METHOD OF SEPARATING Pu FROM METATHESIZED BiPO$sub 4$ CARRIER
Abstract
A process is given for separating uranium, neptunium, and/or plutonium from a bismuth hydroxide carrier by selective dissolution of these actinides with nitric acid of a concentration of from 0.05 to 0.5N.
- Inventors:
- Issue Date:
- Research Org.:
- Originating Research Org. not identified
- OSTI Identifier:
- 4164768
- Patent Number(s):
- 2938768
- 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
G - PHYSICS G21 - NUCLEAR PHYSICS G21C - NUCLEAR REACTORS
- NSA Number:
- NSA-14-021620
- Resource Type:
- Patent
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-60
- Country of Publication:
- United States
- Language:
- English
- Subject:
- CHEMISTRY; BISMUTH HYDROXIDES; NEPTUNIUM; NITRIC ACID; PLUTONIUM; SEPARATION PROCESSES; URANIUM
Citation Formats
Knox, W J, and Thompson, S G. METHOD OF SEPARATING Pu FROM METATHESIZED BiPO$sub 4$ CARRIER. United States: N. p., 1960.
Web.
Knox, W J, & Thompson, S G. METHOD OF SEPARATING Pu FROM METATHESIZED BiPO$sub 4$ CARRIER. United States.
Knox, W J, and Thompson, S G. Tue .
"METHOD OF SEPARATING Pu FROM METATHESIZED BiPO$sub 4$ CARRIER". United States.
@article{osti_4164768,
title = {METHOD OF SEPARATING Pu FROM METATHESIZED BiPO$sub 4$ CARRIER},
author = {Knox, W J and Thompson, S G},
abstractNote = {A process is given for separating uranium, neptunium, and/or plutonium from a bismuth hydroxide carrier by selective dissolution of these actinides with nitric acid of a concentration of from 0.05 to 0.5N.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue May 31 00:00:00 EDT 1960},
month = {Tue May 31 00:00:00 EDT 1960}
}