Potential for graphite use adjacent to the plasma in nuclear fusion reactors [electronic resource].
- Columbus, Ohio : Battelle Memorial Institute, 1976. and Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
- Physical Description:
- Pages: 40 : digital, PDF file
- Additional Creators:
- Battelle Memorial Institute and United States. Department of Energy. Office of Scientific and Technical Information
- Restrictions on Access:
- Free-to-read Unrestricted online access
- The need to reduce high Z impurities in the plasma of fusion reactors has led to various ideas, including a low-Z liner, for isolating the first structural wall from the plasma. Graphite and other carbon containing materials (most notably SiC) are strong candidate materials for such liners. However, to assess the potential of these materials will require more information on the following properties: (1) Radiation effects under fusion reactor environment, (2) Sputtering, (3) Degassing. This document describes the current state of knowledge on carbons and graphites in each of these areas.
- Published through SciTech Connect., 06/01/1976., "bnwl-2078", and Morgan, W.C.; Gray, W.J.; Tingey, G.L.
- Funding Information:
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