Recovery of uranium from an irradiated solid target after removal of molybdenum-99 produced from the irradiated target

Patent metadata

Field	Value
Publication number	US-9793023-B2
Application number	US-201314042115-A
Country	US
Kind code	B2
Filing date	Sep 30, 2013
Priority date	Sep 26, 2013
Publication date	Oct 17, 2017
Grant date	Oct 17, 2017

Abstract

A process for minimizing waste and maximizing utilization of uranium involves recovering uranium from an irradiated solid target after separating the medical isotope product, molybdenum-99, produced from the irradiated target. The process includes irradiating a solid target comprising uranium to produce fission products comprising molybdenum-99, and thereafter dissolving the target and conditioning the solution to prepare an aqueous nitric acid solution containing irradiated uranium. The acidic solution is then contacted with a solid sorbent whereby molybdenum-99 remains adsorbed to the sorbent for subsequent recovery. The uranium passes through the sorbent. The concentrations of acid and uranium are then adjusted to concentrations suitable for crystallization of uranyl nitrate hydrates. After inducing the crystallization, the uranyl nitrate hydrates are separated from a supernatant. The process results in the purification of uranyl nitrate hydrates from fission products and other contaminants. The uranium is therefore available for reuse, storage, or disposal.

First claim

What is claimed is:

1. A process for recovering uranium and molybdenum-99 (Mo-99) from an irradiated solid target, comprising:
irradiating a solid target comprising uranium to produce the irradiated solid target having fission products comprising Mo-99;
dissolving the irradiated solid target to form a first solution and conditioning the first solution to comprise a first nitric acid concentration and a first uranium concentration;
oxidizing the Mo-99 by adding an inorganic oxidant to the first solution to provide a second solution in which the Mo-99 is in a +VI oxidation state;
contacting the second solution with a solid sorbent, whereby uranium remains in the second solution while the Mo-99 is bound to the solid sorbent;
adjusting the first nitric acid concentration and the first uranium concentration in the second solution to provide a second nitric acid concentration and a second uranium concentration suitable for formation of uranyl nitrate hydrate crystals;
inducing formation of uranyl nitrate hydrate crystals; and
separating the uranyl nitrate hydrate crystals from the second solution.

2. The process of claim 1 , wherein the inducing formation of uranyl nitrate hydrate crystals comprises cooling the second solution to a temperature effective for the formation of the uranyl nitrate hydrate crystals.

3. The process of claim 1 , wherein the inducing formation of uranyl nitrate hydrate crystals comprises evaporating the second solution under reduced pressure.

4. The process of claim 1 , further comprising purifying the uranyl nitrate hydrate crystals after separating the uranyl nitrate hydrate crystals.

5. The process of claim 1 , wherein the uranium comprises low-enriched uranium (LEU).

6. A process for recovering uranium and Mo-99 from an irradiated solid target, comprising:
irradiating a solid target comprising uranium to produce the irradiated solid target having fission products comprising Mo-99;
dissolving the irradiated solid target to form a first solution and conditioning the first solution to comprise a nitric acid concentration of about 0.01 M to about 2 M, and a uranium concentration of about 50 gU/L to about 350 gU/L;
oxidizing the Mo-99 by adding an inorganic oxidant to the first solution to provide a second solution in which the Mo-99 is in a +VI oxidation state;
contacting the second solution with a solid sorbent, whereby uranium remains in the second solution while the Mo-99 is bound to the solid sorbent;
adjusting the nitric acid concentration in the second solution to about 4 M to about 8 M, and the uranium concentration in the second solution to about 350 gU/L to about 650 gU/L;
inducing formation of uranyl nitrate hydrate crystals; and
separating the uranyl nitrate hydrate crystals from the second solution.

7. The process of claim 6 , wherein the inducing formation of uranyl nitrate hydrate crystals comprises cooling the second solution to a temperature effective for the formation of the uranyl nitrate hydrate crystals.

8. The process of claim 6 , wherein the inducing formation of uranyl nitrate hydrate crystals comprises evaporating the second solution under reduced pressure.

9. The process of claim 6 , further comprising purifying the uranyl nitrate hydrate crystals after separating the uranyl nitrate hydrate crystals.

10. The process of claim 6 , wherein the uranium comprises LEU.

11. The process of claim 1 , further comprising recycling the nitric acid.

12. The process of claim 6 , further comprising recycling the nitric acid.

Assignees

• Los Alamos Nat Security Llc

Inventors

• Reilly Sean Douglas
• May Iain
• Copping Roy
• Dale Gregory Edward

Classifications

• G21G2001/0036

  Molybdenum · CPC title

• G21G2001/0094

  Other isotopes not provided for in the groups listed above · CPC title

• Y02W30/883

  Cross-Sectional Technologies · mapped topic

• G21C19/46

  Aqueous processes {, e.g. by using organic extraction means, including the regeneration of these means} · CPC title

• G21G1/04 Primary

  outside nuclear reactors or particle accelerators · CPC title