ARSENATE CARRIER PRECIPITATION METHOD OF SEPARATING PLUTONIUM FROM NEUTRON IRRADIATED URANIUM AND RADIOACTIVE FISSION PRODUCTS
Abstract
A process is described for precipitating Pu from an aqueous solution as the arsenate, either per se or on a bismuth arsenate carrier, whereby a separation from uranium and fission products, if present in solution, is accomplished.
- Inventors:
- Issue Date:
- OSTI Identifier:
- 4005026
- Patent Number(s):
- 2989367
- Assignee:
- U.S. Atomic Energy Commission
- Patent Classifications (CPCs):
-
Y - NEW / CROSS SECTIONAL TECHNOLOGIES Y02 - TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE Y02E - REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
G - PHYSICS G21 - NUCLEAR PHYSICS G21C - NUCLEAR REACTORS
- NSA Number:
- NSA-15-019473
- Resource Type:
- Patent
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-61
- Country of Publication:
- United States
- Language:
- English
- Subject:
- CHEMISTRY; ARSENIC COMPOUNDS; BISMUTH; FISSION PRODUCTS; IRRADIATION; NEUTRONS; PLUTONIUM; PRECIPITATION; SEPARATION PROCESSES; SOLUTIONS; URANIUM; WATER
Citation Formats
Thompson, S G, Miller, D R, and James, R A. ARSENATE CARRIER PRECIPITATION METHOD OF SEPARATING PLUTONIUM FROM NEUTRON IRRADIATED URANIUM AND RADIOACTIVE FISSION PRODUCTS. United States: N. p., 1961.
Web.
Thompson, S G, Miller, D R, & James, R A. ARSENATE CARRIER PRECIPITATION METHOD OF SEPARATING PLUTONIUM FROM NEUTRON IRRADIATED URANIUM AND RADIOACTIVE FISSION PRODUCTS. United States.
Thompson, S G, Miller, D R, and James, R A. Tue .
"ARSENATE CARRIER PRECIPITATION METHOD OF SEPARATING PLUTONIUM FROM NEUTRON IRRADIATED URANIUM AND RADIOACTIVE FISSION PRODUCTS". United States.
@article{osti_4005026,
title = {ARSENATE CARRIER PRECIPITATION METHOD OF SEPARATING PLUTONIUM FROM NEUTRON IRRADIATED URANIUM AND RADIOACTIVE FISSION PRODUCTS},
author = {Thompson, S G and Miller, D R and James, R A},
abstractNote = {A process is described for precipitating Pu from an aqueous solution as the arsenate, either per se or on a bismuth arsenate carrier, whereby a separation from uranium and fission products, if present in solution, is accomplished.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1961},
month = {6}
}
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