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Title: 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}
}