0000000001110051

AUTHOR

Pietro Agostini

showing 2 related works from this author

WCLL breeding blanket design and integration for DEMO 2015: status and perspectives

2017

Abstract Water-cooled lithium-lead breeding blanket is considered a candidate option for European DEMO nuclear fusion reactor. ENEA and the linked third parties have proposed and are developing a multi-module blanket segment concept based on DEMO 2015 specifications. The layout of the module is based on horizontal (i.e. radial-toroidal) water-cooling tubes in the breeding zone, and on lithium lead flowing in radial-poloidal direction. This design choice is driven by the rationale to have a modular design, where a basic geometry is repeated along the poloidal direction. The modules are connected with a back supporting structure, designed to withstand thermal and mechanical loads due to norma…

Neutron transportComputer scienceBlanket7. Clean energy01 natural sciencesbreeding blanket; CFD; DEMO; WCLL010305 fluids & plasmaslaw.inventionlaw0103 physical sciencesDesign choiceGeneral Materials Science010306 general physicsWCLL Breeding blanket DEMOSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringWCLL Breeding blanket DEMObusiness.industryMechanical EngineeringLead systemPressurized water reactorFusion powerModular designNuclear Energy and EngineeringSystems engineeringbusinessTransport systemFusion Engineering and Design
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The European contribution to the development and validation activities for the design of IFMIF lithium facility

2013

The International Fusion Materials Irradiation Facility (IFMIF) is an accelerator-driven intense neutron source where candidate materials for fusion reactors will be tested and validated. The high energy neutron flux is produced by means of two deuteron beams (total current of 250 mA, energy of 40 MeV) that strikes a liquid lithium target circulating in a lithium loop of IFMIF plant. The European (EU) contribution to the development of the lithium facility comprises five procurement packages, as follow: (1) participation to the experimental activities of the EVEDA lithium test loop in Oarai (Japan); (2) study aimed at evaluating the corrosion and erosion phenomena, promoted by lithium, for …

Mechanical EngineeringNuclear engineeringLithium testRemote handlingchemistry.chemical_elementInternational Fusion Materials Irradiation FacilityFusion powerLithiumLithium;Remote handling;IFMIF;Corrosion;Target assembly;PurificationCorrosionNuclear Energy and EngineeringchemistryNeutron fluxTarget assemblyIFMIFNeutron sourceEnvironmental scienceGeneral Materials ScienceLithiumPurification methodsEngineering design processSettore ING-IND/19 - Impianti NucleariPurificationCivil and Structural EngineeringIFMIF Target assembly Remote handling Lithium Corrosion Purification
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