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U.S. Department of Energy
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Tritium diffusion in nonmetallic solids of interest for fusion reactors. Annual progress report, June 1, 1974--August 1, 1975

Technical Report ·
OSTI ID:4162003
Tritium diffusion coefficients in selected metal oxides and carbides plus pyrolytic carbon have been measured by injecting tritium into specimens and measuring the time rate of tritium release during isothermal annealing. Release results were generally consistent with classical diffusion solutions and yielded diffusion coefficients characterized by a single-valued activation energy over the temperature range of measurement. The pyrolytic carbon results were unique in that tritium release was apparently controlled by surface desorption or exchange rather than diffusion. Measured diffusion coefficients were considerable lower than the literature values for metals at comparable temperatures, which suggests that metal oxides, carbides, or nitrides may be useful as tritium barriers in fusion systems. (auth)
Research Organization:
North Carolina State Univ., Raleigh (USA). Dept. of Nuclear Engineering
NSA Number:
NSA-33-001097
OSTI ID:
4162003
Report Number(s):
ORO--4721-4
Country of Publication:
United States
Language:
English