Search results for " DIVERTOR"

showing 10 items of 25 documents

Thermal-hydraulic behaviour of the DEMO divertor plasma facing components cooling circuit

2017

Abstract Within the framework of the Work Package DIV 1 – “Divertor Cassette Design and Integration” of the EUROfusion action, a research campaign has been jointly carried out by ENEA and University of Palermo to investigate the thermal-hydraulic performances of the DEMO divertor cassette cooling system. A comparative evaluation study has been performed considering three different options for the cooling circuit layout of the divertor Plasma Facing Components (PFCs). The potential improvement in the thermal-hydraulic performance of the cooling system, to be achieved by modifying cooling circuit layout, has been also assessed and discussed in terms of optimization strategy. The research acti…

Work packageComputer scienceHydraulicsNuclear engineeringComputational fluid dynamics7. Clean energy01 natural sciences010305 fluids & plasmaslaw.inventionThermal hydraulicsMaterials Science(all)law0103 physical sciencesWater coolingGeneral Materials Science010306 general physicsSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringFinite volume methodbusiness.industryMechanical EngineeringDivertorDEMO Divertor Plasma Facing Components CFD analysis HydraulicsPlasmaNuclear Energy and Engineeringbusiness
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Thermal-hydraulic study of the DEMO divertor cassette body cooling circuit equipped with a liner and two reflector plates

2021

Abstract In the framework of the Work Package DIV 1 – “Divertor Cassette Design and Integration” of the EUROfusion action, a research campaign has been jointly carried out by University of Palermo and ENEA to investigate the steady-state thermal-hydraulic performances of the DEMO divertor cassette cooling system. The research activity has been focussed onto the most recent design of the Cassette Body (CB) cooling circuit, consistent with the DEMO baseline 2017 and equipped with a liner and two Reflector Plates (RPs), whose main functions are to protect the underlying vacuum pump hole from the radiation arising from plasma and shield the PFCs inlet distributors, respectively. The research ca…

Materials scienceNuclear engineeringComputational fluid dynamics7. Clean energy01 natural sciences010305 fluids & plasmaslaw.inventionThermal hydraulicsDivertorlawShield0103 physical sciencesWater coolingGeneral Materials Science010306 general physicsDEMOSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringThermofluid-dynamicsCassette bodybusiness.industryMechanical EngineeringDivertorCassette body CFD analysis DEMO Divertor Thermofluid-dynamicsCoolantNuclear Energy and EngineeringFlow velocityVacuum pumpbusinessCFD analysis
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On a computational study of the hydraulic behavior of the ITER divertor cassette full-scale prototype

2009

NUCLEAR FUSION DIVERTOR THERMAL-HYDRAULICS
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Erosion, screening, and migration of tungsten in the JET divertor

2019

The erosion of tungsten (W), induced by the bombardment of plasma and impurity particles, determines the lifetime of plasma-facing components as well as impacting on plasma performance by the influx of W into the confined region. The screening of W by the divertor and the transport of W in the plasma determines largely the W content in the plasma core, but the W source strength itself has a vital impact on this process. The JET tokamak experiment provides access to a large set of W erosion-determining parameters and permits a detailed description of the W source in the divertor closest to the ITER one: (i) effective sputtering yields and fluxes as function of impact energy of intrinsic (Be,…

tungsten divertorNuclear and High Energy PhysicsMaterials scienceNuclear engineeringchemistry.chemical_elementTungsten01 natural sciences010305 fluids & plasmaserosion and depositionASDEX UpgradePhysics::Plasma PhysicsImpurity0103 physical sciencesITER divertor010306 general physicsW spectroscopyJet (fluid)DivertorPlasmaequipment and suppliesCondensed Matter::Mesoscopic Systems and Quantum Hall EffectCondensed Matter PhysicsERO modellingchemistryJETPhysics::Space PhysicsErosionPhysics::Accelerator PhysicsAstrophysics::Earth and Planetary Astrophysicsddc:620Nuclear Fusion
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Hydraulic Characterization of the Full Scale Mock-Up of the DEMO Divertor Outer Vertical Target

2021

In the frame of the pre-conceptual design activities of the DEMO work package DIV-1 “Divertor Cassette Design and Integration” of the EUROfusion program, a mock-up of the divertor outer vertical target (OVT) was built, mainly in order to: (i) demonstrate the technical feasibility of manufacturing procedures; (ii) verify the hydraulic design and its capability to ensure a uniform and proper cooling for the plasma facing units (PFUs) with an acceptable pressure drop; and (iii) experimentally validate the computational fluid-dynamic (CFD) model developed by the University of Palermo. In this context, a research campaign was jointly carried out by the University of Palermo and ENEA to experimen…

TechnologyControl and OptimizationRenewable Energy Sustainability and the EnvironmentTEnergy Engineering and Power Technologyplasma facing components01 natural sciences010305 fluids & plasmas0103 physical sciencesDEMO Divertor Plasma facing components Thermal hydraulicsdivertorDEMO; divertor; plasma facing components; thermal hydraulicsElectrical and Electronic Engineeringthermal hydraulics010306 general physicsEngineering (miscellaneous)DEMOSettore ING-IND/19 - Impianti NucleariEnergy (miscellaneous)
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Eurofusion-DEMO Divertor - Cassette Design and Integration

2020

International audience; The Eurofusion-DEMO design will complete the Pre Conceptual Design phase (PCD) with a PCD Gate, named G1, scheduled to take place in Q4 2020 that will focus on assessing the feasibility of the plant and its main components prior to entering into the Conceptual Design phase. In the paper first an overview is given of the Eurofusion-DEMO Divertor Assembly including design and interface description, systems and functional requirements, load specification, system classification, manufacturing procedures and cost estimate. Then critical issues are discussed and potential design solutions are proposed, e.g.:- Neutron material damage limits of the different (structural) mat…

DEMO; Divertor; CAD DesignMaterials sciencePassive coolingNuclear engineeringPort (circuit theory)01 natural sciences7. Clean energy010305 fluids & plasmas[SPI]Engineering Sciences [physics]DivertorConceptual design0103 physical sciencesDEMO fusion reactorGeneral Materials ScienceCAD Design010306 general physicsDEMOnuclear fusionSettore ING-IND/19 - Impianti NucleariCivil and Structural Engineeringelectromagnetic computationToroidNuclear heatingSeparatrixMechanical EngineeringDivertornuclear fusion plasma control electromagnetic computationNuclear Energy and EngineeringTUNGSTEN/EUROFER COATING SYSTEM CONCEPTUAL DESIGN COOLING CIRCUIT PROGRESS HCLLplasma controlHigh heat
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Divertor of the European DEMO: Engineering and technologies for power exhaust

2022

International audience; In a power plant scale fusion reactor, a huge amount of thermal power produced by the fusion reaction and external heating must be exhausted through the narrow area of the divertor targets. The targets must withstand the intense bombardment of the diverted particles where high heat fluxes are generated and erosion takes place on the surface. A considerable amount of volumetric nuclear heating power must also be exhausted. To cope with such an unprecedented power exhaust challenge, a highly efficient cooling capacity is required. Furthermore, the divertor must fulfill other critical functions such as nuclear shielding and channeling (and compression) of exhaust gas fo…

Technology020209 energyMechanical EngineeringPower exhaust02 engineering and technologyDEMO; Fusion reactor; Divertor; Plasma-facing component; High-heat-flux; Power exhaust01 natural sciences7. Clean energy010305 fluids & plasmas[SPI]Engineering Sciences [physics]Fusion reactorDivertorDEMO; Divertor; Fusion reactor; High-heat-flux; Plasma-facing component; Power exhaustNuclear Energy and Engineering0103 physical sciences0202 electrical engineering electronic engineering information engineeringPlasma-facing componentGeneral Materials ScienceHigh-heat-fluxddc:600DEMOSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringFusion Engineering and Design
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Study of a water-cooled convective divertor prototype for the DEMO fusion reactor

2000

The plasma facing components of a fusion power reactor have a large impact on the overall plant design, its performance and availability and on the cost of electricity. The present work concerns a study of feasibility for a water-cooled prototype of the convective divertor component of the DEMO fusion reactor. The study has been carried out in two steps. In the first one thermal-hydraulic and neutronic parametric analyses have been performed to find out the prototype optimized configuration. In the second step thermo-mechanical analyses have been carried out on the obtained configuration to investigate the potential and limits of the proposed prototype, with a particular reference to the ma…

ConvectionNeutron transportMaterials scienceHeat fluxCritical heat fluxDivertorNuclear engineeringNUCLEAR FUSION DEMO REACTOR DIVERTOR THERMO-MECHANICSHeat transferMechanical engineeringNuclear fusionFusion powerAIP Conference Proceedings
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Further improvements in the structural analysis of DEMO Divertor Cassette body and design assessment according to RCC-MRx

2019

Abstract This paper presents the enhancements related to the structural analyses of DEMO Divertor in the framework of the EUROfusion Power Plant Physics & Technology (PPPT) program. This activity started two years ago and its preliminary results were published in previous papers. It has been divided in some areas defined by the similarity of the matters they contain: the structural analysis, of utmost importance, has been preceded by a preliminary phase, like the geometry definition or the thermal and the electric-magnetic analysis for loads evaluation; then the structural analysis has been finally confirmed with further evaluations related to excessive deformation or plastic instability. T…

Power stationRCC-MRxStructural analysis01 natural sciencesMechanical components010305 fluids & plasmasPreliminary analysisDivertorFEM;RCC-MRx;Divertor;Structural analysis;Thermal analysis;DEMO0103 physical sciencesGeneral Materials ScienceThermal analysis010306 general physicsDEMOSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringDesign assessmentDEMO; Divertor; FEM; RCC-MRx; Structural analysis; Thermal analysisFEMDivertorMechanical EngineeringStructural analysiThermal analysiNuclear Energy and EngineeringSystems engineeringMaterials Science (all)
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Hydraulic characterization of the full scale divertor cassette prototype

2011

In the frame of the activities related to ITER divertor R&D, ENEA C.R. Brasimone was in charge by Fusion For Energy (F4E) to perform the assembly, the hydraulic tests and the theoretical simulation of the hydraulic behavior of the full scale divertor cassette prototype. The objective of these activities was aimed at the investigation of the thermal-hydraulic behavior of the full-scale divertor cassette both under steady state condition and during draining and drying operational transient. In particular, the steady state tests were focused on finally check whether the hydraulic design of the divertor components is able to ensure a uniform and proper cooling for the plasma facing components, …

System codeNuclear Energy and EngineeringITER Divertor Draining and dryingMechanical EngineeringNuclear engineeringDivertorFull scaleEnvironmental scienceGeneral Materials ScienceTransient (oscillation)Settore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringFusion Engineering and Design
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