A5069242549- Nuclear reactor physics and engineering
- Nuclear Materials and Properties
- Graphite, nuclear technology, radiation studies
- Nuclear Engineering Thermal-Hydraulics
- Heat Transfer and Boiling Studies
- Nuclear and radioactivity studies
- Radioactive element chemistry and processing
- Fluid Dynamics and Mixing
- Heat Transfer and Optimization
- Advanced Power Generation Technologies
- Catalytic Processes in Materials Science
- Nuclear Physics and Applications
- Cyclone Separators and Fluid Dynamics
- Catalysis and Oxidation Reactions
- Neural Networks and Applications
- Building materials and conservation
- Dynamics and Control of Mechanical Systems
- Radiative Heat Transfer Studies
- Magnetic confinement fusion research
- Fault Detection and Control Systems
- Energy Load and Power Forecasting
- Catalysis and Hydrodesulfurization Studies
- Particle Dynamics in Fluid Flows
- Heat transfer and supercritical fluids
- Metallurgical Processes and Thermodynamics
Embry–Riddle Aeronautical University
2024
Politecnico di Milano
1999-2013
Ricerca sul Sistema Energetico (Italy)
2003
Fondazione Politecnico di Milano
2002
Dryout phenomena have been experimentally investigated in a helically coiled steam generator tube. The experiences carried out the present work are part of wide experimental program devoted to study GEN III+ innovative nuclear power plant [1].The facility consists an electrically heated AISI 316L stainless steel tube is 32 meters long, 12.53 mm inner diameter, with coil diameter 1m and pitch 0.79 m, resulting total height 8 meters. thermo-hydraulics conditions for dryout investigations...
Two-phase flow regimes are reviewed briefly. A physical model, which is based on the concept that droplet diffusion through a steam boundary layer limiting mechanism for burnout in turbulent flow, described. An equation derived relating to other parameters fog flow. With simplifying assumptions, an order-of-magnitude agreement between analysis and experimental data demonstrated.
IRIS (International Reactor Innovative and Secure) is a light water cooled, 335 MWe power reactor which being designed by an international consortium as part of the US DOE NERI Program. features integral vessel that contains all main coolant system components including core, pumps, steam generators pressurizer. This design approach eliminates large loop piping, thus loss-of-coolant accidents (LOCAs) well individual component pressure vessels supports. In addition, with long-life core...
A deterministic analysis of the IRIS safety features has been carried out by means best-estimate code RELAP (ver. RELAP5 mod3.2). First, main system components were modeled and tested separately, namely: Reactor Pressure Vessel (RPV), modular helical-coil Steam Generators (SG) Passive (natural circulation) Emergency Heat Removal System (PEHRS). Then, a preliminary set accident transients for whole primary systems was investigated. Since project in conceptual phase, reported analyses must be...
The IRIS (International Reactor Innovative and Secure) project has completed the conceptual design phase is moving towards completion of preliminary design, scheduled for end 2002. Several other papers presented in this conference provide details on major aspects design. three most innovative features which uniquely characterize are, descending order impact: 1. Safety-by-design, takes maximum advantage integral configuration to eliminate from consideration some accidents, greatly lessen...
An effective way to reduce the large quantities of Pu currently accumulated worldwide would be use uranium-free fuel in light water reactors (LWRs) so that no new is produced. Such a possibility could provided by an LWR consisting neutronically inert matrix. It may necessary add burnable absorber or thorium reactivity swing during burnup. The methods and data used for analyses have not been tested conjunction with such exotic materials. international exercise has accordingly launched compare...