Actions for Extraction of tritium from lithium aluminate

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Extraction of tritium from lithium aluminate

Author
Yunker, W.
Published
United States : [publisher not identified], 1976.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1976.
Physical Description
microfiche : negative ; 11 x 15 cm

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Summary
Complete data are presented for the extraction of tritium from neutron irradiated lithium aluminate pellets. Two methods were used: (a) thermal/vacuum extraction at temperatures up to 980/sup 0/C and (b) dissolution of the pellets in sodium tetraborate at 850/sup 0/C followed by vacuum extraction. Approximately 1 percent of the tritium was in a noncondensable (at -195/sup 0/C and 10/sup -3/ torr) form. Extraction efficiency was greater than 95 percent.
Report Numbers
HEDL-TME-76-81
Other Subject(s)
Collection
U.S. Atomic Energy Commission depository collection.
Note
DOE contract number: E(45-1)-2170
OSTI Identifier 7231494
Research organization: Hanford Engineering Development Lab., Richland, WA (United States).
View MARC record | catkey: 45374424