Search results for "conceptual design"

showing 3 items of 43 documents

Conceptual Design and Modeling of the Toroidal Field Coils Circuit of DTT

2020

Italian Divertor Tokamak Test (DTT) facility is part of the general European programme on the fusion research. Its specific role is to cover the gap on the power exhaust for the future DEMOstration power plant (DEMO). This tokamak will be built and installed in Italy at Frascati ENEA laboratories. The paper describes the Toroidal Field (TF) coils circuit powered by a TF power supply that feeds in series 18 toroidal superconducting magnets and the development of three software models in order to validate the adopted technical solutions in term of maximum voltage and maximum current stress on each power device/component, due to both the operating and fault conditions, and across TF coils.

TokamakToroidPower stationComputer scienceNuclear engineeringDivertorToroidal Field Superconducting MagnetsCrowbar ProtectionSuperconducting magnetFault (power engineering)Converter Transformer01 natural sciences010305 fluids & plasmaslaw.inventionSettore ING-IND/33 - Sistemi Elettrici Per L'EnergiaSettore ING-IND/31 - ElettrotecnicaAC/DC ConverterConceptual designlaw0103 physical sciences010306 general physicsVoltage
researchProduct

Progress of the conceptual design of the European DEMO breeding blanket, tritium extraction and coolant purification systems

2020

Abstract In the frame of the EUROfusion consortium activities the Helium Cooled Pebble Bed (HCPB) and the Water Cooled Lithium Lead (WCLL) concepts are being developed as possible candidates to become driver Breeding Blanket (BB) for the EU DEMO, which aims at the tritium self-sufficiency and net electricity production. The two BB design options encompass water or helium as coolants and solid ceramic with beryllium/beryllides or PbLi as tritium breeder and neutron multipliers. The BB segments have evolved towards a more stable conceptual design taking into account multiple feasibility aspects and requirements imposed by interfacing systems. Possible solutions to improve shielding capabiliti…

TokamakTritium extraction and removalNuclear engineeringchemistry.chemical_elementIsolation valveBlanket7. Clean energy01 natural sciences010305 fluids & plasmaslaw.inventionBreeder (animal)Conceptual designlaw0103 physical sciencesGeneral Materials Science010306 general physicsSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringMechanical EngineeringCoolant purificationCoolantElectricity generationNuclear Energy and EngineeringchemistryEnvironmental scienceBreeding blanketBeryllium
researchProduct

Recent Progress in the WCLL Breeding Blanket Design for the DEMO Fusion Reactor

2018

The water-cooled lithium-lead (PbLi) breeding blanket is one of the candidate systems considered for the implementation in the 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 as the coolant, and EUROFER as the structural material. The current design is based on the single module segment approach and follows the requirements of the DEMO-2015 baseline design. The module is constituted by a basic toroidal-radial cell that is recursively repeated along the poloidal direction where the liquid metal flows along a radial-poloidal path. The heat generated by the fusion r…

liquid metal technologyNuclear and High Energy PhysicsLiquid metalPower stationLayoutComputer scienceNuclear engineeringNeutronBlanket01 natural sciences7. Clean energy010305 fluids & plasmasBreeding blanket (BB); Demonstration Power Plant (DEMO); fusion reactor design; liquid metal technology; Nuclear and High Energy Physics; Condensed Matter PhysicsBreeding blanket (BB)Conceptual design0103 physical sciencesliquid metal technology.Nuclear fusion010306 general physicsSettore ING-IND/19 - Impianti NucleariNuclear and High Energy PhysicMetalDemonstration Power Plant (DEMO)Fusion powerCondensed Matter PhysicsManifoldbreeding blanket; DEMO; fusion reactor design; liquid metal technologyCoolantElectricity generationCoolantPower generationfusion reactor designIEEE Transactions on Plasma Science
researchProduct