A Comparison of the Radioactive Waste Produced for Different Nuclear Energy Development Scenarios

Exploring the Factors Influencing Expansion of Nuclear Energy in Croatia

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

PCA Benchmark Analysis with ADVANTG3.0.1. and MCNP6.1.1b Codes

Student Polling on Nuclear Energy and Radioactive Waste Management

Ispitivanje studentskog mnijenja o nuklearnoj energiji i radioaktivnom otpadu

PARTISN5.97 Code Verification Using keff Analytical Benchmarks

Total Ambient Dose Equivalent Neutron Buildup Factor Calculation Using TART

PCA Benchmark Analysis with ADVANTG3.0.1. and MCNP6.1.1b Codes

Ispitivanje i analiza javnog mnijenja u Republici Hrvatskoj o nuklearnoj energiji i radioaktivnom otpadu

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 DOCPAGANSA GUI and Control Module

National Survey on Nuclear Energy and Radioactive Waste in Croatia

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

Ispitivanje i analiza javnog mnijenja o izvorima energije

The potential of fission nuclear energy in resolving global climate change

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

RESEARCH AND DEVELOPMENT OF POINT-KERNEL METHOD APPLICATION IN RADIATION SHIELDING

Boration modeling of the PWR biological shield using SCALE6.1 hybrid shielding methodology

Application of Support Vector Regression on Neutron Buildup Factors

Nadogradnja NEMIS portala 2014

Molten Salt Thorium Reactor - A Promising Nuclear Technology to Stop Global Warming

A View on the Future of Nuclear Fission Energy

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

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

Nastavak ispitivanja i analize javnog mnijenja o nuklearnoj energiji

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

Lattice Codes Pin Power Prediction Comparison

Xenon Correction in Homogenized Neutron Cross Sections

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

Nadogradnja portala NEMIS

Perspektiva nuklearne energetike nakon nesreće u Fukushimi

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”

The potential of fission nuclear power in resolving global climate change under the constraints of nuclear fuel resources and once-through fuel cycles

Editorial Selected Papers from TopSafe 2008: Safety at Nuclear Installations

On the Potential of Nuclear Fission Energy for Effective Reduction of Carbon Emission Under the Constraint of Uranium Resources Use without Spent Fuel Reprocessing

Spectral Codes Pin Power Prediction Comparison

Prediction Capabilities of Spectral Codes DRAGON, FA2D, NEWT

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

Learning Support Vector Regression Models for Fast Radiation Dose Rate Calculations

Upgrade of the FUMACS 2005 Code Package

Upgrade of FUMACS Code Package for Modeling of NGF and Gadolinium, Final Report

Nadogradnja informatičkog portala NEMIS - Nuklearna energija mistika i stvarnost

Sensitivity Studies of Fuel Pin Temperature for PWR Fuel Assemblies Containing Burnable Absorbers

Koncept elektroenergetski nezavisnog otoka u Hrvatskoj - preliminarna studija otoka Visa

Informacijski portal o nuklearnoj energiji NEMIS - nuklearna energija; mistika i stvarnost

Sufficiency of the Nuclear Fuel

Availability of nuclear fuel for long-term expansion of nuclear power

FA2D Prediction Capability for NPP Krsko Fuel Assembly Calculation

Verification of FA2D Prediction Capability Using Fuel Assembly Benchmark

Influence of NPP Krško Core Nuclear Characteristics on RCCA Ejection Accident

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

Ispitivanje i analiza javnog mnijenja o nuklearnoj energiji

Rješeni zadaci iz mehanike i topline, VIII promijenjeno izdanje

Nuklearna energija i okoliš

Support vector regression model for the estimation of γ -ray buildup factors for multi-layer shields

Neutroničko modeliranje nuklearnog goriva koje sadrži integralne sagorive apsorbere

Pregled statusa nuklearne energetike u EU i SAD, te prikladnost pojedinih tehnologija za RH

New Features Implemented in FUMACS 2005 Code Package and Future Perspectives in Development of the New Versions

Analiza nabave nuklearnog goriva za NE Krško

Gastric pentadecapeptide BPC 157 - effective therapy of muscle crush injury in rat, given intraperitoneally or applied locally as a cream

BPC 157 accelerates healing of transected rat quadriceps muscle

IRIS - Napredni integralni nuklearni reaktor modularne izvedbe

Application of Support Vector Regression in Estimation of Buildup Factors for Double-Layered Shields

Analiza dugoročnog smještaja nisko i srednje aktivnog otpada u NE Krško

Modelling of Chashma NPP Reactor Core Using FUMACS Computer Code Package

Depletion Modeling of Integral Burnable Absorbers Containing Enriched Boron

Modeling of CHASHMA NPP Reactor Core Using FUMACS Computer Code Package

Three-Batch Reloading Scheme for IRIS Reactor Extended Cycles

Tehno-ekonomska optimizacija odlaganja ozračenog goriva u NE Krško u redovnom i produljenom životnom vijeku

Ekonomsko-energetska opravdanost i tehničke mogućnosti uvođenja 18-mjesečnog radnog ciklusa za NE Krško

Techno-Economical Aspects of Ultra Long Working Cycles

IRIS Core Criticality Calculations

Tehno-ekonomski aspekti ultra dugih radnih ciklusa

Neutroničko modeliranje jezgre IRIS reaktora

Analiza prijelaznih radnih ciklusa NE Krško u uvjetima povećane snage

Calculation of Core Design Benchmark 44 for IRIS Reactor Using Modified CORD-2 Code Package

Design of a Four-Year Straight-Burn Core for the Generation IV IRIS Reactor

Design Of A Four-Year Straight-Burn Core For The Generation-IV Iris Reactor

Design Of A Four-Year Straight-Burn Core For The Generation-IV Iris Reactor

Core Design Calculations of IRIS Reactor Using Modified CORD-2 Code Package

Upgrade Of The Fumacs Code Package

Radiation Dose Evaluation for Hypothetical Accident with Transport Package Containing Iridium-192 Source

Utjecaj tehničkih i financijskih ograničenja odlaganja visoko radioaktivnog otpada na razvoj nuklearne energetike

Upgrade of the FUMACS Code Package

Model of a Dry Storage Facility for a Medium Nuclear Power Plant

Modernizacija paketa računalskih programa FUMACS

DEVELOPMENT OF POWER REACTOR SAFETY ANALYSES COUPLED SYSTEM FOR PERSONAL COMPUTER ENVIRONMENT

THERMAL-HYDRAULIC MODELING OF RERACKED SPENT FUEL POOL

Thermal-Hydraulic Modeling of Reracked Spent Fuel Pool

Investigating a Possibility to Extend an Operating Cycle Length of NPP Krško

Radiological Implications of Spent Fuel Pool Capacity Increase by Spent Fuel Consolidation

Utjecaj mogućnosti povećanja kapaciteta bazena za istrošeno gorivo NE Krško uz pretpostavku gušćeg smještaja goriva i odgora istrošenog goriva na brzine doza

Proračun štita spremišta za privremenu pohranu dotrajalih parogeneratora NE Krško

DEVELOPMENT OF POWER REACTOR SAFETY ANALYSES COUPLED SYSTEM FOR PERSONAL COMPUTER ENVIRONMENT

Radiation Dose Rates in the Vicinity of the NPP Krško Spent Fuel Pool

Gospodarenje gorivom u jezgri reaktora NE Krško u uvjetima predviđenog povećanja snage reaktora nakon zamjene parogeneratora

Analiza moderatorskog temperaturnog koeficijenta jezgre NE Krško u uvjetima povećanja snage

Investigating a possibility to implement 24-month cycle in NPP Krško

Equilibrium cycles of NPP Krško after power uprate

Recent improvements in the design and manufacture of LWR fuel

Investigating a possibility to implement 24-month cycle in NPP Krško

Equilibrium Cycles of NPP Krško after Power Uprate

RELAP5/mod3.2 - QUABOX/CUBBOX-HYCA Coupling

Reracking Possibilities of the NPP Krško Spent Fuel Pool

Reracking Possibilities of the NPP Krško Spent Fuel Pool

Razvoj metoda i programa za proračun štitova od nuklearnog zračenja

Consolidation of spent fuel rods as an option to increase the capacity of spent fuel pool

Analiza 24 mjesečnog radnog ciklusa NE Krško u uvjetima povećanja snage

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

RELAP5/Mod3.2 - Quabox/Cubbox-Hyca Coupled Code

Analiza tehničkih i energetskih elemenata značajnih za uređenje statusa NE Krško

Impact of burnup credit on the NPP Krško spent fuel pool criticality

Impact of Burnup on the NPP Krško Spent Fuel Pool Criticality

Analiza pohrane istrošenog goriva akumuliranog tijekom čitavog radnog vijeka NE Krško u postojećem bazenu za istrošeno gorivo

Capability of the QUABOX/CUBBOX-ATHLET Coupled Code System

Procjena individualnih rizika na području Zagreba od normalnog pogona NE Krško

Procjena rizika od energetskih i drugih kompleksnih gospodarskih sustava na području Grada Zagreba (1)

Procjena rizika od energetskih i drugih kompleksnih gospodarskih sustava na području Grada Zagreba (2)

Konceptualna studija privremenog odlagališta istrošenog goriva na lokaciji nuklearne elektrane

Case Study Zagreb Project - Main Experiences and Results

Procjena rizika za pučanstvo Grada Zagreba od normalnog pogona NE Krško

Procjena ekoloških posljedica i rizika od prijevremenog zatvaranja nuklearne elektrane Krško

Procjena ekoloških posljedica zatvaranja NE Krško

Investigation of intermediate conversion pressurized water reactor for small or medioum nuclear systems

Razmatranje mogućnosti suhog skladištenja istrošenog goriva na lokaciji NE

Reactor Safety Research Applied to NPP Krško in 1988/1989

Nuklearni gorivni ciklusi

Tecno-economic considerations for a small or medium nuclear system built within a limited time interval

Analiza, provjera i proračun štitova za odlaganje radioaktivnog otpada

Modeliranje prelazne pojave nekontroliranog smanjenja koncentracije borne kiseline za NE Krško

Neke mogućnosti smanjenja troškova goriva kod lakovodnih (PWR)i teškovodnih reaktora.

Proračun štita za gama zračenje iz srednje aktivnog otpada nuklearne elektrane

Analiza prijelazne pojave nekontroliranog smanjenja koncentracije borne kiseline

IAEA Coordinated Research Programme on Requirements for Future Application of Advanced Reactors, Second Annual Progress Report

A case study of the effect of advanced fuel cycles and improvements in PWR and PHWR reactors on the resource requirements within small or medium nuclear power programme

Analiza prijelaznih pojava brzog povećanja reaktivnosti

IAEA Coordinated Research Programme on Requirements for Future Application of Advanced Reactors, Progress Report, September 1985

Analiza prijelazne pojave nekontroliranog izvlačenja banke kontrolnih štapova PWR reaktora pri punoj snazi

Analiza prijelaznih pojava nekontroliranog izvlačenja banke kontrolnih štapova na punoj snazi i izbacivanja snopa kontrolnih štapova