OXIDATION OF TRANSURANIC ELEMENTS

Title: OXIDATION OF TRANSURANIC ELEMENTS

Full Record
Other Related Research

Abstract

A method is reported for oxidizing neptunium or plutonium in the presence of cerous values without also oxidizing the cerous values. The method consists in treating an aqueous 1N nitric acid solution, containing such cerous values together with the trivalent transuranic elements, with a quantity of hydrogen peroxide stoichiometrically sufficient to oxidize the transuranic values to the hexavalent state, and digesting the solution at room temperature.

Inventors:: Moore, R.L.

Publication Date:: Tue Feb 17 00:00:00 EST 1959

Research Org.:: Originating Research Org. not identified

OSTI Identifier:: 4247451

Patent Number(s):: US 2874025

Assignee:: U.S. Atomic Energy Commission DTIE; NSA-13-015127

NSA Number:: NSA-13-015127

Resource Type:: Patent

Resource Relation:: Other Information: Orig. Receipt Date: 31-DEC-59

Country of Publication:: United States

Language:: English

Subject:: CHEMISTRY; ACTINIDES; CERIUM COMPOUNDS; CHEMICAL REACTIONS; HYDROGEN PEROXIDES; MIXING; NEPTUNIUM; NITRIC ACID; OPERATION; OXIDATION; PATENT; PLUTONIUM; QUANTITY RATIO; SOLUTIONS; TEMPERATURE; WATER

Citation Formats


                    Moore, R.L. OXIDATION OF TRANSURANIC ELEMENTS.  United States: N. p., 1959. 
        Web.

Copy to clipboard


                    Moore, R.L. OXIDATION OF TRANSURANIC ELEMENTS.  United States.

Copy to clipboard


                    Moore, R.L. Tue .  
        "OXIDATION OF TRANSURANIC ELEMENTS".  United States.

Copy to clipboard


                    
@article{osti_4247451,

  title        = {OXIDATION OF TRANSURANIC ELEMENTS},

  author       = {Moore, R.L.},

  abstractNote = {A method is reported for oxidizing neptunium or plutonium in the presence of cerous values without also oxidizing the cerous values. The method consists in treating an aqueous 1N nitric acid solution, containing such cerous values together with the trivalent transuranic elements, with a quantity of hydrogen peroxide stoichiometrically sufficient to oxidize the transuranic values to the hexavalent state, and digesting the solution at room temperature.},

  doi          = {},

  journal      = {},

  number       = ,

  volume       = ,

  place        = {United States},

  year         = {Tue Feb 17 00:00:00 EST 1959},

  month        = {Tue Feb 17 00:00:00 EST 1959}

}

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 OSTI.GOV collections:

METHOD OF RECOVERING TRANSURANIC ELEMENTS OF AN ATOMIC NUMBER BELOW 95

Patent Seaborg, G.T. ; James, R.A.

The concentration of neptanium or plutonium by two carrier precipitation steps with identical carriers but using (after dissolution of the first carrier in nitric acid) a reduced quantity of carrier for the second precipitation is discussed. Carriers suitable are uranium(IV) hypophosphate, uranium(IV) pyrophosphate, uranium(IV) oxalate, thorium oxalate, thorium citrate, thorium tartrate, thorium sulfide, and uranium(IV) sulfide.
SEPARATION OF TRANSURANIC ELEMENTS FROM RARE EARTH COMPOUNDS

Patent Kohman, T.P.

A process of separating neptunium and plutonium values from rare earths and alkaline earth fission products present on a solid mixed actinide carrier (Th or U(IV) oxalate or fluoride) --fission product carrier (LaF/sub 3/, CeF/sub 3/, SrF/sub 2/, CaF/sub 2/, YF/sub 3/, La oxalate, cerous oxalate, Sr oxalate, Ca oxalate or Y oxalate) by extraction of the actinides at elevated temperature with a solution of ammonium fluoride and/or ammonium oxalate is described. Separation of the fission-product-containing carriers from the actinide solution formed and precipitation of the neptunium and plutonium from the solution with mineral acid are also accomplished. (AEC)
OXIDATION-REDUCTION REACTIONS WITH TRANSURANIC ELEMENTS IN SOLUTION. (in French)

Technical Report Gourisse, D.
Recoverable immobilization of transuranic elements in sulfate ash

Patent Greenhalgh, Wilbur O.

Disclosed is a method of reversibly immobilizing sulfate ash at least about 20% of which is sulfates of transuranic elements. The ash is mixed with a metal which can be aluminum, cerium, samarium, europium, or a mixture thereof, in amounts sufficient to form an alloy with the transuranic elements, plus an additional amount to reduce the transuranic element sulfates to elemental form. Also added to the ash is a fluxing agent in an amount sufficient to lower the percentage of the transuranic element sulfates to about 1% to about 10%. The mixture of the ash, metal, and fluxing agent ismore »« less
Full Text Available
Process to separate transuranic elements from nuclear waste

Patent Johnson, Terry R. ; Ackerman, John P. ; Tomczuk, Zygmunt ; ...

A process for removing transuranic elements from a waste chloride electrolytic salt containing transuranic elements in addition to rare earth and other fission product elements so the salt waste may be disposed of more easily and the valuable transuranic elements may be recovered for reuse. The salt is contacted with a cadmium-uranium alloy which selectively extracts the transuranic elements from the salt. The waste salt is generated during the reprocessing of nuclear fuel associated with the Integral Fast Reactor (IFR).
Full Text Available

Similar Records