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

Title: WET FLUORIDE SEPARATION METHOD

Abstract

The separation of U/sup 233/ from thorium, protactinium, and fission products present in neutron-irradiated thorium is accomplished by dissolving the irradiated materials in aqueous nitric acid, adding either a soluble fluoride, iodate, phosphate, or oxalate to precipltate the thorium, separating the precipltate from the solution, and then precipitating uranlum and protactinium by alkalizing the solution. The uranium and protactinium precipitate is removcd from the solution and dissolved in nitric acid. The uranyl nitrate may then be extracted from the acid solution by means of ether, and the protactinium recovered from the aqueous phase.

Inventors:
; ;
Publication Date:
Research Org.:
Originating Research Org. not identified
OSTI Identifier:
4296252
Patent Number(s):
US 2861866
Assignee:
U.S. Atomic Energy Commission DTIE; NSA-13-008412
NSA Number:
NSA-13-008412
Resource Type:
Patent
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-59
Country of Publication:
United States
Language:
English
Subject:
PATENTS; CHEMICAL REACTIONS; ETHERS; FISSION PRODUCTS; FLUORIDES; HYDROXIDES; IODIC ACID; IRRADIATION; MINERAL ACIDS; NEUTRON BEAMS; NITRIC ACID; OXALATES; PHOSPHATES; PRECIPITATION; PROTACTINIUM; SEPARATION PROCESSES; SOLUTIONS; THORIUM; URANIUM 233; URANYL NITRATES; WATER

Citation Formats

Seaborg, G.T., Gofman, J.W., and Stoughton, R.W. WET FLUORIDE SEPARATION METHOD. United States: N. p., 1958. Web.
Seaborg, G.T., Gofman, J.W., & Stoughton, R.W. WET FLUORIDE SEPARATION METHOD. United States.
Seaborg, G.T., Gofman, J.W., and Stoughton, R.W. Tue . "WET FLUORIDE SEPARATION METHOD". United States.
@article{osti_4296252,
title = {WET FLUORIDE SEPARATION METHOD},
author = {Seaborg, G.T. and Gofman, J.W. and Stoughton, R.W.},
abstractNote = {The separation of U/sup 233/ from thorium, protactinium, and fission products present in neutron-irradiated thorium is accomplished by dissolving the irradiated materials in aqueous nitric acid, adding either a soluble fluoride, iodate, phosphate, or oxalate to precipltate the thorium, separating the precipltate from the solution, and then precipitating uranlum and protactinium by alkalizing the solution. The uranium and protactinium precipitate is removcd from the solution and dissolved in nitric acid. The uranyl nitrate may then be extracted from the acid solution by means of ether, and the protactinium recovered from the aqueous phase.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1958},
month = {11}
}