Search results for " Plasma facing components"

showing 6 items of 6 documents

THERMOFLUID-DYNAMICS OF DEMO DIVERTOR CASSETTE

2023

The divertor is a critical in-vessel component of nuclear fusion reactors, being responsible for the fulfilment of certain fundamental functions for the machine: it must be able to handle the power deposited by charged particle and neutron irradiation, ensure the presence of channels through which the fusion ashes can be removed from the Vacuum Vessel (VV), provide plasma-compatible surfaces, and shield the VV and magnets from nuclear loads. The heat load that can be tolerated by the divertor under normal and off-normal operating conditions is a pivotal parameter when dimensioning a fusion power plant since exceptionally high heat fluxes can be observed in some regions of the divertor, in t…

DEMO Divertor Plasma facing components Thermofluid-dynamics CFD analysisSettore ING-IND/19 - Impianti Nucleari
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Steady state and transient thermal-hydraulic characterization of full-scale ITER divertor plasma facing components

2008

Abstract In the frame of the activities related to ITER divertor R&D, ENEA CR Brasimone was in charge by EFDA (European Fusion Development Agreement) to investigate the thermal-hydraulic behaviour of the full-scale divertor plasma facing components, i.e. the outer vertical target, the inner vertical target and the dome-liner, both in steady state and during draining and drying transient. The investigation was performed by means of both experimental test campaigns performed at ENEA CR Brasimone and theoretical simulation developed in RELAP5 Mod.3.3 environment at the Department of Nuclear Engineering of the University of Palermo (DIN). This paper presents the achieved experimental results fo…

Materials scienceSteady stateITER Divertor Plasma facing components Thermal-hydraulicsMechanical EngineeringNuclear engineeringDivertorFull scalePlasmaThermal hydraulicsNuclear Energy and EngineeringFUSIONE NUCLEARE ITER DIVERTORE TERMOIDRAULICAGeneral Materials ScienceTransient (oscillation)Settore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringFusion Engineering and Design
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Hydraulic analysis of EU-DEMO divertor plasma facing components cooling circuit under nominal operating scenarios

2019

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 University of Palermo and ENEA to investigate the steady state thermal-hydraulic behaviour of the DEMO divertor cassette cooling circuit, focussing the attention on its Plasma Facing Components (PFCs). The research campaign has been carried out following a theoretical-computational approach based on the Finite Volume Method and adopting the commercial Computational Fluid-Dynamic code ANSYS-CFX. A realistic model of the PFCs cooling circuit has been analysed, specifically embedding each Plasma Facing Unit (PFU) cooling chann…

Nuclear engineeringCFD analysis; DEMO; Divertor; Plasma facing components; Thermofluid-dynamics7. Clean energy01 natural sciences010305 fluids & plasmasDivertor0103 physical sciencesGeneral Materials ScienceBoundary value problemCFD analysiTotal pressure010306 general physicsDEMOSettore ING-IND/19 - Impianti NucleariPlasma facing componentsCivil and Structural EngineeringThermofluid-dynamicsFinite volume methodSteady stateTurbulenceMechanical EngineeringDivertorPlasma facing componentCoolantVibrationNuclear Energy and EngineeringEnvironmental scienceCFD analysisFusion Engineering and Design
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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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Status of ITER TBM port plug conceptual design and analyses

2014

The test blanket module port plug (TBM PP) consists of a TBM frame and two TBM-sets. However, at any time of the ITER operation, a TBM set can be replaced by a dummy TBM. The frame provides a standardized interface with the vacuum vessel (VV)/port structure and provides thermal isolation from the shield blanket. As one of the plasma-facing components, it shall withstand heat loads while at the same time provide adequate neutron shielding for the VV and magnet coils. The frame design shall provide a stable engineering solution to hold TBM-sets and also provide a mean for rapid remote handling replacement and refurbishment. This paper presents main design features of the conceptual design of …

TokamakITER Tokamak Plasma facing components TBM port plug (TBM PP)TokamakComputer scienceMechanical EngineeringInterface (computing)Nuclear engineeringFrame (networking)Port (circuit theory)BlanketPlasma facing componentlaw.inventionNuclear Energy and EngineeringConceptual designlawITERShieldElectromagnetic shieldingGeneral Materials ScienceTBM port plug (TBM PP)Settore ING-IND/19 - Impianti NucleariTokamak;TBM port plug (TBM PP);Plasma facing components;ITERPlasma facing componentsCivil and Structural EngineeringFusion Engineering and Design
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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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