Fuel inventory and deposition in castellated structures in JET-ILW

Since 2011 the JET tokamak has been operated with a metal ITER-like wall (JET-ILW) including castellated beryllium limiters and lamellae-type bulk tungsten tiles in the divertor. This has allowed for a large scale test of castellated plasma-facing components (PFC). Procedures for sectioning the limi...

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Authors: Rubel, M., Petersson, P., Zhou, Y., Coad, J.P., Lungu, C., Jet Contributors, García Muñoz, Manuel
Format: article
Status:Published version
Publication Date:2017
Country:España
Institution:Universidad de Sevilla (US)
Repository:idUS. Depósito de Investigación de la Universidad de Sevilla
OAI Identifier:oai:idus.us.es:11441/100422
Online Access:https://hdl.handle.net/11441/100422
https://doi.org/10.1088/1741-4326/aa6864
Access Level:Open access
Keyword:JET
ITER-like wall
Beryllium limiters
Castellation
Deposition
Fuel inventory
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spelling Fuel inventory and deposition in castellated structures in JET-ILWRubel, M.Petersson, P.Zhou, Y.Coad, J.P.Lungu, C.Jet ContributorsGarcía Muñoz, ManuelJETITER-like wallBeryllium limitersCastellationDepositionFuel inventorySince 2011 the JET tokamak has been operated with a metal ITER-like wall (JET-ILW) including castellated beryllium limiters and lamellae-type bulk tungsten tiles in the divertor. This has allowed for a large scale test of castellated plasma-facing components (PFC). Procedures for sectioning the limiters into single blocks of castellation have been developed. This facilitated morphology studies of morphology of surfaces inside the grooves for limiters after experimental campaigns 2011–2012 and 2013–2014. The deposition in the 0.4–0.5mm wide grooves of the castellation is ‘shallow’. It reaches 1–2mm into the 12mm deep gap. Deuterium concentrations are small (mostly below 1 × 1018 cm−2 ). The estimated total amount of deuterium in all the castellated limiters does not exceed the inventory of the plasma-facing surfaces (PFS) of the limiters. There are only traces of Ni, Cr and Fe deposited in the castellation gaps. The same applies to the carbon content. Also low deposition of D, Be and C has been measured on the sides of the bulk tungsten lamellae pieces. Modelling clearly reflects: (a) a sharp decrease in the measured deposition profiles and (b) an increase in deposition with the gap width. Both experimental and modelling data give a strong indication and information to ITER that narrow gaps in the castellated PFC are essential. X-ray diffraction on PFS has clearly shown two distinct composition patterns: Be with an admixture of Be–W intermetallic compounds (e.g. Be22W) in the deposition zone, whilst only pure Be has been detected in the erosion zone. The lack of compound formation in the erosion zone indicates that no distinct changes in the thermo-mechanical properties of the Be PFC might be expected.EURATOM 633053Swedish Research Council (VR) 2015–04844IOP PublishingFísica Atómica, Molecular y NuclearRNM138: Física Nuclear Aplicada2017info:eu-repo/semantics/articleinfo:eu-repo/semantics/publishedVersionapplication/pdfapplication/pdfhttps://hdl.handle.net/11441/100422https://doi.org/10.1088/1741-4326/aa6864reponame:idUS. Depósito de Investigación de la Universidad de Sevillainstname:Universidad de Sevilla (US)InglésNuclear Fusion, 57 (6), 066027-.6330532015–04844https://doi.org/10.1088/1741-4326/aa6864info:eu-repo/semantics/openAccessoai:idus.us.es:11441/1004222026-06-17T12:51:07Z
dc.title.none.fl_str_mv Fuel inventory and deposition in castellated structures in JET-ILW
title Fuel inventory and deposition in castellated structures in JET-ILW
spellingShingle Fuel inventory and deposition in castellated structures in JET-ILW
Rubel, M.
JET
ITER-like wall
Beryllium limiters
Castellation
Deposition
Fuel inventory
title_short Fuel inventory and deposition in castellated structures in JET-ILW
title_full Fuel inventory and deposition in castellated structures in JET-ILW
title_fullStr Fuel inventory and deposition in castellated structures in JET-ILW
title_full_unstemmed Fuel inventory and deposition in castellated structures in JET-ILW
title_sort Fuel inventory and deposition in castellated structures in JET-ILW
dc.creator.none.fl_str_mv Rubel, M.
Petersson, P.
Zhou, Y.
Coad, J.P.
Lungu, C.
Jet Contributors
García Muñoz, Manuel
author Rubel, M.
author_facet Rubel, M.
Petersson, P.
Zhou, Y.
Coad, J.P.
Lungu, C.
Jet Contributors
García Muñoz, Manuel
author_role author
author2 Petersson, P.
Zhou, Y.
Coad, J.P.
Lungu, C.
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
Beryllium limiters
Castellation
Deposition
Fuel inventory
topic JET
ITER-like wall
Beryllium limiters
Castellation
Deposition
Fuel inventory
description Since 2011 the JET tokamak has been operated with a metal ITER-like wall (JET-ILW) including castellated beryllium limiters and lamellae-type bulk tungsten tiles in the divertor. This has allowed for a large scale test of castellated plasma-facing components (PFC). Procedures for sectioning the limiters into single blocks of castellation have been developed. This facilitated morphology studies of morphology of surfaces inside the grooves for limiters after experimental campaigns 2011–2012 and 2013–2014. The deposition in the 0.4–0.5mm wide grooves of the castellation is ‘shallow’. It reaches 1–2mm into the 12mm deep gap. Deuterium concentrations are small (mostly below 1 × 1018 cm−2 ). The estimated total amount of deuterium in all the castellated limiters does not exceed the inventory of the plasma-facing surfaces (PFS) of the limiters. There are only traces of Ni, Cr and Fe deposited in the castellation gaps. The same applies to the carbon content. Also low deposition of D, Be and C has been measured on the sides of the bulk tungsten lamellae pieces. Modelling clearly reflects: (a) a sharp decrease in the measured deposition profiles and (b) an increase in deposition with the gap width. Both experimental and modelling data give a strong indication and information to ITER that narrow gaps in the castellated PFC are essential. X-ray diffraction on PFS has clearly shown two distinct composition patterns: Be with an admixture of Be–W intermetallic compounds (e.g. Be22W) in the deposition zone, whilst only pure Be has been detected in the erosion zone. The lack of compound formation in the erosion zone indicates that no distinct changes in the thermo-mechanical properties of the Be PFC might be expected.
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/11441/100422
https://doi.org/10.1088/1741-4326/aa6864
url https://hdl.handle.net/11441/100422
https://doi.org/10.1088/1741-4326/aa6864
dc.language.none.fl_str_mv Inglés
language_invalid_str_mv Inglés
dc.relation.none.fl_str_mv Nuclear Fusion, 57 (6), 066027-.
633053
2015–04844
https://doi.org/10.1088/1741-4326/aa6864
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 IOP Publishing
publisher.none.fl_str_mv IOP Publishing
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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score 15,300719

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