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Title: URANOUS IODATE AS A CARRIER FOR PLUTONIUM

Abstract

A process is described for precipitating plutonium on a uranous iodate carrier from an aqueous acid solution conA plutonium solution more concentrated than the original solution can then be obtained by oxidizing the uranium to the hexavalent state and dissolving the precipitate, after separating the latter from the original solution, by means of warm nitric acid.

Inventors:
; ;
Publication Date:
Research Org.:
Originating Research Org. not identified
OSTI Identifier:
4197023
Patent Number(s):
US 2917358
Assignee:
U.S. Atomic Energy Commission DTIE; NSA-14-007477
NSA Number:
NSA-14-007477
Resource Type:
Patent
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-60
Country of Publication:
United States
Language:
English
Subject:
CHEMISTRY; ACIDS; IODATES; NITRIC ACID; PLUTONIUM; PRECIPITATION; SEPARATION PROCESSES; SOLUTIONS; URANIUM COMPOUNDS; WATER

Citation Formats

Miller, D.R., Seaborg, G.T., and Thompson, S.G. URANOUS IODATE AS A CARRIER FOR PLUTONIUM. United States: N. p., 1959. Web.
Miller, D.R., Seaborg, G.T., & Thompson, S.G. URANOUS IODATE AS A CARRIER FOR PLUTONIUM. United States.
Miller, D.R., Seaborg, G.T., and Thompson, S.G. Tue . "URANOUS IODATE AS A CARRIER FOR PLUTONIUM". United States. doi:.
@article{osti_4197023,
title = {URANOUS IODATE AS A CARRIER FOR PLUTONIUM},
author = {Miller, D.R. and Seaborg, G.T. and Thompson, S.G.},
abstractNote = {A process is described for precipitating plutonium on a uranous iodate carrier from an aqueous acid solution conA plutonium solution more concentrated than the original solution can then be obtained by oxidizing the uranium to the hexavalent state and dissolving the precipitate, after separating the latter from the original solution, by means of warm nitric acid.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue Dec 15 00:00:00 EST 1959},
month = {Tue Dec 15 00:00:00 EST 1959}
}