REPROCESSING OF POWER REACTOR FUELS. Third Quarterly Progress Report for April 1 to July 1, 1958
Technical Report
·
OSTI ID:4286807
Zirconium-clad fuel elements of uranium-- molybdenum alloy can be dissolved in boiling hydrofluoric-nitric acid mixtures practicably and without excessive corrosion in a dissolver made of wrought 309 Nb stainless steel; the corrosion of welded seams in these mixtures has not been investigated. Plutonium and urauium can be extracted from the dissolver solution satisfactorily with 10% tribuiyl phosphate in Ultrasene'' provided that aluminum nitrate is present in the dissolver solution. (For preceding period see DP-318.) (auth)
- Research Organization:
- Du Pont de Nemours (E.I.) & Co. Savannah River Lab., Augusta, Ga.
- DOE Contract Number:
- AT(07-2)-1
- NSA Number:
- NSA-13-009842
- OSTI ID:
- 4286807
- Report Number(s):
- DP-319
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-59
- Country of Publication:
- United States
- Language:
- English
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