A5010845120- Fusion materials and technologies
- Nuclear reactor physics and engineering
- Nuclear Materials and Properties
- Nuclear and radioactivity studies
- Nuclear Physics and Applications
- Superconducting Materials and Applications
- Magnetic confinement fusion research
- Graphite, nuclear technology, radiation studies
- Solar and Space Plasma Dynamics
- Particle accelerators and beam dynamics
- Nuclear Engineering Thermal-Hydraulics
- Energetic Materials and Combustion
- Space exploration and regulation
- Solar Radiation and Photovoltaics
- Geophysics and Gravity Measurements
- Fatigue and fracture mechanics
- Radiation Detection and Scintillator Technologies
- Muon and positron interactions and applications
- Powder Metallurgy Techniques and Materials
- Thermoregulation and physiological responses
- Non-Invasive Vital Sign Monitoring
- Hemodynamic Monitoring and Therapy
- Metallurgy and Material Forming
- Boron and Carbon Nanomaterials Research
- Blood properties and coagulation
National Agency for New Technologies, Energy and Sustainable Economic Development
2004-2024
ENEA Brasimone Research Centre
2020-2024
National University of Distance Education
2022
University of Palermo
2012-2019
University of Catania
2005-2017
Arcetri Astrophysical Observatory
1984-1990
The 2014–2016 JET results are reviewed in the light of their significance for optimising ITER research plan active and non-active operation. More than 60 h plasma operation with first wall materials successfully took place since its installation 2011. New multi-machine scaling type I-ELM divertor energy flux density to is supported by principle modelling. relevant disruption experiments modelling reported a set three mitigation valves mimicking setup. Insights L–H power threshold Deuterium...
The water-cooled lithium–lead breeding blanket is a candidate option for the European Demonstration Power Plant (DEMO) nuclear fusion reactor. This concept relies on liquid as breeder–multiplier, pressurized water coolant, and EUROFER structural material. current design based DEMO 2015 specifications represents follow-up of developed in 2015. single-module-segment approach employed. constituted by basic geometry repeated along poloidal direction. power removed means radial–toroidal (i.e.,...
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 scope of the EUFOfusion Work Package Breeding Blanket is to develop a blanket concept for EU DEMO reactor; this includes segments inside Vacuum Vessel and related Tritium Extraction/Removal Systems. In Pre-Concept Design (PCD) Phase, two concepts have been selected as candidates; solid liquid breeder cooled with helium water, respectively. design these systems has adapted plant developed in PCD Phase performances assessed. A large R&D programme implemented evaluate different technologies...
Abstract An overview is presented of the progress since 2021 in construction and scientific programme preparation Divertor Tokamak Test (DTT) facility. Licensing for building has been granted at end 2021. Cat. A radiologic source also 2022. The toroidal field magnet system progressing. prototype 170 GHz gyrotron produced it now under test on FALCON design vacuum vessel, poloidal coils civil infrastructures completed. shape first DTT divertor agreed with EUROfusion to different plasma exhaust...
The water-cooled lithium-lead (PbLi) breeding blanket is one of the candidate systems considered for implementation in European Demonstration Power Plant (DEMO) nuclear fusion reactor. This concept employs PbLi liquid metal as tritium breeder and neutron multiplier, water pressurized at 15.5 MPa coolant, EUROFER structural material. current design based on single module segment approach follows requirements DEMO-2015 baseline design. constituted by a basic toroidal-radial cell that...
The Pre-Concept Design (PCD) of the Balance Plant (BoP) systems EU-DEMO power plant is described in this paper for both breeding blanket (BB) concepts under assessment, namely Water Cooled Lithium Lead (WCLL) BB and Helium Pebble Bed (HCPB) BB. Moreover, results a preliminary evaluation number BoP variants are discussed. This outlines steps design development, highlighting project objectives strategy their achievement very challenging requirements which include, among others, intermittent...
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...
The EU conducted the pre-conceptual design (PCD) phase of demonstration reactor (DEMO) during 2014–2020 under framework EUROfusion consortium. current strategy DEMO is to bridge breeding blanket (BB) technology gaps between ITER and a commercial fusion power plant (FPP) by playing role “Component Test Facility” for BB. Within this strategy, so-called driver blanket, with nearly full in-vessel surface coverage, will aim at achieving high-level stakeholder requirements tritium self-sufficiency...
One of the two most promising Breeding Blanket (BB) concepts to be chosen as driver design EU-DEMO fusion reactor is Water-Cooled Lead Lithium (WCLL) BB. A crucial point this key component cooling BB structural elements and Lithium-Lead alloy, used neutronic multiplier Tritium breeder. Indeed, high flux needed for breeding implies volumetric power affecting Zone (BZ) materials. The current layout employs water-cooled Double Wall Tubes (DWTs) with a C-shaped configuration BZ cooling. Despite...
The Water-Cooled Lead-Lithium (WCLL) is one of the two candidate concepts for Breeding Blanket (BB) DEMO. A Test Module (TBM) together with its Water Cooling System (WCS) going to be installed and tested in ITER reactor. WCS acts as primary cooling circuit TBM module, it designed reproduce water thermodynamic conditions expected at DEMO BB inlet. During last years, ENEA DIAEE Sapienza University Rome have carried out conceptualization Loop (WL) facility, belonging W-HYDRA experimental...
Within the framework of EUROfusion R&D activities an intense research campaign has been carried out at University Palermo, in close cooperation with ENEA Brasimone, order to investigate thermo-mechanical performances DEMO water-cooled lithium lead breeding blanket (WCLL). In particular, attention paid most recent geometric configuration WCLL outboard equatorial module, as designed by project team during 2015, endowed attachment system based on use radial pins, purposely outlined connect...