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
On the Perspective of Nuclear Energy Following the Fukushima Accident
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
Cable aging management as part of the extended nuclear power plant lifespan programme
Comparison of production costs of electrical energy from coal-powered power plants, gas-powered power plants and nuclear power plants
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
Definition of the role and importance of the hydro-meteorological data in the functioning of the electric power utilities on the open market
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
Possible Role of Advanced Nuclear Reactor IRIS in Croatian Power System
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 - advanced medium power nuclear reactor with advanced security and econimics
IRIS - Advanced Medium Power Nuclear Reactor with Improved Safety and Economy
IRIS Design Overview and Status Update
IRIS – ADVANCED MEDIUM POWER NUCLEAR REACTOR WITH IMPROVED SAFETY AND ECONOMY
IRIS - Advanced Integral Nuclear Reactor with Modular Construction
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
Power plants and the environment
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"
Manufacture of electrical and optical equipment
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
Nuclear Power Plants
Modelling of Transient Temperature Fields in Structures with System Transfer Function
Some Dynamic Stability Characteristics of Nuc1ear Reactor
Evaluation of ecological consequences of closing NP Krško
A New Aspect in Analisys of Feedwater Pipe Break Consequences in NPP
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A Contribution to The Method for Numerical Analysis of The Therma1 Process Transfer Functions in The Heat Exchangers
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Electrical Energy Feed on New Railway Rijeka - Zagreb