SULFIDE METHOD PLUTONIUM SEPARATION
Patent
·
OSTI ID:4329797
A process is described for the recovery of plutonium from neutron irradiated uranium solutions. Such a solution is first treated with a soluble sullide, causing precipitation of the plutoniunn and uraniunn values present, along with those impurities which form insoluble sulfides. The precipitate is then treated with a solution of carbonate ions, which will dissolve the uranium and plutonium present while the fission product sulfides remain unaffected. After separation from the residue, this solution may then be treated by any of the usual methods, such as formation of a lanthanum fluoride precipitate, to effect separation of plutoniunn from uranium.
- Research Organization:
- Originating Research Org. not identified
- NSA Number:
- NSA-13-001010
- Assignee:
- U.S. Atomic Energy Commission
- Patent Number(s):
- US 2847274
- OSTI ID:
- 4329797
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-59
- Country of Publication:
- United States
- Language:
- English
Similar Records
Solubility of Plutonium (IV) Oxalate During Americium/Curium Pretreatment
DISSOLUTION OF PLUTONIUM CONTAINING CARRIER PRECIPITATE BY CARBONATE METATHESIS AND SEPARATION OF SULFIDE IMPURITIES THEREFROM BY SULFIDE PRECIPITATION
PROCESSES FOR SEPARATING AND RECOVERING CONSTITUENTS OF NEUTRON IRRADIATED URANIUM
Technical Report
·
Wed Aug 11 00:00:00 EDT 1999
·
OSTI ID:4329797
DISSOLUTION OF PLUTONIUM CONTAINING CARRIER PRECIPITATE BY CARBONATE METATHESIS AND SEPARATION OF SULFIDE IMPURITIES THEREFROM BY SULFIDE PRECIPITATION
Patent
·
Tue Jul 14 00:00:00 EDT 1959
·
OSTI ID:4329797
PROCESSES FOR SEPARATING AND RECOVERING CONSTITUENTS OF NEUTRON IRRADIATED URANIUM
Patent
·
Tue Nov 10 00:00:00 EST 1959
·
OSTI ID:4329797