skip to main content
DOE Patents title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: PROCESS FOR THE RECOVERY OF PLUTONIUM

Abstract

An improvement is presented in the process for recovery and decontamination of plutonium. The carrier precipitate containing plutonium is dissolved and treated with an oxidizing agent to place the plutonium in a hexavalent oxidation state. A lanthanum fluoride precipitate is then formed in and removed from the solution to carry undesired fission products. The fluoride ions in the reniaining solution are complexed by addition of a borate sueh as boric acid, sodium metaborate or the like. The plutonium is then reduced and carried from the solution by the formation of a bismuth phosphate precipitate. This process effects a better separation from unwanted flssion products along with conccntration of the plutonium by using a smaller amount of carrier.

Inventors:
Issue Date:
Research Org.:
Originating Research Org. not identified
OSTI Identifier:
4253014
Patent Number(s):
2868619
Assignee:
U.S. Atomic Energy Commission DTIE; NSA-13-013375
NSA Number:
NSA-13-013375
Resource Type:
Patent
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-59
Country of Publication:
United States
Language:
English
Subject:
CHEMISTRY; BISMUTH PHOSPHATES; BORATES; CHEMICAL REACTIONS; COMPLEXES; DECONTAMINATION; ENRICHMENT; FISSION PRODUCTS; LANTHANUM FLUORIDES; OXIDATION; PLUTONIUM; PRECIPITATION; RECOVERY; REDUCTION; SEPARATION PROCESSES; SOLUTIONS

Citation Formats

Ritter, D.M. PROCESS FOR THE RECOVERY OF PLUTONIUM. United States: N. p., 1959. Web.
Ritter, D.M. PROCESS FOR THE RECOVERY OF PLUTONIUM. United States.
Ritter, D.M. Tue . "PROCESS FOR THE RECOVERY OF PLUTONIUM". United States.
@article{osti_4253014,
title = {PROCESS FOR THE RECOVERY OF PLUTONIUM},
author = {Ritter, D.M.},
abstractNote = {An improvement is presented in the process for recovery and decontamination of plutonium. The carrier precipitate containing plutonium is dissolved and treated with an oxidizing agent to place the plutonium in a hexavalent oxidation state. A lanthanum fluoride precipitate is then formed in and removed from the solution to carry undesired fission products. The fluoride ions in the reniaining solution are complexed by addition of a borate sueh as boric acid, sodium metaborate or the like. The plutonium is then reduced and carried from the solution by the formation of a bismuth phosphate precipitate. This process effects a better separation from unwanted flssion products along with conccntration of the plutonium by using a smaller amount of carrier.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1959},
month = {1}
}