten Salt Thorium Reactor - A Promising Nuclear Technology to Stop Global Warming
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
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
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
Full Core Criticality Modeling of Gas-Cooled Fast Reactor using the SCALE6.0 and MCNP5 Code Packages
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
Upgrade of NEMIS Portal
Manual and automatic variance reduction in Monte Carlo calculations of H.B.Robinson-2 benchmark
Modeling of H.B.Robinson-2 Pressure Vessel Benchmark
Fuel Depletion Modeling of a Gas-cooled Fast Reactor Using the SCALE6.0 Code Package
The potential of fission nuclear power in resolving global climate change under the constraints of nuclear fuel resources and once-through fuel cycles
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
On the potential of nuclear fission energy for effective reduction of carbon emission under the constraint of uranium resources use without spent fuel reprocessing
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
Laser ablation on the edge of Cu target
Nuclear Energy Information Portal NEMIS - nuclear energy; mysticism and reality
Surface edge of Cu target irradiated by means of pulse laser
Edge of copper target irradiated by beam of impulse laser
Sufficiency of the Nuclear Fuel
Availability of nuclear fuel for long-term expansion of nuclear power
Public Opinion Survey - Energy - The Present and the Future
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 (Lectures)
- BSc Thesis (Lectures)
- Digital Logic (Lecturers)
- Introduction to Programming (Lecturers)
- Laser Physics (Lecturers, Lecturers)
- Physics 2R (Lecturers)
- Project (Lectures)
- Project C (Lectures)
- Project E (Lectures)
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 (Lectures)
- Seminar 1 (Lectures)
Postgraduate doctoral study programme
- Nuclear Reactor Theory (Lecturer in charge)
- Selected Topics in Nuclear Physics and 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