Search results for "iter-like wall"

showing 5 items of 5 documents

Overview of the JET results

2015

Since the installation of an ITER-like wall, the JET programme has focused on the consolidation of ITER design choices and the preparation for ITER operation, with a specific emphasis given to the bulk tungsten melt experiment, which has been crucial for the final decision on the material choice for the day-one tungsten divertor in ITER. Integrated scenarios have been progressed with the re-establishment of long-pulse, high-confinement H-modes by optimizing the magnetic configuration and the use of ICRH to avoid tungsten impurity accumulation. Stationary discharges with detached divertor conditions and small edge localized modes have been demonstrated by nitrogen seeding. The differences in…

Chemical analysiMagnetic confinementEdge localized modeTokamak:Física [Ciências exactas e naturais]Nuclear engineeringplasma-facing componentsTungsten7. Clean energyiter-like walllaw.inventionheat loadsAlcator C-ModlawPlasma-facing componentalcator C-MODQCPhysicsJet (fluid)Thermally activatedDivertormagnetic confinementMagnetic confinement fusionTokamak deviceerosionCondensed Matter PhysicsChemical erosionPost mortem analysiCondensed Matter Physics; Nuclear and High Energy PhysicsBerylliumAtomic physicstokamaksTokamaksNuclear and High Energy Physicschemistry.chemical_elementImpurity accumulationCondensed Matter PhysicNuclear and High Energy Physics; Condensed Matter PhysicsTungstenFísica Física:Physical sciences [Natural sciences]divertorNuclear fusionNuclear and High Energy PhysicPhysics Physical sciencesGas fuel analysifuel retentionSettore FIS/07 - Fisica Applicata(Beni Culturali Ambientali Biol.e Medicin)operationOrders of magnitudechemistryJETtransportMagnetic configuration
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Comparison of the structure of the plasma-facing surface and tritium accumulation in beryllium tiles from JET ILW campaigns 2011-2012 and 2013-2014

2019

In this study, beryllium tiles from Joint European Torus (JET) vacuum vessel wall were analysed and compared regarding their position in the vacuum vessel and differences in the exploitation conditions during two campaigns of ITER-Like-Wall (ILW) in 2011-2012 (ILW1) and 2013-2014 (ILW2) Tritium content in beryllium samples were assessed. Two methods were used to measure tritium content in the samples - dissolution under controlled conditions and tritium thermal desorption. Prior to desorption and dissolution experiments, scanning electron microscopy and energy dispersive x-ray spectroscopy were used to study structure and chemical composition of plasma-facing-surfaces of the beryllium sampl…

Fuel retentionPhysics::Medical Physics01 natural sciencesQuantitative Biology::Cell Behavior010305 fluids & plasmasiter-like walljoint european torusRETENTION010302 applied physicsJet (fluid)tritiumPhysicsMechanicsSurface (topology)Fusion Plasma and Space Physicslcsh:TK9001-9401surgical procedures operativecardiovascular systemJoint European TorusTritiumBerylliumBerylliumNuclear and High Energy PhysicsretentionTechnology and Engineeringanimal structuresMaterials scienceQuantitative Biology::Tissues and OrgansMaterials Science (miscellaneous)Joint European Toruschemistry.chemical_elementTritium114 Physical sciencesGeneral Relativity and Quantum CosmologyFusion plasma och rymdfysik0103 physical sciencesddc:530ITER-LIKE-WALLITER-like walltechnology industry and agriculturePlasmaiter-like-wallberylliumTRANSPORTfuel retentionbody regionsNuclear Energy and Engineeringchemistrytransportlcsh:Nuclear engineering. Atomic power
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Tritium retention in plasma facing materials of JET ITER-Like-Wall retrieved from the vacuum vessel in 2012 (ILW1), 2014 (ILW2) and 2016 (ILW3)

2021

Abstract ITER-Like-Wall (ILW) project has been carried out at Joint European Torus (JET) to test plasma facing materials relevant to International Thermonuclear Experimental Reactor – ITER [1]. Limiters and an upper dump plate of the vacuum vessel are made of bulk beryllium tiles, whereas for the divertor bulk tungsten and tungsten-coated carbon fibre (CFC) composite tiles are used. During the shutdowns in ILW1 (2012), ILW2 (2014) and ILW3 (2016), selected beryllium tiles were removed from the vacuum vessel. In this study, tiles from three positions were analysed, and analysis results were compared regarding both the tile position in the vacuum vessel and differences in the exploitation con…

Nuclear and High Energy PhysicsITER-Like WallMaterials scienceThermonuclear fusionFuel retentionMaterials Science (miscellaneous)Nuclear engineeringJoint European Toruschemistry.chemical_elementTungstenTritium01 natural sciences010305 fluids & plasmas0103 physical sciences010302 applied physicsDivertorTK9001-9401Nuclear Energy and EngineeringchemistryDeuteriumvisual_artvisual_art.visual_art_mediumJoint European TorusNuclear engineering. Atomic powerTritiumTileBerylliumBerylliumNuclear Materials and Energy
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Structure, tritium depth profile and desorption from 'plasma-facing' beryllium materials of ITER-Like-Wall at JET

2017

This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training programme 2014–2018 under grant agreement No 633053 . The views and opinions expressed herein do not necessarily reflect those of the European Commission.

Nuclear and High Energy PhysicsThermal desorption spectroscopyMaterials Science (miscellaneous)Nuclear engineeringJoint European TorusAnalytical chemistryThermal desorptionchemistry.chemical_elementFuel accumulationTritiumThermal desorption7. Clean energy01 natural sciences010305 fluids & plasmasFusion plasma och rymdfysikDesorption0103 physical sciences:NATURAL SCIENCES:Physics [Research Subject Categories]010306 general physicsJet (fluid)ChemistryITER-like wallPlasmaITER-Like-Walllcsh:TK9001-9401Fusion Plasma and Space Physicsrespiratory tract diseasesNuclear Energy and Engineeringcardiovascular systemlcsh:Nuclear engineering. Atomic powerTritiumBerylliumDepth profileBeryllium
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Fuel inventory and material migration of JET main chamber plasma facing components compared over three operational periods

2020

Fuel retention and material migration results from JET ITER-like wall beryllium limiter tiles are presented for three operating periods. Ion beam analysis results support the general picture of erosion during limiter configurations with local deposition on tile ends far into the scrape off layer. Similar trends of fuel concentrations are observed in all JET operating periods; (i) low on surfaces exposed to high heat flux and erosion and (ii) higher in deposits. The pattern of fuel retention and deposition correlates with heat flux and distribution of limiter plasmas touching inner and outer limiters. The D/Be ratio in the thickest deposit is similar to 0.01. Global fuel retention attributed…

DESORPTIONMaterials scienceEROSIONJET ITER-like wallchemistry.chemical_element01 natural sciences114 Physical sciences010305 fluids & plasmasmaterial migrationDesorption0103 physical sciencesDEPOSITION010306 general physicsMathematical PhysicsJet (fluid)ITER-LIKE-WALLDivertorMetallurgyPlasmaCondensed Matter PhysicsberylliumAtomic and Molecular Physics and Opticsfuel retentionchemistryINNER WALLErosionDIVERTORBerylliumDeposition (chemistry)
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