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:
- Issue Date:
- OSTI Identifier:
- 4197023
- Patent Number(s):
- 2917358
- Assignee:
- U.S. Atomic Energy Commission
- Patent Classifications (CPCs):
-
C - CHEMISTRY C01 - INORGANIC CHEMISTRY C01G - COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
- 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.
@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 = {1959},
month = {12}
}
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