METHOD FOR SEPARATING PLUTONIUM AND FISSION PRODUCTS EMPLOYING AN OXIDE AS A CARRIER FOR FISSION PRODUCTS

Title: METHOD FOR SEPARATING PLUTONIUM AND FISSION PRODUCTS EMPLOYING AN OXIDE AS A CARRIER FOR FISSION PRODUCTS

Full Record
Other Related Research

Abstract

Carrier precipitation processes for separating plutonium values from uranium fission products are described. Silicon dioxide or titanium dioxide in a finely divided state is added to an acidic aqueous solution containing hexavalent plutonium ions together with ions of uranium fission products. The supernatant solution containing plutonium ions is then separated from the oxide and the fission products associated therewith.

Inventors:: Davies, T.H.

Issue Date:: 1961-07-18

Research Org.:: Originating Research Org. not identified

OSTI Identifier:: 4065754

Patent Number(s):: 2992889

Assignee:: U.S. Atomic Energy Commission DTIE; NSA-15-022385

NSA Number:: NSA-15-022385

Resource Type:: Patent

Resource Relation:: Other Information: Orig. Receipt Date: 31-DEC-61

Country of Publication:: United States

Language:: English

Subject:: CHEMISTRY; ACIDITY; CATIONS; FISSION PRODUCTS; OXIDES; PLUTONIUM; PRECIPITATION; SEPARATION PROCESSES; SILICON OXIDES; SOLUTIONS; TITANIUM OXIDES; URANIUM; USES; WATER

Citation Formats


                    Davies, T.H. METHOD FOR SEPARATING PLUTONIUM AND FISSION PRODUCTS EMPLOYING AN OXIDE AS A CARRIER FOR FISSION PRODUCTS.  United States: N. p., 1961. 
        Web.

Copy to clipboard


                    Davies, T.H. METHOD FOR SEPARATING PLUTONIUM AND FISSION PRODUCTS EMPLOYING AN OXIDE AS A CARRIER FOR FISSION PRODUCTS.  United States.

Copy to clipboard


                    Davies, T.H. Tue .  
        "METHOD FOR SEPARATING PLUTONIUM AND FISSION PRODUCTS EMPLOYING AN OXIDE AS A CARRIER FOR FISSION PRODUCTS".  United States.

Copy to clipboard


                    
@article{osti_4065754,

  title        = {METHOD FOR SEPARATING PLUTONIUM AND FISSION PRODUCTS EMPLOYING AN OXIDE AS A CARRIER FOR FISSION PRODUCTS},

  author       = {Davies, T.H.},

  abstractNote = {Carrier precipitation processes for separating plutonium values from uranium fission products are described. Silicon dioxide or titanium dioxide in a finely divided state is added to an acidic aqueous solution containing hexavalent plutonium ions together with ions of uranium fission products. The supernatant solution containing plutonium ions is then separated from the oxide and the fission products associated therewith.},

  doi          = {},

  journal      = {},
number       = ,

  volume       = ,

  place        = {United States},

  year         = {1961},

  month        = {7}

}

Copy to clipboard

Patent:

Search for the full text at the U.S. Patent and Trademark Office

Save / Share:

Export Metadata

Save to My Library

Similar records in DOE Patents and OSTI.GOV collections:

ARSENATE CARRIER PRECIPITATION METHOD OF SEPARATING PLUTONIUM FROM NEUTRON IRRADIATED URANIUM AND RADIOACTIVE FISSION PRODUCTS

Patent Thompson, S.G.; Miller, D.R.; James, R.A.

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.
METHOD OF SEPARATING URANIUM, PLUTONIUM AND FISSION PRODUCTS BY BROMINATION AND DISTILLATION

Patent Jaffey, A.H.; Seaborg, G.T.

The method for separation of plutonium from uranium and radioactive fission products obtained by neutron irradiation of uranlum consists of reacting the lrradiated material with either bromine, hydrogen bromide, alumlnum bromide, or sulfur and bromine at an elevated temperature to form the bromides of all the elements, then recovering substantlally pure plutonium bromide by dlstillatlon in combinatlon with selective condensatlon at prescribed temperature and pressure.
METHOD OF SEPARATING URANIUM VALUES, PLUTONIUM VALUES AND FISSION PRODUCTS BY CHLORINATION

Patent Brown, H.S.; Seaborg, G.T.

The separation of plutonium and uranium from each other and from other substances is described. In general, the method comprises the steps of contacting the uranium with chlorine in the presence of a holdback material selected from the group consisting of lanthanum oxide and thorium oxide to form a uranium chloride higher than uranium tetrachloride, and thereafter heating the uranium chloride thus formed to a temperature at which the uranium chloride is volatilized off but below the volatilizalion temperature of plutonium chloride.
EXTRACTION METHOD FOR SEPARATING URANIUM, PLUTONIUM, AND FISSION PRODUCTS FROM COMPOSITIONS CONTAINING SAME

Patent Seaborg, G.T.

Methods for separating plutonium from the fission products present in masses of neutron irradiated uranium are reported. The neutron irradiated uranium is first dissolved in an aqueous solution of nitric acid. The plutonium in this solution is present as plutonous nitrate. The aqueous solution is then agitated with an organic solvent, which is not miscible with water, such as diethyl ether. The ether extracts 90% of the uraryl nitrate leaving, substantially all of the plutonium in the aqueous phase. The aqueous solution of plutonous nitrate is then oxidized to the hexavalent state, and agitated with diethyl ether again. In themore »« less
PROCESS FOR SEPARATING PLUTONIUM FROM URANIUM FROM FISSION PRODUCTS.

Patent Knighton, J.B.; Knoch, W.; Steunenberg, R.K.

Similar Records