Targetry coupled separations

Patent metadata

Field	Value
Publication number	US-10141079-B2
Application number	US-201514757683-A
Country	US
Kind code	B2
Filing date	Dec 23, 2015
Priority date	Dec 29, 2014
Publication date	Nov 27, 2018
Grant date	Nov 27, 2018

Abstract

Targetry coupled separation refers to enhancing the production of a predetermined radiation product through the selection of a target (including selection of the target material and the material's physical structure) and separation chemistry in order to optimize the recovery of the predetermined radiation product. This disclosure describes systems and methods for creating (through irradiation) and removing one or more desired radioisotopes from a target and further describes systems and methods that allow the same target to undergo multiple irradiations and separation operations without damage to the target. In contrast with the prior art that requires complete dissolution or destruction of a target before recovery of any irradiation products, the repeated reuse of the same physical target allowed by targetry coupled separation represents a significant increase in efficiency and decrease in cost over the prior art.

First claim

What is claimed is:

1. A method for manufacturing 99 Mo radioisotope, the method comprising:
providing a source containing a first mass of uranium particles, the uranium particles having an average particle size of from 10% to 200% of a recoil distance of 99 Mo in the uranium particles;
enclosing the source in a neutronically-translucent container;
exposing the source to neutrons, thereby reducing the first mass of uranium particles in the source to a second mass of uranium particles less than the first mass and creating at least some atoms of the 99 Mo radioisotope;
removing, after exposing the source to neutrons, at least some of the atoms of the 99 Mo radioisotope from the source without removing uranium particles from the source;
wherein the removing operation further comprises:
passing an extraction material selected to dissolve the 99 Mo radioisotope through the container, thereby contacting the uranium particles with the extraction material; and
wherein the extraction material is supercritical carbon dioxide containing a ligand that dissolves the 99 Mo radioisotope and does not dissolve the uranium.

2. The method of claim 1 wherein the removing operation removes less than 0.01% of the uranium from the second mass of uranium particles in the source.

3. The method of claim 1 wherein the removing operation removes less than 0.1% of the uranium from the second mass of uranium particles in the source.

4. The method of claim 1 wherein the providing operation further comprises:
providing a source made at least partially from particles containing uranium oxide or uranium metal.

5. The method of claim 1 , wherein exposing the source further comprises exposing the container enclosing the source to neutrons.

6. The method of claim 1 further comprising:
selecting an extraction material that dissolves atoms of the 99 Mo radioisotope without changing the phase of the uranium in the source.

7. The method of claim 1 further comprising:
selecting an extraction material in which atoms of the 99 Mo radioisotope are more soluble than atoms of uranium.

8. The method of claim 6 further comprising:
determining the form of the source based on the selected extraction material.

9. The method of claim 1 further comprising:
selecting a combination of a source and an extraction material, wherein the combination allows 99 Mo radioisotope to be removed from the source after exposure to neutrons without dissolving uranium in the source.

10. The method of claim 1 wherein the ligand is selected from 8-hydroxyquinoline, a-benzoinoxime, disodium 4,5-dihydroxy-1,3-benzenedisulfonate, phosphate compounds, and diketone compounds.

11. The method of claim 1 wherein the ligand has one or more functional groups selected from hydroxyl, carbonyl, diketones, aldehyde, haloformyl, carbonate ester, carboxylate, ester, ether, peroxy, amine, carboxamide, imide, imine, nitrate, cyanate, thiol, sulfide, sulfinyl, sulfonyl, thiocyanate, isothiocyanate, phosphate, and phosphono groups.

12. The method of claim 5 further comprising:
repeatedly performing the exposing operation and the removing operations on the container without removing the uranium from the container.

13. The method of claim 11 further comprising:
removing the 99 Mo radioisotope from the extraction material.

14. The method of claim 1 further comprising:
after the removing operation, repeating the exposing operation on the same source.

15. The method of claim 1 further comprising:
removing, in addition to the 99 Mo radioisotope, an amount of one or more other fission products created during the exposing operation.

16. The method of claim 1 wherein the uranium particles are loose grains of material containing uranium.

Assignees

• Terrapower Llc

Inventors

• Czerwinski Ken
• Walter Joshua C

Classifications

• G21C19/42 Primary

  Reprocessing of irradiated fuel · CPC title

• G21G1/08

  accompanied by nuclear fission · CPC title

• B01D11/0203

  with a supercritical fluid · CPC title

• G21G2001/0036

  Molybdenum · CPC title

• G21G1/02 Primary

  in nuclear reactors (by thermonuclear reactions G21B; conversion of nuclear fuel G21C) · CPC title