THE REPROCESSING OF HOMOGENEOUS BERYLLIUM-BASED REACTOR FUEL. A SUGGESTED SCHEME FOR THE SELECTIVE AQUEOUS DISSOLUTION OF THE MATRIX

Author: Farrell, M. S.
Published: [Place of publication not identified] : [publisher not identified], 1962.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1962.
Physical Description: microopaque : positive ; 8 x 13 cm
Additional Creators: Temple, R. B.

Availability

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Summary

The matrix of a dilute homogeneous H.T.G.C. reactor fuel employing metallic Be as a moderator can be selectively dissolved by a caustic soda solution containing salicylate ion. At least 90% of the U and Th can be recovered as insoluble solids, but in the case of irradiated material the U loss might be higher. Some decontamination of the resulting Be solution from fission products and Pa/sup 233/ can also be obtained. A tentative chemical flowsheet is proposed on the basis of the results obtained. (auth)

Report Numbers

AAEC/E-93

Other Subject(s)

Collection

U.S. Atomic Energy Commission depository collection.

Note

NSA number: NSA-16-033061
OSTI Identifier 4777482
Research organization: Australia. Atomic Energy Commission Research Establishment, Lucas Heights, New South Wales.

View MARC record | catkey: 38046559