Plasma exposures of a high-conductivity graphitic foam for plasma facing components

The plasma-surface interactions from samples of high-conductivity graphitic foam biased to 120 V and placed in 6–8 eV deuterium plasmas with densities as high as 1019 m−3 were investigated at the PSI-2 linear plasma device in Jülich. Graphitic foam-plasma interactions were also studied at the Wendel...

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Main Authors: D.L. Youchison, S. Brezinsek, A. Lumsdaine, J.W. Klett, J.W. Coenen, C. Parish, A.V. Ievlev, J. Oelmann, C. Li, M. Rasinski, Y. Martynova, Ch. Linsmeier, S. Ertmer, A. Kreter
Format: Article
Language:English
Published: Elsevier 2018-12-01
Series:Nuclear Materials and Energy
Online Access:http://www.sciencedirect.com/science/article/pii/S2352179118300826
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author D.L. Youchison
S. Brezinsek
A. Lumsdaine
J.W. Klett
J.W. Coenen
C. Parish
A.V. Ievlev
J. Oelmann
C. Li
M. Rasinski
Y. Martynova
Ch. Linsmeier
S. Ertmer
A. Kreter
author_facet D.L. Youchison
S. Brezinsek
A. Lumsdaine
J.W. Klett
J.W. Coenen
C. Parish
A.V. Ievlev
J. Oelmann
C. Li
M. Rasinski
Y. Martynova
Ch. Linsmeier
S. Ertmer
A. Kreter
author_sort D.L. Youchison
collection DOAJ
description The plasma-surface interactions from samples of high-conductivity graphitic foam biased to 120 V and placed in 6–8 eV deuterium plasmas with densities as high as 1019 m−3 were investigated at the PSI-2 linear plasma device in Jülich. Graphitic foam-plasma interactions were also studied at the Wendelstein 7-X (W7-X) stellarator in Greifswald by exposure to hydrogen and helium plasmas using the Jülich multi-purpose manipulator. The purpose was to explore the possibility of using the material in a plasma facing component, and initial results were encouraging. In W7-X, no measurable erosion or cracking was observed. The PSI-2 samples received a deuterium fluence of 5 × 1025 m−2 resulting in an average erosion of 43 µm or about 5 mg per sample. Residual gas analysis (RGA) data were acquired to monitor sample outgassing. Laser-induced Breakdown Spectroscopy (LIBS) was used to measure deuterium retention in the porous foam. After exposure, the surfaces were characterized with scanning electron microscopy, energy dispersive x-ray analysis and time-of-flight secondary ion mass spectrometry (ToF-SIMS). The graphitic foam has a thermal conductivity as high as 287 W/mK and is considered as a replacement to more exotic carbon fiber composites such as SepCarb NB31 or isotropic graphites like ATJ that are no longer produced but used in present-day tokamak experiments. Actively cooled monoblocks were made from the foam and underwent extensive materials characterization including infrared response studies at Oak Ridge National Laboratory. This material is under consideration for the proposed actively-cooled W7-X divertor scraper element. Keywords: Graphitic foam, Graphite, Plasma facing component, Plasma exposure, Monoblock
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spelling doaj.art-f86a138f9eef47eab99d9e06aae75c3e2022-12-21T19:18:54ZengElsevierNuclear Materials and Energy2352-17912018-12-0117123128Plasma exposures of a high-conductivity graphitic foam for plasma facing componentsD.L. Youchison0S. Brezinsek1A. Lumsdaine2J.W. Klett3J.W. Coenen4C. Parish5A.V. Ievlev6J. Oelmann7C. Li8M. Rasinski9Y. Martynova10Ch. Linsmeier11S. Ertmer12A. Kreter13Oak Ridge National Laboratory, Oak Ridge, TN 37831, USA; Corresponding author.Forschungszentrum Jülich GmbH, Institut für Energie- und Klimaforschung – Plasmaphysik, Partner of the Trilateral Euregio Cluster (TEC), Jülich 52425, GermanyOak Ridge National Laboratory, Oak Ridge, TN 37831, USAOak Ridge National Laboratory, Oak Ridge, TN 37831, USAForschungszentrum Jülich GmbH, Institut für Energie- und Klimaforschung – Plasmaphysik, Partner of the Trilateral Euregio Cluster (TEC), Jülich 52425, GermanyOak Ridge National Laboratory, Oak Ridge, TN 37831, USAOak Ridge National Laboratory, Oak Ridge, TN 37831, USAForschungszentrum Jülich GmbH, Institut für Energie- und Klimaforschung – Plasmaphysik, Partner of the Trilateral Euregio Cluster (TEC), Jülich 52425, GermanyForschungszentrum Jülich GmbH, Institut für Energie- und Klimaforschung – Plasmaphysik, Partner of the Trilateral Euregio Cluster (TEC), Jülich 52425, GermanyForschungszentrum Jülich GmbH, Institut für Energie- und Klimaforschung – Plasmaphysik, Partner of the Trilateral Euregio Cluster (TEC), Jülich 52425, GermanyForschungszentrum Jülich GmbH, Institut für Energie- und Klimaforschung – Plasmaphysik, Partner of the Trilateral Euregio Cluster (TEC), Jülich 52425, GermanyForschungszentrum Jülich GmbH, Institut für Energie- und Klimaforschung – Plasmaphysik, Partner of the Trilateral Euregio Cluster (TEC), Jülich 52425, GermanyForschungszentrum Jülich GmbH, Institut für Energie- und Klimaforschung – Plasmaphysik, Partner of the Trilateral Euregio Cluster (TEC), Jülich 52425, GermanyForschungszentrum Jülich GmbH, Institut für Energie- und Klimaforschung – Plasmaphysik, Partner of the Trilateral Euregio Cluster (TEC), Jülich 52425, GermanyThe plasma-surface interactions from samples of high-conductivity graphitic foam biased to 120 V and placed in 6–8 eV deuterium plasmas with densities as high as 1019 m−3 were investigated at the PSI-2 linear plasma device in Jülich. Graphitic foam-plasma interactions were also studied at the Wendelstein 7-X (W7-X) stellarator in Greifswald by exposure to hydrogen and helium plasmas using the Jülich multi-purpose manipulator. The purpose was to explore the possibility of using the material in a plasma facing component, and initial results were encouraging. In W7-X, no measurable erosion or cracking was observed. The PSI-2 samples received a deuterium fluence of 5 × 1025 m−2 resulting in an average erosion of 43 µm or about 5 mg per sample. Residual gas analysis (RGA) data were acquired to monitor sample outgassing. Laser-induced Breakdown Spectroscopy (LIBS) was used to measure deuterium retention in the porous foam. After exposure, the surfaces were characterized with scanning electron microscopy, energy dispersive x-ray analysis and time-of-flight secondary ion mass spectrometry (ToF-SIMS). The graphitic foam has a thermal conductivity as high as 287 W/mK and is considered as a replacement to more exotic carbon fiber composites such as SepCarb NB31 or isotropic graphites like ATJ that are no longer produced but used in present-day tokamak experiments. Actively cooled monoblocks were made from the foam and underwent extensive materials characterization including infrared response studies at Oak Ridge National Laboratory. This material is under consideration for the proposed actively-cooled W7-X divertor scraper element. Keywords: Graphitic foam, Graphite, Plasma facing component, Plasma exposure, Monoblockhttp://www.sciencedirect.com/science/article/pii/S2352179118300826
spellingShingle D.L. Youchison
S. Brezinsek
A. Lumsdaine
J.W. Klett
J.W. Coenen
C. Parish
A.V. Ievlev
J. Oelmann
C. Li
M. Rasinski
Y. Martynova
Ch. Linsmeier
S. Ertmer
A. Kreter
Plasma exposures of a high-conductivity graphitic foam for plasma facing components
Nuclear Materials and Energy
title Plasma exposures of a high-conductivity graphitic foam for plasma facing components
title_full Plasma exposures of a high-conductivity graphitic foam for plasma facing components
title_fullStr Plasma exposures of a high-conductivity graphitic foam for plasma facing components
title_full_unstemmed Plasma exposures of a high-conductivity graphitic foam for plasma facing components
title_short Plasma exposures of a high-conductivity graphitic foam for plasma facing components
title_sort plasma exposures of a high conductivity graphitic foam for plasma facing components
url http://www.sciencedirect.com/science/article/pii/S2352179118300826
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