A5041368537- Nuclear reactor physics and engineering
- Nuclear Materials and Properties
- Nuclear and radioactivity studies
- Nuclear Engineering Thermal-Hydraulics
- Graphite, nuclear technology, radiation studies
- Nuclear Physics and Applications
- Risk and Safety Analysis
- Non-Destructive Testing Techniques
- Spacecraft and Cryogenic Technologies
- Global Energy and Sustainability Research
- Climate Change Policy and Economics
- Combustion and Detonation Processes
- Regional Development and Management Studies
- Fault Detection and Control Systems
- Superconducting Materials and Applications
- Distributed and Parallel Computing Systems
- Particle accelerators and beam dynamics
- Agricultural Engineering and Mechanization
- Fire dynamics and safety research
- Software Reliability and Analysis Research
- Advancements in Semiconductor Devices and Circuit Design
- Mining and Industrial Processes
- Pulsed Power Technology Applications
- Radioactivity and Radon Measurements
- Global Energy Security and Policy
University of Zagreb
2009-2023
Institut de Radioprotection et de Sûreté Nucléaire
2022
Faculty of Electrical Engineering and Computing in Zagreb
2008
Rudjer Boskovic Institute
1992
IRIS is an advanced integral pressurized water reactor, developed by international consortium led Westinghouse. The licensing process requires the execution of and separate effect tests on a properly scaled reactor simulator for concept, safety system verification, code assessment. Within framework Italian R&D program Nuclear Fission, managed ENEA supported Ministry Economic Development, SPES3 facility under design will be built operated at SIET laboratories. simulates primary,...
The integrity of the containment will be challenged during a severe accident due to pressurization caused by accumulation steam and other gases possible ignition hydrogen carbon monoxide. Installation passive filtered venting system autocatalytic recombiners allows control pressure, radioactive releases, concentration flammable gases. Thermal hydraulic analysis equipped with dedicated safety systems after hypothetical station blackout event is performed for two-loop pressurized water reactor...
An Italian MSE R&D programme on Nuclear Fission is funding, through ENEA, the design and testing of SPES3 facility at SIET, for IRIS reactor simulation. a modular, medium size, advanced, integral PWR, developed by an international consortium utilities, industries, research centres universities. simulates primary, secondary containment systems IRIS, with 1:100 volume scale, full elevation prototypical thermal-hydraulic conditions. The RELAP5 code was extensively used in support to...
A comprehensive uncertainty analysis in the event of a severe accident two-loop pressurized water reactor is conducted using an package integrated ASYST code. The plant model based on nuclear power (NPP) Krško, Westinghouse-type plant. station blackout scenario with small break loss coolant analyzed, and all processes in-vessel phase are covered. best estimate plus (BEPU) methodology probabilistic propagation input used. uncertain parameters selected their impact safety criteria, operation...
A comprehensive analysis of the double ended main steam line break (MSLB) accident assumed to occur in Babcock & Wilcox Three Mile Island Unit 1 (TMI-1) has been carried out at Dipartimento di Ingegneria Meccanica, Nucleare e della Produzione University Pisa, Italy, cooperation with Zagreb, Croatia. The overall activity completed within framework participation Organization for Economic Cooperation and Development-Committee on Safety Nuclear Installations-Nuclear Science Committee pressurized...
Abstract The aim of this paper is to present a fractional scaling analysis (FSA) application for system with interacting components where multiple figures merits need be respected during complex transient accident scenario several consecutive time sequences. This presents FSA the International Reactor Innovative and Secure (IRIS) reactor Simulatore Pressurizzato per Esperienze di Sicurezza 3 (SPES3) integral effects test (IET) facility. was applied small break loss coolant (SBLOCA) on direct...
Fault tree is a common approach in probabilistic risk assessment of complex engineering systems. Since their introduction, binary decision diagrams proved to be valuable tool for complete quantification hard fault models. As known, the size diagram representation mainly determined by quality selected event ordering scheme. Finding optimal computationally intractable problem, which reason heuristic approaches are applied find reasonable good schemes. The existing method finding schemes...
This paper presents comparison of the Krško Power Plant simplified Spent Fuel Pool (SFP) dose rates using different computational shielding methodologies. The analysis was performed to estimate limiting gamma on wall mounted level instrumentation in case significant loss cooling water. SFP represented with simple homogenized cylinders (point kernel and Monte Carlo (MC)) or cuboids (MC) uranium, iron, water, dry-air as a bulk region materials. pool is divided old new section where one has...
Abstract Renewal of nuclear power programs in countries with modest electricity consumptions and weak electrical grid interconnections has raised the question optimal plants sizes for such countries. The same would be also valid isolated or weakly connected regions within a large country. Building size plant could prevented by technical financial limits. Research have been initiated International Atomic Energy Agency USA (within framework Global Nuclear Partnership (GNEP) program) aim to...
Abstract In this paper, shielding analysis was performed to determine neutron and gamma dose rates around the transfer cask HI-TRAC VW (Holtec International Transfer Cask Variable Weight) loaded with spent fuel assemblies (SFA) from nuclear power plant (NPP) Krsko dry storage (SFDS) campaign one. The is a multilayered cylindrical vessel designed accept multipurpose canister (MPC) during loading, unloading, building. MPC can contain up 37 assemblies. divided into two steps. first step source...
Abstract One of main issues in planning future power system expansion is forecast expected electricity generating costs. Due to the fact that should be extended plants lifetime it best consider and compare levelized cost generated for each candidate plants. The analysis a part studies Croatian system, but valid generally. competitors nuclear are combined cycle natural gas fired whose economy strongly depends upon cost. increase following decades can substantially influence competitiveness...