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

Abstract

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 10 19 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 × 10 25 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 graphitesmore » 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.« less

Authors:
 [1]; ORCiD logo [2]; ORCiD logo [1];  [1]; ORCiD logo [2];  [1]; ORCiD logo [1];  [2];  [2];  [2];  [2]; ORCiD logo [2]; ORCiD logo [2]; ORCiD logo [2]
  1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  2. Forschungszentrum Julich (Germany). Inst. of Energy and Climate Research - Plasma Physics. Partner of the Trilateral Euregio Cluster (TEC)
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1479753
Grant/Contract Number:  
AC05-00OR22725
Resource Type:
Journal Article: Accepted Manuscript
Journal Name:
Nuclear Materials and Energy
Additional Journal Information:
Journal Volume: 17; Journal ID: ISSN 2352-1791
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; graphitic foam; graphite; plasma facing component; plasma exposure; monoblock

Citation Formats

Youchison, D. L., Brezinsek, S., Lumsdaine, A., Klett, J. W., Coenen, J. W., Parish, C., Ievlev, A. V., Oelmann, J., Li, C., Rasinski, M., Martynova, Y., Linsmeier, Ch., Ertmer, S., and Kreter, A. Plasma exposures of a high-conductivity graphitic foam for plasma facing components. United States: N. p., 2018. Web. doi:10.1016/j.nme.2018.10.002.
Youchison, D. L., Brezinsek, S., Lumsdaine, A., Klett, J. W., Coenen, J. W., Parish, C., Ievlev, A. V., Oelmann, J., Li, C., Rasinski, M., Martynova, Y., Linsmeier, Ch., Ertmer, S., & Kreter, A. Plasma exposures of a high-conductivity graphitic foam for plasma facing components. United States. doi:10.1016/j.nme.2018.10.002.
Youchison, D. L., Brezinsek, S., Lumsdaine, A., Klett, J. W., Coenen, J. W., Parish, C., Ievlev, A. V., Oelmann, J., Li, C., Rasinski, M., Martynova, Y., Linsmeier, Ch., Ertmer, S., and Kreter, A. Tue . "Plasma exposures of a high-conductivity graphitic foam for plasma facing components". United States. doi:10.1016/j.nme.2018.10.002. https://www.osti.gov/servlets/purl/1479753.
@article{osti_1479753,
title = {Plasma exposures of a high-conductivity graphitic foam for plasma facing components},
author = {Youchison, D. L. and Brezinsek, S. and Lumsdaine, A. and Klett, J. W. and Coenen, J. W. and Parish, C. and Ievlev, A. V. and Oelmann, J. and Li, C. and Rasinski, M. and Martynova, Y. and Linsmeier, Ch. and Ertmer, S. and Kreter, A.},
abstractNote = {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.},
doi = {10.1016/j.nme.2018.10.002},
journal = {Nuclear Materials and Energy},
issn = {2352-1791},
number = ,
volume = 17,
place = {United States},
year = {2018},
month = {10}
}

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