A5082867462- Fusion materials and technologies
- Nuclear reactor physics and engineering
- Nuclear Materials and Properties
- Magnetic confinement fusion research
- Nuclear Engineering Thermal-Hydraulics
- Metallurgical Processes and Thermodynamics
- Fluid Dynamics and Heat Transfer
- Fluid Dynamics and Vibration Analysis
- Superconducting Materials and Applications
- Ionosphere and magnetosphere dynamics
- Fluid Dynamics and Thin Films
- Lattice Boltzmann Simulation Studies
- Vibration and Dynamic Analysis
- Membrane-based Ion Separation Techniques
- Nanofluid Flow and Heat Transfer
- Electromagnetic Launch and Propulsion Technology
- Fluid Dynamics and Turbulent Flows
- Cyclone Separators and Fluid Dynamics
- Non-Destructive Testing Techniques
- Aerosol Filtration and Electrostatic Precipitation
- Water Systems and Optimization
Sapienza University of Rome
2020-2024
The Water-Cooled Lead–Lithium Breeding Blanket (WCLL BB) is one of the two blanket concept candidates to become driver EU-DEMO reactor. design was enacted with a holistic approach. influence that neutronics, thermal-hydraulics (TH), thermo-mechanics (TM) and magneto-hydro-dynamics (MHD) may have on were considered at same time. This new approach allowed for team create WCLL BB layout able comply different foreseen requirements in terms integration, tritium self-sufficiency, TH TM needs. In...
The water-cooled lead lithium breeding blanket (WCLL BB) is one of two BB candidate concepts to be chosen as the driver EU-DEMO fusion reactor. Research activities carried out in past decade, under umbrella EUROfusion consortium, have allowed a quite advanced reactor architecture achieved. Moreover, significant efforts been made order develop WCLL pre-conceptual design following holistic approach, identifying interfaces between components and systems while respecting system engineering...
Several systems in nuclear fusion reactors utilize liquid metals as working fluids and the design of these cannot overlook magnetohydrodynamics effects arising from interaction between electrically conductive fluid magnetic fields used to confine plasma, since significantly influence flow features. In this context, rigorous studies research activities are imperative provide high–quality numerical data develop precise predictive tools. This work introduces two OpenFOAM solvers outlines their...
Abstract The water-cooled lead lithium (WCLL) and the dual-cooled (DCLL) are two of breeding blanket (BB) concepts that EUROfusion consortium is pursuing in framework development fusion reactor industrial demonstrator DEMO. Both involve use a liquid metal (LM) as working fluid, lead-lithium eutectic alloy (PbLi), due to its excellent thermal properties possibility serve both coolant tritium breeder carrier. Unfortunately, high electrical conductivity LMs, their motion influenced by magnetic...
In the fight against climate change through progress of fusion technology, Affordable, Robust and Compact (ARC) reactor design is under development at Commonwealth Fusion Systems (CFS) Massachusetts Institute Technology (MIT)- Plasma Science Center, in collaboration with Ente Nazionale Idrocarburi (ENI) S.p.A. The features demountable superconducting toroidal field coils a replaceable vacuum vessel immersed Fluorine Lithium Beryllium (FLiBe) molten salt blanket. low-pressure cools divertors...
The breeding blanket is one of the fundamental components a nuclear fusion reactor and responsible for fuel production, generating tritium through neutronic capture reaction between lithium neutrons. Lithium liquid PbLi alloy helium formed as by-product can coalesce into bubbles, two-phase mixture with high-density ratio (ηρ∼O5). These bubbles accumulate stagnate within channels potentially harmful consequences. In this work, interIsoFoam solver OpenFOAM v2012 used to simulate bubble motion...
The transport, permeation and retention of tritium inside nuclear fusion reactors is a topic great interest due to the scarcity isotope, its ease diffusion through materials radioactivity. An accurate balance needed in all fuel cycle, each loss term needs be evaluated detail. In this context, reliable flexible tools evaluate are necessity for development technologies. This work presents OpenFOAM PermeAtion Solver Tritium Analysis Foam (pastaFoam) solver two custom boundary conditions, along...
Magnetohydrodynamic (MHD) phenomena significantly impact the design of magnetic-confinement fusion reactors, particularly in context breeding blankets (BB) utilizing liquid metals (LMs) as working fluids. These effects arise from interaction between electro-conductive flowing metal and magnetic field used for plasma confinement reactor chamber. Induced electrical currents generate Lorentz forces, thereby altering flow behaviour comparison to standard hydrodynamic conditions. For example, MHD...
Liquid metals offer unique properties and their use in a nuclear fusion reactor, both as confined flows free-surface flow, is widely studied the community. The interaction between this conductive fluid tokamak magnetic fields leads to magnetohydrodynamic (MHD) phenomena that influence flow features. To properly design components employ liquid metals, it necessary accurately predict these features, although efforts have been made development, mature code specifically customized simulate MHD...
In the design of magnetic confinement nuclear fusion power plants, breeding blanket (BB) plays a crucial role since it must fulfil key functions such as tritium breeding, radiation-shielding, and removal heat generated by plasma. The latter task is achieved first wall (FW) zone (BZ) cooling systems, which in water-cooled lithium–lead (WCLL) BB employ pressurized water. Different arrangements BZ coolant conduits have been investigated recent past to identify an efficient layout, could meet...
The Water-Cooled Lead Lithium (WCLL) Breeding Blanket (BB) is one of the two leading candidates for implementation as driver blanket in European DEMO reactor, which expected to start operation late 2050s and serve a BB test facility. One main risks associated with current WCLL concept large number welds necessary realize its horizontal (toroidal-radial) breeding zone cooling system stiffening structure, negatively affects reliability. Hence, an alternative variant has been proposed relies on...
The transport, permeation and retention of tritium inside nuclear fusion reactors is a topic great interest due to the scarcity isotope, its ease di usion through materials radioactivity. An accurate balance needed in all fuel cycle, each loss term needs be evaluated detail. In this context, reliable exible tools evaluate are necessity for development technologies. This work presents OpenFOAM PermeAtion Solver Tritium Analysis Foam (pastaFoam) solver two custom boundary conditions, along...