Separation of protactinum, actinium, and other radionuclides from proton irradiated thorium target

Patent metadata

Field	Value
Publication number	US-9951399-B2
Application number	US-201514681320-A
Country	US
Kind code	B2
Filing date	Apr 8, 2015
Priority date	Apr 9, 2014
Publication date	Apr 24, 2018
Grant date	Apr 24, 2018

Abstract

Protactinium, actinium, radium, radiolanthanides and other radionuclide fission products were separated and recovered from a proton-irradiated thorium target. The target was dissolved in concentrated HCl, which formed anionic complexes of protactinium but not with thorium, actinium, radium, or radiolanthanides. Protactinium was separated from soluble thorium by loading a concentrated HCl solution of the target onto a column of strongly basic anion exchanger resin and eluting with concentrated HCl. Actinium, radium and radiolanthanides elute with thorium. The protactinium that is retained on the column, along with other radionuclides, is eluted may subsequently treated to remove radionuclide impurities to afford a fraction of substantially pure protactinium. The eluate with the soluble thorium, actinium, radium and radiolanthanides may be subjected to treatment with citric acid to form anionic thorium, loaded onto a cationic exchanger resin, and eluted. Actinium, radium and radiolanthanides that are retained can be subjected to extraction chromatography to separate the actinium from the radium and from the radio lanthanides.

First claim

What is claimed is:

1. A process for separating actinium from a proton-irradiated thorium target, comprising:
forming a solution of a proton-irradiated thorium metal target, said solution comprising cationic thorium(IV) and cationic actinium(III);
evaporating the solution to form a residue;
dissolving the residue to form a second solution comprising soluble anionic complexes of thorium(IV) and soluble cationic actinium(III); and
separating the soluble anionic thorium(IV) complexes from the soluble cationic actinium(III).

2. The process of claim 1 , wherein the soluble anionic complexes of thorium(IV) comprise citrate.

3. The process of claim 1 , wherein the solution of proton irradiated thorium target further comprises hexafluorosilicate.

4. The process of claim 1 , wherein the step of separating the soluble anionic thorium(IV) complexes from the cationic actinium(III) comprises loading the solution of soluble thorium anionic thorium(IV) complexes and soluble actinium(III) complexes onto a suitable cation exchanger resin.

5. The process of claim 4 , wherein the suitable cation exchanger resin comprises a copolymer lattice of styrene and divinylbenzene with sulfonic acid functional groups attached thereto.

6. A process for separating actinium from a proton-irradiated thorium target, comprising:
forming a solution of proton-irradiated thorium target, the solution comprising soluble cationic radionuclides, the soluble cationic radionuclides comprising soluble thorium(IV) cations, soluble actinium(III) ions, and soluble radium(II) ions;
evaporating the solution to form a residue;
dissolving the residue to form a target solution comprising soluble anionic complexes of thorium(IV);
loading the target solution onto a cation exchanger resin suitable for retaining cationic species while retaining soluble cationic actinium ions and soluble cationic radium ions, eluting the cationic actinium ions and radium ions from the cation exchange resin, thereby forming an eluant;
loading the eluant onto a column of an extraction suitable for retaining the cationic actinium ions and cationic radium ions; and
eluting the radium ions from the extraction resin, and thereafter eluting the actinium ions selectively from the extraction resin.

7. The process of claim 6 , wherein the solution of proton-irradiated thorium target comprises hexafluorosilicate.

8. The process of claim 6 , wherein the extraction resin comprises N,N,N′,N′-tetra-noctyldiglycolamide.

9. The process of claim 6 , wherein the extraction resin comprises di(2-ethylhexyl) orthophosphoric acid.

10. The process of claim 6 , wherein target solution comprises a carboxylic acid.

11. The process of claim 10 , wherein the carboxylic acid is citric acid, tartaric acid, or ethylenediaminetetraacetic acid.

Assignees

• Los Alamos Nat Security Llc

Inventors

• Fassbender Michael E
• Radchenko Valery

Classifications

• C22B60/026

  liquid-liquid extraction with or without dissolution in organic solvents · CPC title

• C22B7/006

  Wet processes · CPC title

• C22B60/0295 Primary

  obtaining other actinides except plutonium · CPC title

• Y02P10/234

  Cross-Sectional Technologies · mapped topic

• Y02P10/20

  Recycling · CPC title