PristupačnostNa FER-u postoji više zaposlenika s imenom
Point-Kernel Shielding Applications of Sievert Integral
Point-Kernel Code Development for Gamma-Ray Shielding Applications
Web aplikacija za vizualizaciju MARS geometrije
Proceedings of the 14th International Conference of the Croatian Nuclear Society
Marine applications of floating solar photovoltaic systems
Contributon-Informed Approach to RPV Irradiation Study Using Hybrid Shielding Methodology
Proceedings of the 13th International Conference of the Croatian Nuclear Society
Aplikacija za analizu fotografija nastalih djelovanjem gama zračenja
Trenutačni status i perspektiva razvoja obnovljivih izvora energije u Hrvatskoj
Exploring the Factors Influencing Expansion of Nuclear Energy in Croatia
Razvoj WinMod web aplikacije za proračune vjetro sustava za proizvodnju električne energije
Progresivna web aplikacija za događaje
Razvoj centra korisničke podrške baziranog na mikrofrontend i mikroservisnoj arhitekturi
Web platforma za planiranje, upravljanje i pohranu dizajna manjih vrtova
Razvoj SolMod web aplikacije za proračune fotovoltaičnih sustava za proizvodnju električne energije
Nuclear energy sustainable development based on available plutonium resources for operation of fast breeder reactors
Dynamics for Sustainable Nuclear Buildup Based on LWR and FBR Technologies and Its Impact on CO2 Emission Reduction
Mobilna aplikacija za planiranje i upravljanje školom jahanja
Radioactive waste management in Croatia - public opinion, legal framework, and policy
FIZLer web aplikacija za učenje fizike
Point Kernel Modification Including Support Vector Regression Neutron Buildup Factor Models
Mobilna aplikacija za upravljanje projektima
PCA Benchmark Analysis with ADVANTG3.0.1. and MCNP6.1.1b Codes
Total Ambient Dose Equivalent Neutron Buildup Factor Calculation Using TART
Student Polling on Nuclear Energy and Radioactive Waste Management
Ispitivanje studentskog mnijenja o nuklearnoj energiji i radioaktivnom otpadu
Total neutron buildup factor modelling using support vector machines
Razvoj suvremene programske potpore za postojeći računalni program za izračunavanje brzina doza neutronskog i gama zračenja
COINvestigator - web aplikacija za analizu e-valuta
Web-aplikacija i baza podataka za povezivanje e-igrača
Tehno-ekonomska analiza urbanog vjetroagregata
Point Kernel Modification Including Support Vector Regression Neutron Buildup Factor Models
Hybrid Shielding Methods Validation Using Graphite Shielding Measurements
PCA Benchmark Analysis with ADVANTG3.0.1. and MCNP6.1.1b Codes
Draft Version of the Computational Module for Simplified Radiological Analyses
Ispitivanje i analiza javnog mnijenja u Republici Hrvatskoj o nuklearnoj energiji i radioaktivnom otpadu
National Survey on Nuclear Energy and Radioactive Waste in Croatia
Stav javnosti o nuklearnoj energiji i radioaktivnom otpadu
Draft Version of the DOCPAGANSA GUI and Control Module
Usporedba nuklearnih reaktora s tekućim solima s lakovodnim i teškovodnim nuklearnim reaktorima sa stajališta sigurnosti
Public Opinion Survey - Energy - The Present and the Future – 2015.
Tehno-ekonomska analiza naprednog fotonaponskog sustava za opskrbu električnom energijom obiteljske kuće
Build up the PV-RO membrane system for brackish water desalination
Skladištenje energije u elektroenergetskom sustavu
The small photovoltaic installation for the self-sustaining house
Techno-economical analysis of the roof mounted on-grid photovoltaic system for the household electricity supply
PWR Containment Shielding Calculations with SCALE6.1 using Hybrid Deterministic-Stochastic Methodology
I2S-LWR Pressure Vessel Fast Fluence Calculations
Techno-economical analysis of the roof mounted off-grid photovoltaic system for the household electricity supply
Boration modeling of the PWR biological shield using SCALE6.1 hybrid shielding methodology
Active learning for support vector regression in radiation shielding design
Research and development of Point-Kernel method application in radiation shielding
Tehno-ekonomska analiza energetski neovisne poslovne zgrade
Preliminarno solarno mapiranje naselja Veruda u Puli
Tehno-ekonomska analiza integrirane Sunčeve elektrane
Ispitivanje i analiza javnog mnijenja o izvorima energije
SCALE6.1 Hybrid shielding methodology for the spent fuel dry storage
Dose rates modeling of pressurized water reactor primary loop components with SCALE6.0
Application of Support Vector Regression on Neutron Buildup Factors
Modeliranje i simulacija rada PV/T sustava u LabVIEW programskom jeziku
Integracija obnovljivih izvora energije u pametne zgrade s ciljem povećanja energetske učinkovitosti
Public Opinion Survey - Energy – The Present and the Future – 2012/2013
Prenamjena stare mlinice u mikro hidroelektranu
SCALE6 Hybrid Deterministic-Stochastic Shielding Methodology for PWR Containment Calculations
Nadogradnja NEMIS portala 2014
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
Napredni hibridni sustavi obnovljivih izvora energije za opskrbu energijom obiteljske kuće
Transferring an Old Mill Into Micro Hydro Power Plant - Preliminary Techno-Economic Anylsis
Preliminary Analyses of the V2G Technology Role – Case Study Croatia
24-Month Operating Cycle Containing Gadolinium Integral Burnable Absorbers for NPP Krško
Three Years’ Experience of the Web Site NEMIS
Nastavak ispitivanja i analize javnog mnijenja o nuklearnoj energiji
Full Core Criticality Modeling of Gas-Cooled Fast Reactor using the SCALE6.0 and MCNP5 Code Packages
Modeling of the ORNL PCA benchmark using SCALE6.0 hybrid deterministic-stochastic methodology
Monte Carlo Codes for Neutron Buildup Factors
Tehno-ekonomska analiza solarne fotonaponske elektrane instalirane snage 1 MW
Dose Rates Modeling of Pressurized Water Reactor Primary Loop Components with SCALE6.0
Sustainability of Nuclear Fuel Resources
Nadogradnja portala NEMIS
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
Dimenzioniranje samostalnog hibridnog sustava za opskrbu električnom energijom veće obiteljske kuće
Modeling of H.B.Robinson-2 Pressure Vessel Benchmark
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
Problem of Computer Programming Education for Technical Engineers
Upgrade of the FUMACS 2005 Code Package
Learning Support Vector Regression Models for Fast Radiation Dose Rate
Nadogradnja informatičkog portala NEMIS - Nuklearna energija mistika i stvarnost
Koncept elektroenergetski nezavisnog otoka u Hrvatskoj - preliminarna studija otoka Visa
Upgrade of FUMACS Code Package for Modeling of NGF and Gadolinium, Final Report
Informacijski portal o nuklearnoj energiji NEMIS - nuklearna energija; mistika i stvarnost
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
Primjena regresijskog modela s potpornim vektorima u proračunu reaktorskog štita
Ispitivanje i analiza javnog mnijenja o nuklearnoj energiji
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
Pregled statusa nuklearne energetike u EU i SAD, te prikladnost pojedinih tehnologija za RH
Application of Support Vector Regression in Estimation of Buildup Factors for Double-Layered Shields
Analiza nabave nuklearnog goriva za NE Krško
Radiation Dose rates in the Vicinity of the NPP Krško Reracked Spent Fuel Pool in Real Case Scenarios
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
Radiological Analyses of Intermediate and Low Level Supercompacted Waste Drums by VQAD Code
Analiza dugoročnog smještaja nisko i srednje aktivnog otpada u NE Krško
Tehno-ekonomska optimizacija odlaganja ozračenog goriva u NE Krško u redovnom i produljenom životnom vijeku
IRIS Core Criticality Calculations
Neutroničko modeliranje jezgre IRIS reaktora
Modeliranje prijelaznih radnih ciklusa NE Krško u uvjetima povećane snage
Techno-Economical Aspects of Ultra Long Working Cycles
2002/03 Public Opinion Survey “ Nuclear Energy – the Present and the Future
Tehno-ekonomski aspekti ultra dugih radnih ciklusa
Ekonomsko-energetska opravdanost i tehničke mogućnosti uvođenja 18-mjesečnog radnog ciklusa za NE Krško
Upgrade Of The Fumacs Code Package
Radiation Dose Evaluation for Hypothetical Accident with Transport Package Containing Iridium-192 Source
Analiza prijelaznih radnih ciklusa NE Krško u uvjetima povećane snage
Poboljšanje pristupa optimalizacije položaja fotonaponskog modula i izračun efektivne ozračenosti plohe modula
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
Evaluation Of A Multisource Option Introduced Into Qad-Cggp Code
Upgrade of the FUMACS Code Package
Utjecaj tehničkih i financijskih ograničenja odlaganja visoko radioaktivnog otpada na razvoj nuklearne energetike
Model of a Dry Storage Facility for a Medium Nuclear Power Plant
Double Tiering as an Option for Spent Fuel Pool Capacity Increase
Double tiering as an option for spent fuel pool capacity increase
Radiological Implications of Spent Fuel Pool Capacity Increase by Spent Fuel Consolidation
Modernizacija paketa računalskih programa FUMACS
Utjecaj mogućnosti povećanja kapaciteta bazena za istrošeno gorivo NE Krško uz pretpostavku gušćeg smještaja goriva i odgora istrošenog goriva na brzine doza
Radiation Dose Rates in the Vicinity of the NPP Krško Spent Fuel Pool
Proračun štita spremišta za privremenu pohranu dotrajalih parogeneratora NE Krško
Analiza 24 mjesečnog radnog ciklusa NE Krško u uvjetima povećanja snage
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
Razvoj metoda i programa za proračun štitova od nuklearnog zračenja
Validation of QAD-CGGP for Shielding Analyses of Intermediate and Low Level Waste Drums
Concrete spent fuel storage casks dose rates
Incorporation of multi-layer option into QAD-CGGP code
Extended Burnup Impact on the TN24 Spent Fuel Storage Cask Main Parameters
Proračun termohidrauličkih parametara bazena za istrošeno gorivo NE Krško uz pretpostavku gušćeg smještaja goriva i odgora istrošenog goriva
Generiranje udarnih presjeka za redoviti pogon i sigurnosne analize Nuklearne elektrane Krško
Analiza pohrane istrošenog goriva akumuliranog tijekom čitavog radnog vijeka NE Krško u postojećem bazenu za istrošeno gorivo
Nastava
Sveučilišni preddiplomski
- Istraživanje javnog mnijenja u prihvatu novih tehnologija (Nositelj, Nositelj)
- Istraživanje javnog mnijenja u prihvatu novih tehnologija (Nositelj, Nositelj)
- Tehnološke osnove iskorištavanja obnovljivih izvora energije (Nositelj)
- Tehnološke osnove iskorištavanja obnovljivih izvora energije (Nositelj)
- Projekt (Predavanja)
- Projekt E (Predavanja)
- Projekt R (Predavanja)
- Završni rad (Predavanja)
- Završni rad (Predavanja)
Sveučilišni diplomski
- Nuklearni gorivi ciklus i reaktorski materijali (Nositelj)
- Osnove zaštite od zračenja (Nositelj)
- Osnove zaštite od zračenja (Nositelj)
- Diplomski projekt (Predavanja)
- Diplomski projekt (Predavanja)
- Diplomski projekt (Predavanja)
- Diplomski rad (Predavanja)
- Diplomski rad (Predavanja)
- Diplomski rad (Predavanja)
- Mentorski seminar (Predavanja)
- Mentorski seminar (Predavanja)
- Prezentacijski seminar (Predavanja)
Poslijediplomski doktorski
- Reaktorska analiza (Nositelj)
Kompetencije
-
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
Profesionalni interesi i članstva
Član Hrvatskog nuklearnog društva
Član Europskog nuklearnog društva