A5048007273- Fusion materials and technologies
- Magnetic confinement fusion research
- Superconducting Materials and Applications
- Nuclear reactor physics and engineering
- Nuclear Materials and Properties
- Nuclear Physics and Applications
- Particle accelerators and beam dynamics
- Technology Assessment and Management
- Systems Engineering Methodologies and Applications
- Graphite, nuclear technology, radiation studies
- Diverse Scientific and Engineering Research
- Radiation Detection and Scintillator Technologies
- Nuclear and radioactivity studies
- Multi-Criteria Decision Making
- Gamma-ray bursts and supernovae
- BIM and Construction Integration
- Quality Function Deployment in Product Design
- Manufacturing Process and Optimization
- Safety Systems Engineering in Autonomy
- Spacecraft and Cryogenic Technologies
- Astrophysics and Cosmic Phenomena
- Model-Driven Software Engineering Techniques
- Electromagnetic Launch and Propulsion Technology
- Mechanical and Thermal Properties Analysis
- Engineering Education and Technology
University of Trieste
2020-2024
Consorzio CREO (Italy)
2020-2024
National Agency for New Technologies, Energy and Sustainable Economic Development
2015-2022
University of Naples Federico II
2015-2021
Istituto per il Rilevamento Elettromagnetico dell'Ambiente
2019-2020
Culham Science Centre
2017
United Kingdom Atomic Energy Authority
2017
Engineering (Italy)
2017
In a power plant scale fusion reactor, huge amount of thermal produced by the reaction and external heating must be exhausted through narrow area divertor targets. The targets withstand intense bombardment diverted particles where high heat fluxes are generated erosion takes place on surface. A considerable volumetric nuclear also exhausted. To cope with such an unprecedented exhaust challenge, highly efficient cooling capacity is required. Furthermore, fulfill other critical functions as...
Plasma exhaust has been identified as a major challenge towards the realisation of magnetic confinement fusion. To mitigate risk that single null divertor (SND) with high radiation fraction in scrape-of-layer (SOL) adopted for ITER will not extrapolate to DEMO reactor, EUROfusion consortium is assessing potential benefits and engineering challenges alternative configurations. Alternative configurations could be readily design include X (XD), Super-X (SXD), Snowflake (SFD) double (DND). The...
Since 2014 preconceptual design activities for European DEMO divertor have been conducted as an integrated, interdisciplinary R&D effort in the framework of EUROfusion Consortium. Consisting two subproject areas, 'Cassette' and 'Target', this project has objective to deliver a holistic concept together with key technological solutions materialize design. In paper, brief overview on recent results from is presented. subproject, overall cassette system engineered based load analysis...
A physics and engineering analysis of alternative divertor configurations is carried out by examining benefits problems comparing the baseline single null solution with a Snowflake, an X- Super-X divertor. It observed that can provide margin resilience against large power fluctuations, but their has intrinsic difficulties, especially in balance between structural solidity accessibility components when specific poloidal field coil positioning poses further constraints. hybrid proposed as...
One of the fundamental input parameters required for thermo hydraulic and structural design a divertor cassette is operation temperature range. In current activities to develop European DEMO in frame EUROfusion, reduced activation steel EUROFER97 was chosen as material body considering its low long-term superior creep swelling resistance under neutron irradiation (You et al., 2016) [1]. For specifying an range (i.e. cooling condition) various, often conflicting requirements have be...
Abstract The paper presents an overview of the design status Radial Neutron Camera (RNC), that, together with Vertical Camera, will provide, through reconstruction techniques applied to measured line-integrated neutron fluxes, time resolved measurement ITER and α-source profile (i.e. emissivity, neutrons emitted per unit volume). RNC is composed two subsystems, In-Port Ex-Port located, respectively, inside outside Plug Equatorial Port #01. subsystem in a more advanced stage since it has...
The Radial Neutron Camera is an ITER diagnostic designed to measure the un-collided 14 MeV and 2.5 neutrons from deuterium-tritium (DT) deuterium-deuterium (DD) fusion reactions, through array of detectors covering a poloidal plasma section along collimated Lines Of Sight (LOS). It composed by two fan-shaped collimating structures viewing radially vertical slots in shielding module Equatorial Port 1: In-Port RNC, devoted edge coverage, Ex-Port core coverage. This paper presents overview...
This paper presents the pre-conceptual design activities conducted for European DEMO divertor, focusing on cassette and Plasma Facing Components (PFC) integration. Following systems engineering principles, a systematic method, Iterative Participative Axiomatic Design Process (IPADeP), has been adopted. Basing Design, IPADeP supports early conceptual of complex systems. The work moved from geometrical interface constraints imposed by 2015 configuration model. Then, since different materials...
In the context of EUROfusion activities for development DEMO reactor project, divertor design is a major challenge. It must sustain very high heat, ion particle and neutron fluxes allowing, at same time, shielding vacuum vessel pumping reducing plasma pollution. The conceptual based on use EUROFER97 cassette body, while tungsten monoblocks bonded to CuCrZr pipes are used plasma-facing targets. was selected considering its reduced long-term activation superior creep swelling resistance under...
In the EU DEMO design (Romanelli, 2012; Federici et al., 2014), due to large number of complex systems inside tokamak vessel it is vital importance address in-vessel integration at an early stage in process. design, after a first phase which different have been developed independently based on defined baseline configuration, effort has made define interface requirements and propose strategies for mechanical auxiliary heating fuelling into Vacuum Vessel Breeding Blanket. This work presents...
This paper presents eligere, a new open-source distributed software platform for group decision making in engineering design. It is based on the fuzzy analytical hierarchy process (fuzzy AHP), multiple criteria method used selection processes to rank discrete set of alternatives with respect some evaluation criteria. eligere built following paradigm cyber-physical systems. provides several features interest problems: web-application where experts express their opinion using natural language,...
The Iterative and Participative Axiomatic Design Process (IPADeP) deals with the early conceptual design stage of complex mechanical assemblies. It provides a systematic approach based on theory Product Development Lifecycle aims to minimize risks related uncertainty incompleteness requirements, considering that requirements will be refined completed during process. IPADeP has an iterative nature is focused experience people involved in functional parameters are conceived through...