A5023807333- Nuclear Engineering Thermal-Hydraulics
- Nuclear reactor physics and engineering
- Nuclear Materials and Properties
- Heat Transfer and Boiling Studies
- Heat transfer and supercritical fluids
- Risk and Safety Analysis
- Heat Transfer and Optimization
- Nuclear and radioactivity studies
- Combustion and Detonation Processes
- Computational Fluid Dynamics and Aerodynamics
- Nuclear Physics and Applications
- Heat Transfer and Numerical Methods
- Advanced Control Systems Optimization
- Heat Transfer Mechanisms
- Safety Systems Engineering in Autonomy
- Refrigeration and Air Conditioning Technologies
- Radiative Heat Transfer Studies
- Superconducting Materials and Applications
- Iron and Steelmaking Processes
- Software Reliability and Analysis Research
- Combustion and flame dynamics
- Induction Heating and Inverter Technology
VTT Technical Research Centre of Finland
2004-2024
Sapienza University of Rome
2023
An approach for integrated transient simulation of a BFB boiler furnace and the coupled steam cycle is presented. The simulated with in-house CFD models implemented in ANSYS Fluent® software. control loops dynamic process software Apros®. paper describes steps taken to couple modeling tools discusses way numerical solutions can proceed unison. demonstrated commercial boiler. A fast load change situation was selected as test case. carried out behavior during analyzed. Critical properties...
The EU-funded ELSMOR (Towards European Licencing of Small Modular Reactors) project seeks to design methods and tools for stakeholders assess verify Light Water SMRs' safety when installed across Europe. Within the project, an experimental facility has been built at SIET (Piacenza, Italy) test a passive heat removal system. system is based on natural circulation, with plate-type Compact Steam Generator (CSG) as source in-pool condenser sink. An campaign conducted investigate effect different...
In the hypothetical Large-Break Loss Of Coolant Accident (LBLOCA), rapid depressurization of reactor primary circuit causes loads on internals. This paper presents numerical simulations a HDR experiment, where LBLOCA pressurized water due to sudden pipe break in loop was studied. Fluid-Structure Interaction (FSI) phenomena caused by flexibility core barrel were studied particular. Star-CD Computational Fluid Dynamics (CFD) code and ABAQUS structural analysis used for three-dimensional...
In this article, we study a large-break loss of coolant accident (LBLOCA) where guillotine break one the main pipes occurs near reactor pressure vessel (RPV). This initiates wave which propagates inside RPV. The simulation bidirectional fluid-structure interaction phenomena has been found to be important for accurate prediction resulting deformation and loads. fully coupled results are validated against German HDR (Heißdampfreaktor) experiments. computational fluid dynamic (CFD) software...