PROCESS FOR SEPARATING PLUTONIUM BY HYDROXIDES
Patent
·
OSTI ID:4117172
A carrier process for separating plutonium from solu tions of irradiated uranium is outlined which results in reduction of carrier bulk and liquid volumes. In this process, which is preferably preceded by a bismuth phosphate precipitation, a soluble salt of a carrier metal is added to the nitric acid solution to give a concentration of 5O to 5OO mg/l, the solution is made neutral or slightly alkaline, the plutonium-carrying precipitate is removed and then redissolved, and the process repeated with a second metal salt. The carrier metal may be one of the group Al, Bi, Cu, Co, Fe, La, Ni, and Zr. The plutonium may be in either the reduced or oxidized form. (D.L.C.)
- Research Organization:
- Originating Research Org. not identified
- NSA Number:
- NSA-15-007430
- OSTI ID:
- 4117172
- Report Number(s):
- GB 859191
- Country of Publication:
- United Kingdom
- Language:
- English
Similar Records
BISMUTH HYDROXIDE METHOD FOR RECOVERING PLUTONIUM
PLUTONIUM CARRIER METATHESIS WITH ORGANIC REAGENT
SEPARATION OF PLUTONIUM HYDROXIDE FROM BISMUTH HYDROXIDE
Patent
·
Mon Oct 31 23:00:00 EST 1960
·
OSTI ID:4100938
PLUTONIUM CARRIER METATHESIS WITH ORGANIC REAGENT
Patent
·
Tue Jul 01 00:00:00 EDT 1958
·
OSTI ID:4304462
SEPARATION OF PLUTONIUM HYDROXIDE FROM BISMUTH HYDROXIDE
Patent
·
Tue Aug 19 00:00:00 EDT 1958
·
OSTI ID:4329793