Studies in fusion reactor technology. Final report, September 1, 1974--August 31, 1977 [electronic resource].
- Washington, D.C. : United States. Dept. of Energy, 1977.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
- Physical Description:
- Pages: 6 : digital, PDF file
- Additional Creators:
- Princeton University
United States. Department of Energy
United States. Department of Energy. Office of Scientific and Technical Information
- Two independent measurements of hydrogen permeation through stainless steel at driving pressures in the range from 10/sup -6/ to 1 Pa indicate that most extant predictions of tritium permeation through fusion reactors are probably overestimated grossly. A comprehensive analysis demonstrates that, given available structural materials, the prospects are negligible for the economic production of synthetic fuels via radiolytic reactions in fusion reactor systems.
- Published through SciTech Connect.
Axtmann, R C; Perkins, H K.
- Funding Information:
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