Assessment of erosion, deposition and fuel retention in the JET-ILW divertor from ion beam analysis data

Post-mortem analyses of individual components provide relevant information on plasma-surface interac- tions like tungsten erosion, beryllium deposition and plasma fuel retention with divertor tiles via implan- tation or co-deposition. Ion Beam techniques are ideal tools for such purposes and have be...

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Autores: Catarino, N., Barradas, N.P., Corregidor, V., Widdowson, A., Baron-Wiechec, A., Jet Contributors, García Muñoz, Manuel
Tipo de recurso: artículo
Estado:Versión publicada
Fecha de publicación:2017
País:España
Institución:Universidad de Sevilla (US)
Repositorio:idUS. Depósito de Investigación de la Universidad de Sevilla
OAI Identifier:oai:idus.us.es:11441/100410
Acceso en línea:https://hdl.handle.net/11441/100410
https://doi.org/10.1016/j.nme.2016.10.027
Access Level:acceso abierto
Palabra clave:JET
ITER-like wall
Plasma facing components
Erosion
Deposition
Ion beam analysis
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spelling Assessment of erosion, deposition and fuel retention in the JET-ILW divertor from ion beam analysis dataCatarino, N.Barradas, N.P.Corregidor, V.Widdowson, A.Baron-Wiechec, A.Jet ContributorsGarcía Muñoz, ManuelJETITER-like wallPlasma facing componentsErosionDepositionIon beam analysisPost-mortem analyses of individual components provide relevant information on plasma-surface interac- tions like tungsten erosion, beryllium deposition and plasma fuel retention with divertor tiles via implan- tation or co-deposition. Ion Beam techniques are ideal tools for such purposes and have been extensively used for post-mortem analyses of selected tiles from JET following each campaign. In this contribution results from tiles removed from the JET ITER-Like Wall (JET-ILW) divertor follow- ing the 2013–2014 campaign are presented. The results summarize erosion, deposition and fuel retention along the poloidal cross section of the divertor surface and provide data for comparison with the first JET-ILW campaign, showing a similar pattern of material migration with the exception of Tile 6 where the strike point time on the tile was ∼4 times longer in 2013–2014 than in 2011–2012, which is likely to account for more material migration to this region. The W deposition on top of the Mo marker coating of Tile 4 shows that the enrichment takes place at the strike point location.EURATOM 633053Portuguese FCT - Fundação para a Ciência e a Tecnologia PD/BD/52411/2013ElsevierFísica Atómica, Molecular y NuclearRNM138: Física Nuclear Aplicada2017info:eu-repo/semantics/articleinfo:eu-repo/semantics/publishedVersionapplication/pdfapplication/pdfhttps://hdl.handle.net/11441/100410https://doi.org/10.1016/j.nme.2016.10.027reponame:idUS. Depósito de Investigación de la Universidad de Sevillainstname:Universidad de Sevilla (US)InglésNuclear Materials and Energy, 12, 559-563.633053PD/BD/52411/2013http://dx.doi.org/10.1016/j.nme.2016.10.027info:eu-repo/semantics/openAccessoai:idus.us.es:11441/1004102026-06-17T12:51:07Z
dc.title.none.fl_str_mv Assessment of erosion, deposition and fuel retention in the JET-ILW divertor from ion beam analysis data
title Assessment of erosion, deposition and fuel retention in the JET-ILW divertor from ion beam analysis data
spellingShingle Assessment of erosion, deposition and fuel retention in the JET-ILW divertor from ion beam analysis data
Catarino, N.
JET
ITER-like wall
Plasma facing components
Erosion
Deposition
Ion beam analysis
title_short Assessment of erosion, deposition and fuel retention in the JET-ILW divertor from ion beam analysis data
title_full Assessment of erosion, deposition and fuel retention in the JET-ILW divertor from ion beam analysis data
title_fullStr Assessment of erosion, deposition and fuel retention in the JET-ILW divertor from ion beam analysis data
title_full_unstemmed Assessment of erosion, deposition and fuel retention in the JET-ILW divertor from ion beam analysis data
title_sort Assessment of erosion, deposition and fuel retention in the JET-ILW divertor from ion beam analysis data
dc.creator.none.fl_str_mv Catarino, N.
Barradas, N.P.
Corregidor, V.
Widdowson, A.
Baron-Wiechec, A.
Jet Contributors
García Muñoz, Manuel
author Catarino, N.
author_facet Catarino, N.
Barradas, N.P.
Corregidor, V.
Widdowson, A.
Baron-Wiechec, A.
Jet Contributors
García Muñoz, Manuel
author_role author
author2 Barradas, N.P.
Corregidor, V.
Widdowson, A.
Baron-Wiechec, A.
Jet Contributors
García Muñoz, Manuel
author2_role author
author
author
author
author
author
dc.contributor.none.fl_str_mv Física Atómica, Molecular y Nuclear
RNM138: Física Nuclear Aplicada
dc.subject.none.fl_str_mv JET
ITER-like wall
Plasma facing components
Erosion
Deposition
Ion beam analysis
topic JET
ITER-like wall
Plasma facing components
Erosion
Deposition
Ion beam analysis
description Post-mortem analyses of individual components provide relevant information on plasma-surface interac- tions like tungsten erosion, beryllium deposition and plasma fuel retention with divertor tiles via implan- tation or co-deposition. Ion Beam techniques are ideal tools for such purposes and have been extensively used for post-mortem analyses of selected tiles from JET following each campaign. In this contribution results from tiles removed from the JET ITER-Like Wall (JET-ILW) divertor follow- ing the 2013–2014 campaign are presented. The results summarize erosion, deposition and fuel retention along the poloidal cross section of the divertor surface and provide data for comparison with the first JET-ILW campaign, showing a similar pattern of material migration with the exception of Tile 6 where the strike point time on the tile was ∼4 times longer in 2013–2014 than in 2011–2012, which is likely to account for more material migration to this region. The W deposition on top of the Mo marker coating of Tile 4 shows that the enrichment takes place at the strike point location.
publishDate 2017
dc.date.none.fl_str_mv 2017
dc.type.none.fl_str_mv info:eu-repo/semantics/article
info:eu-repo/semantics/publishedVersion
format article
status_str publishedVersion
dc.identifier.none.fl_str_mv https://hdl.handle.net/11441/100410
https://doi.org/10.1016/j.nme.2016.10.027
url https://hdl.handle.net/11441/100410
https://doi.org/10.1016/j.nme.2016.10.027
dc.language.none.fl_str_mv Inglés
language_invalid_str_mv Inglés
dc.relation.none.fl_str_mv Nuclear Materials and Energy, 12, 559-563.
633053
PD/BD/52411/2013
http://dx.doi.org/10.1016/j.nme.2016.10.027
dc.rights.none.fl_str_mv info:eu-repo/semantics/openAccess
eu_rights_str_mv openAccess
dc.format.none.fl_str_mv application/pdf
application/pdf
dc.publisher.none.fl_str_mv Elsevier
publisher.none.fl_str_mv Elsevier
dc.source.none.fl_str_mv reponame:idUS. Depósito de Investigación de la Universidad de Sevilla
instname:Universidad de Sevilla (US)
instname_str Universidad de Sevilla (US)
reponame_str idUS. Depósito de Investigación de la Universidad de Sevilla
collection idUS. Depósito de Investigación de la Universidad de Sevilla
repository.name.fl_str_mv
repository.mail.fl_str_mv
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