Search Menu
DOE PAGES title logo U.S. Department of Energy
Office of Scientific and Technical Information
Search Scholarly Publications

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 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 aremore » 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]
+ Show Author Affiliations
  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:
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.
Copy to clipboard
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. https://doi.org/10.1016/j.nme.2018.10.002
Copy to clipboard
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. https://doi.org/10.1016/j.nme.2018.10.002. https://www.osti.gov/servlets/purl/1479753.
Copy to clipboard
@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},
number = ,
volume = 17,
place = {United States},
year = {Tue Oct 16 00:00:00 EDT 2018},
month = {Tue Oct 16 00:00:00 EDT 2018}
}
Copy to clipboard
Journal Article:
Free Publicly Available Full Text
Publisher's Version of Record
https://doi.org/10.1016/j.nme.2018.10.002
Copyright Statement
Other availability
Search WorldCat Search WorldCat to find libraries that may hold this journal
Citation Metrics:
Cited by: 5 works
Citation information provided by
Web of Science
Save / Share:
Export Metadata
Save to My Library
You must Sign In or Create an Account in order to save documents to your library.

Works referenced in this record:

Mechanical and thermo-physical characterization of the carbon fibre composite NB31
journal, March 2007

Prototyping phase of the high heat flux scraper element of Wendelstein 7-X
journal, November 2016

The role of structure on the thermal properties of graphitic foams
journal, June 2004

High heat flux facility GLADIS:
journal, August 2007

Linear Plasma Device PSI-2 for Plasma-Material Interaction Studies
journal, July 2015

  • Kreter, A.; Brandt, C.; Huber, A.
  • Fusion Science and Technology, Vol. 68, Issue 1
  • DOI: 10.13182/FST14-906

Engineering Challenges in W7-X: Lessons Learned and Status for the Second Operation Phase
journal, May 2018

  • Bosch, H. -S.; Andreeva, T.; Brakel, R.
  • IEEE Transactions on Plasma Science, Vol. 46, Issue 5
  • DOI: 10.1109/TPS.2018.2818934

A multi-purpose manipulator system for W7-X as user facility for plasma edge investigation
journal, November 2017

Depth-resolved sample composition analysis using laser-induced ablation-quadrupole mass spectrometry and laser-induced breakdown spectroscopy
journal, June 2018

Hydrogen isotope inventory in the graphite divertor tiles of ASDEX Upgrade as measured by thermal desorption spectroscopy
journal, October 1997

Analysis for hydrogen by nuclear reaction and energy recoil detection
journal, March 1992

  • Lanford, W. A.
  • Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 66, Issue 1-2
  • DOI: 10.1016/0168-583X(92)96142-L

High Resolution Surface Analysis by TOF-SIMS
journal, April 2000

    Sort by:
    [ × clear filter / sort ]

    Works referencing / citing this record:

    Development and Performance of Tungsten-Coated Graphitic Foam for Plasma-Facing Components
    journal, May 2019

      Sort by:
      [ × clear filter / sort ]

      Similar Records in DOE PAGES and OSTI.GOV collections: