Search results for " divertor"

showing 10 items of 25 documents

On the numerical and experimental characterisation of the ITER divertor cassette plasma facing component steady state hydraulic behaviour

2008

NUCLEAR FUSION ITER DIVERTOR THERMAL-HYYDRAULICS
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Overview of the DEMO staged design approach in Europe

2019

This paper describes the status of the pre-conceptual design activities in Europe to advance the technical basis of the design of a DEMOnstration Fusion Power Plant (DEMO) to come in operation around the middle of this century with the main aims of demonstrating the production of few hundred MWs of net electricity, the feasibility of operation with a closed-tritium fuel cycle, and maintenance systems capable of achieving adequate plant availability. This is expected to benefit as much as possible from the ITER experience, in terms of design, licensing, and construction. Emphasis is on an integrated design approach, based on system engineering, which provides a clear path for urgent R&D …

Nuclear and High Energy Physicsbreeding blanket; DEMO; design integration; divertor; fusion reactor; systems codeDesign activitiesFuel cyclemedia_common.quotation_subjectThermal power stationDesign integration7. Clean energy01 natural sciences010305 fluids & plasmasdesign integration0103 physical sciencesdivertorProduction (economics)010306 general physicsDEMOmedia_commonbreeding blanketIntegrated designbusiness.industryCondensed Matter PhysicsInterdependencesystems codeSystems engineeringfusion reactorElectricityddc:620businessNuclear Fusion
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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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Erosion and screening of tungsten during inter/intra-ELM periods in the JET-ILW divertor

2020

Abstract Intra-ELM tungsten sources, which dominate the total W source, are quantified in the inner and outer divertor of JET-ILW. The amount of the sputtered W atoms for individual ELMs demonstrates a clear dependence on the ELM frequency. It decreases when the pedestal temperature is lower and, correspondingly, the ELM frequency is higher. Nevertheless, the entire gross erosion W source (the number of eroded W atoms per second due to ELMs) increases initially with ELM frequency and reaches its maximum at fELM ≈ 50–55 Hz followed by its reduction in the high frequency range. The in/out asymmetry of the intra-ELM W sources during ELMs is a critical issue and is investigated in this contribu…

PFCNuclear and High Energy PhysicsMaterials scienceMaterials Science (miscellaneous)media_common.quotation_subjectJET-ILWTungsten erosionchemistry.chemical_elementTungsten01 natural sciencesAsymmetry010305 fluids & plasmasDivertor screening of tungstenPedestal0103 physical sciencesDuct (flow)PSImedia_common010302 applied physicsDivertorlcsh:TK9001-9401Tungsten imaging spectroscopyNuclear Energy and EngineeringchemistryW Divertorlcsh:Nuclear engineering. Atomic powerAtomic physicsddc:624Nuclear Materials and Energy
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Structural verification and manufacturing procedures of the cooling system, for DEMO divertor target (OVT)

2019

The paper presents the design activities and testing plan of a vertical target mock-up, developed within the pre-conceptual design phase for DEMO Work Package DIV-1 “Divertor Cassette Design and Integration” - EUROfusion Power Plant Physics & Technology (PPPT) program. Activities concerning the Divertor Outboard Vertical Target cooling mock-up are presented in term of CAD model, thermal-hydraulic numerical simulation, structural analysis, structural integrity verification and manufacturing procedure. Moreover, the mechanical dimensions of support systems for Plasma Facing Components (PFCs), manifold and diffuser have been analyzed in detail, in order to avoid structural fault during the tes…

Power stationComputer simulationDesign activitiesDivertor target cooling mock-upNuclear engineeringDivertorMechanical EngineeringDivertor cassetteCADFault (power engineering)01 natural sciences010305 fluids & plasmasNuclear Energy and Engineering0103 physical sciencesWater coolingDEMO; Divertor cassette; Divertor target cooling mock-up; Civil and Structural Engineering; Nuclear Energy and Engineering; Materials Science (all); Mechanical EngineeringGeneral Materials ScienceMaterials Science (all)Test plan010306 general physicsDEMO; Divertor cassette; Divertor target cooling mock-upDEMOSettore ING-IND/19 - Impianti NucleariCivil and Structural Engineering
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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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The hydraulic behaviour of the prototype of on a ITER divertor cassette

2009

Settore ING-IND/19 - Impianti NucleariITER divertor thermal-hydraulics
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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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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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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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