I2S-LWR Concept Update

NPP Krško DVI LOCA Calculation using RELAP5/mod 3.3 and FRAPTRAN to Assess UFC Modification Influence

Optimization of OPDT Protection for Overcooling Accidents

The Pioneering Role of IRIS in Resurgence of Small Modular Reactors

Analysis of Rod Withdrawal at Power (RWAP) Accident using ATHLET Mod 2.2 Cycle A and RELAP5/mod 3.3 Codes

Analysis of Steam Generator Tube Rupture (SGTR) Accident for NPP Krško

Perspektiva nuklearne energetike nakon nesreće u Fukushimi

Coupled Code Calculation of Rod Withdrawal at Power Accident

Limiting Conditions for Nuclear Power Plant Competitiveness vs. Fossil and Wind Plants

Comparison of Different Energy Options for Future Electricity Generation

Condensation within Small Compartments during Design Basis Accidents

Editorial Selected Papers from TopSafe 2008: Safety at Nuclear Installations

RELAP5 Modeling of PWR Reactor RTD Bypass

Small and medium reactors in the countries energy security, IRIS example

Upravljanje životnim vijekom kabela kao dio programa produljenja životnog vijeka nuklearne elektrane

Usporedba ukupnih proizvodnih troškova električne energije iz TE na ugljen, TE na plin i nuklearnih elektrana

Nuclear Power Plant as a Potential Option for Sustainable Development of Electrical Power Generation in Croatia

Nuclear power plant as a potential option for sustainable development of electrical power generation in Croatia

Potential advantages and disadvantages of sequential building small nuclear units instead of a large nuclear power plant

Application of the System Thermal-Hydraulics Codes for the Evaluation of the Operating PWR Plant Safety in the Shutdown Conditions

Analysis of In-Vessel Severe Accident Phenomena in NPP Krško

IRIS - AN ADVANCED, GRID-APPROPRIATE PWR FOR NEAR-TERM DEPLOYMENT

Definiranje mjesta i uloge hidrometeoroloških podataka u tržišnom funkcioniranju elektroprivrednih poduzeća

IRIS (International Reactor Innovative and Secure) – Progress in Development, Licensing and Deployment Activities

Anticipated Transient Without Scram Analysis for NPP Krško using Point Kinetics Option and Coupled Code

IRIS – Progress in Licensing and Toward Deployment

Moguća uloga naprednog nuklearnog reaktora IRIS u hrvatskom elektroenergetskom sustavu

THE IRIS Consortium: International Cooperationa in Advanced Reactor Development

IRIS (International Reactor Innovative and Secure) - Design Overview and Deployment Prospects

Analysis of future nuclear power plants competitive investment costs with stochastic methods

IRIS - napredni nuklearni reaktor srednje snage s poboljšanom sigurnošću i ekonomičnošću

IRIS - napredni nuklearni reaktor srednje snage s poboljšanom sigurnošću i ekonomičnošću

IRIS Design Overview and Status Update

IRIS - NAPREDNI NUKLEARNI REAKTOR SREDNJE SNAGE S POBOLJŠANOM SIGURNOŠĆU I EKONOMIČNOŠĆU

IRIS - Napredni integralni nuklearni reaktor modularne izvedbe

RCP Seal Leakage Analysis During Station Blackout for NPP Krško

Nuclear Option in Countries with Small and Medium Electricity Grid

Radiation Dose Specification for Equipment Qulaification

Coupled RELAP5/GOTHIC Model for IRIS SBLOCA Analysis

Use of the Deterministic Safety Analyses in Support to the NPP Krško Modifications

Analysis of future Nuclear Power Plants competitiveness by using stochastic methods

LOCA Analysis of the IRIS Reactor

RELAP5 Assessment Using ISP38 Data

Technical Support Centre and its Role in a Nuclear Emergency Response Preparedness

Bethsy Nodalization Study During Mid-Loop Operation

Elektrane i okoliš

Proceedings International Conference "Nuclear Option in Countries with Small and Medium Electricity Grids"

NPP KRŠKO CONTAINMENT RESPONSE FOLLOWING MAIN STEAM LINE BREAK

Feasibility analisys of wind-energy utilization in Croatia

New Structure of Emergency Response Plan in Croatia

Proceedings International Conference "Nuclear Option in Countries with Small and Medium Electricity Grids"

Proizvodnja električne i optičke opreme

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

RELAP5/mod2 Code for Win95/NT Environment with F90 Capabilities

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

Proceedings International Conference "Nuclear Option in Countries with Small and Medium Electricity Grids"

RELAP5/mod2 Analysis of Inadvertent Closing of the Main Steam Isolation Valve in NPP Krško

Mathematical modelling of transient temperature fields in cylinders by transfer functions

Nuklearne elektrane

Modeliranje prijelaznih temperaturnih polja u strukturama pomoću prijenosnih funkcija

Neki pokazatelji dinamičke stabilnosti nuklearnog reaktora

Procjena ekoloških posljedica zatvaranja NE Krško

Novi aspekt u analizi posljedica loma cijevi napojne vode u nuklearnoj elektrani

Determinističke i probabilističke metode u analizi sigurnosti nuklearne elektrane Krško

Analiza sigurnosti i pouzdanosti sistema i komponenata nuklearne elektrane

Analiza sigurnosti i pouzdanosti sistema i komponenata nuklearne elektrane

Analiza promjene pogonskih parametara NE Krško u slučaju naglog rasterećenja

Razrada matematičkog modela za kvantitativnu analizu komponenata nuklearne elektrane

Prilog metodi za numeričku analizu prenosnih funkcija toplinskih procesa u izmjenjivačima topline

Analiza sigurnosti i pouzdanosti nuklearnih elektrana uz primjenu računskih programa

Analiza, sistematiziranje i razvitak metoda kod istraživanja pouzdanosti komponenata i sistema nuklearne elektrane - II. dio (145 str.)

Analiza sigurnosti i pouzdanosti komponenata i sistema nuklearne elektrane

Analiza, sistematiziranje i razvitak metoda kod istraživanja pouzdanosti komponenata i sistema nuklearne elektrane - I. dio

Napajanje električnom energijom na novoj pruzi Rijeka - Zagreb