0000000000141916

AUTHOR

M. Frisoni

showing 7 related works from this author

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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Updated design and integration of the ancillary circuits for the European Test Blanket Systems

2019

The validation of the key technologies relevant for a DEMO Breeding Blanket is one of the main objectives of the design and operation of the Test Blanket Systems (TBS) in ITER. In compliance with the main features and technical requirements of the parent breeding blanket concepts, the European TBM Project is developing the HCLL (Helium Cooled Lithium Lead) and HCPB (Helium Cooled Pebble Bed)-TBS, focusing in this phase on the design life cycle and on R&D activities in support of the design. The TBS ancillary systems are mainly circuits devoted to the removal of thermal power and to the extraction and recovery of the tritium generated in the Test Blanket Modules. They are: • The Helium C…

Computer scienceThermo-mechanical analysiTest Blanket ModuleBlanketCAD integration; Test Blanket Module; Thermo-hydraulic analysis; Thermo-mechanical analysis; Tritium technologies01 natural sciences7. Clean energy010305 fluids & plasmasTritium technologiesConceptual design0103 physical sciencesGeneral Materials Science010306 general physicsSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringElectronic circuitThermo-hydraulic analysisThermo-mechanical analysisMechanical EngineeringCAD integrationCoolantTest (assessment)Nuclear Energy and EngineeringPhysical spaceSystems engineeringThermo-hydraulic analysiFusion Engineering and Design
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Start-up and shutdown thermomechanical transient analyses of the IFMIF European lithium target system

2014

In the framework of the current IFMIF Engineering Validation and Engineering Design Activities (IFMIF/EVEDA) phase, ENEA is responsible for the design of the European concept of the IFMIF lithium target system which foresees the possibility to periodically replace only the most irradiated and thus critical component (i.e., the backplate) while continuing to operate the rest of the target for a longer period (bayonet backplate concept). With the objective of evaluating the performances of the system in terms of temperature, stress and displacement fields evolution during start-up and shutdown phases, an uncoupled thermomechanical transient analysis has been performed in close collaboration w…

Materials scienceNuclear engineeringIFMIF Target assembly Bayonet backplate Thermomechanics Start-up ShutdownStart-upShutdown7. Clean energy01 natural sciencesThermomechanic010305 fluids & plasmasStress (mechanics)ThermomechanicsTarget assembly0103 physical sciencesThermalIFMIFGeneral Materials ScienceNeutron010306 general physicsBayonet backplateSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringMechanical EngineeringNuclear dataFinite element methodIFMIF;Bayonet backplate;Thermomechanics;Start-up;Shutdown;Target assemblyNuclear Energy and EngineeringSystems designTransient (oscillation)Engineering design process
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The design of the DONES lithium target system

2019

Abstract In the framework of the EU fusion roadmap implementing activities, an accelerator-based Li(d,xn) neutron source called DONES (Demo-Oriented early NEutron Source) is being designed within the EUROfusion Work Package Early Neutron Source as an essential irradiation facility for testing candidate materials for DEMO reactor and future fusion power plants. DONES will employ a high speed liquid lithium jet struck by a 125 mA, 40 MeV deuteron beam to generate the intense neutron flux used to irradiate the material samples up to the desired level of displacement damage (˜10 dpa/fpy for iron in 0.3 l) and He production rates (˜10-13 appm He/dpa). In order to rapidly achieve a sound and stab…

Work packageComputer scienceNuclear engineeringLithium target systemchemistry.chemical_elementTarget system01 natural sciences7. Clean energy010305 fluids & plasmasNeutron flux0103 physical sciencesIFMIFGeneral Materials ScienceDONES; IFMIF; Lithium target system; Target system010306 general physicsSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringMechanical EngineeringFusion powerNuclear Energy and EngineeringchemistryNeutron sourceLithiumVacuum chamberDONESLiquid lithiumBeam (structure)Fusion Engineering and Design
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Engineering design and steady state thermomechanical analysis of the IFMIF European lithium target system

2013

In the framework of the current IFMIF Engineering Validation and Engineering Design Activities (IFMIF/EVEDA) phase, ENEA is responsible for the design of the European concept of the IFMIF lithium target system which foresees the possibility to periodically replace only the most irradiated and thus critical component (i.e., the backplate) while continuing to operate the rest of the target for a longer period (bayonet backplate concept). In this work, the results of the steady state thermomechanical analysis of the IFMIF EU target assembly are briefly reported highlighting the relevant indications obtained with respect to the fulfillment of the design requirements. © 2013 IEEE.

EngineeringSteady state (electronics)Nuclear FusionThermo-mechanicsbusiness.industryengineering design;IFMIF;target assembly;therm omechanicsengineering designchemistry.chemical_elementMechanical engineeringtarget assemblychemistryIFMIFThermomechanical analysisLithiumEngineering design processbusinessSettore ING-IND/19 - Impianti Nuclearitherm omechanics2013 IEEE 25th Symposium on Fusion Engineering (SOFE)
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Analysis of the thermomechanical behavior of the IFMIF bayonet target assembly under design loading scenarios

2015

In the framework of the IFMIF Engineering Validation and Engineering Design Activities (IFMIF/EVEDA) phase, ENEA is responsible for the design of the European concept of the IFMIF lithium target system which foresees the possibility to periodically replace only the most irradiated and thus critical component (i.e., the backplate) while continuing to operate the rest of the target for a longer period (the so-called bayonet backplate concept). In this work, the results of the steady state thermomechanical analysis of the IFMIF bayonet target assembly under two different design loading scenarios (a "hot" scenario and a "cold" scenario) are briefly reported highlighting the relevant indications…

Steady stateEngineering designComputer scienceMechanical EngineeringNuclear engineeringStructural integrityIFMIF Target assembly Bayonet backplate Engineering design ThermomechanicsThermomechanicStress (mechanics)ThermomechanicsHigh fluxNuclear Energy and EngineeringLinearizationTarget assemblyComponent (UML)Thermomechanics;Bayonet backplate;Engineering design;Target assembly;IFMIFIFMIFGeneral Materials ScienceEngineering design processBayonet backplateMiddle planeSettore 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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