Search results for "Remote handling"

showing 2 items of 2 documents

Design, manufacturing and testing of a fast disconnecting system for the European target assembly concept of IFMIF

2013

The International Fusion Materials Irradiation Facility (IFMIF) will be equipped with a lithium target assembly to produce the required neutron flux for the irradiation of candidate fusion materials up to a damage rate of 100 dpa (cumulated damage in five years). The present European target assembly design is based on the so called replaceable backplate bayonet concept that was developed with the objective to simplify the maintenance operations for its refurbishment/replacement and to reduce the material for disposal as well. To this purpose it was also conceived to be attached to the lithium pipes and to the beam line by means of remotely operated connections based on clamped flanges with …

EngineeringRemote handling;target assembly;FDS;IFMIFbusiness.industryGasketMaintainabilityRemote handlingMechanical engineeringFDSInternational Fusion Materials Irradiation FacilityStructural engineeringtarget assemblyWorking conditionNeutron fluxInsulation systemIFMIFAssembly designbusinessSettore ING-IND/19 - Impianti Nucleari
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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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