Search results for "International Fusion Materials Irradiation Facility"

showing 5 items of 5 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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Thermo-mechanical analysis of irradiation swelling and design optimization of the IFMIF target assembly with bayonet backplate

2017

Abstract The availability of a high flux neutron source for testing candidate materials under irradiation conditions, which will be typically encountered in future fusion power reactors (ITER, DEMO, FPR), is a fundamental step towards the development of fusion energy. To this purpose, the International Fusion Materials Irradiation Facility (IFMIF) represents the reference option to provide the fusion community with a DEMO-relevant neutron source capable of irradiating samples at a damage rate of up to 20 dpa/fpy (in steel) in a volume of 0.5 l. In the framework of the engineering design activities of IFMIF, ENEA is committed in the design of the lithium target assembly (TA) with removable (…

FusionMaterials scienceMechanical EngineeringReference designNuclear engineeringInternational Fusion Materials Irradiation FacilityIFMIF Target assembly Bayonet backplate Design optimization Swelling analysisFusion power01 natural sciences7. Clean energyFinite element method010305 fluids & plasmasPower (physics)Nuclear Energy and Engineering0103 physical sciencesNeutron sourceGeneral Materials Science010306 general physicsEngineering design processSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringFusion 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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Analytical and Numerical Assessment of Thermally Induced Pressure Waves in the IFMIF-DONES Liquid-Lithium Target

2020

The intended steady-state operation conditions of the International Fusion Materials Irradiation Facility-DEMO Oriented Neutron Source (IFMIF-DONES) target system are based on the D+ beam stationary running at full nominal power (5 MW). Nevertheless, critical situations can occur in the case of unavoidable sudden events like beam trips. The instantaneous variation in the heating power deposited in lithium when the beam is rapidly switched between ON-and OFF-states leads to thermal expansion, which is compensated by the compression of the target material, resulting in locally high pressures and a pressure wave propagating through the target toward the back wall. Besides the tensile stress of…

Nuclear and High Energy PhysicsMaterials sciencepressure wavesNuclear engineeringComputational fluid dynamics (CFD)Numerical assessmentInternational Fusion Materials Irradiation Facility-DEMO oriented neutron source (IFMIF-DONES)Condensed Matter PhysicsLiquid lithiumlithium targetSettore ING-IND/19 - Impianti Nucleari
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Assessment of Fatigue Effects Induced by Fast Beam Transients in the IFMIF-DONES Li Target

2020

One of the crucial steps toward the commercial exploitation of fusion energy is the availability of a high-intensity neutron source able to test and qualify structural materials to be used in future fusion power reactors. The International Fusion Materials Irradiation Facility-DEMO Oriented NEutron Source (IFMIF-DONES) facility, which is currently being designed within the framework of the EUROfusion Consortium, represents the European effort to develop such a neutron source. It employs a liquid lithium target struck by an accelerated deuteron (D+) beam to produce fusion-like neutrons used to irradiate materials samples. So far, a detailed investigation of the thermomechanical behavior of t…

Shock waveNuclear and High Energy PhysicsMaterials scienceNuclear engineeringchemistry.chemical_element7. Clean energy01 natural sciences010305 fluids & plasmasBeam trips0103 physical sciencesNeutronlithium targetSettore ING-IND/19 - Impianti NucleariStructural materialInternational Fusion Materials Irradiation Facility-DEMO Oriented NEutron Source (IFMIF-DONES)shock wavesFusion powerCondensed Matter Physics3. Good healthchemistry13. Climate actionNeutron sourceLithiumfatigueBeam (structure)Nominal power (photovoltaic)IEEE Transactions on Plasma Science
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