Method for dissolving nuclear fuel

Patent metadata

Field	Value
Publication number	US-10839968-B2
Application number	US-201716310471-A
Country	US
Kind code	B2
Filing date	Jun 21, 2017
Priority date	Jun 23, 2016
Publication date	Nov 17, 2020
Grant date	Nov 17, 2020

Abstract

A process for dissolving nuclear fuel, in particular irradiated nuclear fuel, comprising immersion of the nuclear fuel in a nitric acid solution. This dissolution process further comprises mechanical milling of the nuclear fuel, this mechanical milling being performed in the nitric acid solution during the immersion. The disclosure also relates to the use of a mill equipped with mechanical milling structure to implement the dissolution process.

First claim

What is claimed is:

1. Process for dissolving nuclear fuel, comprising immersion of the nuclear fuel in a nitric acid solution, wherein it comprises mechanical milling of the nuclear fuel, this mechanical milling being performed in the nitric acid solution during said immersion.

2. The dissolution process according to claim 1 , wherein the nitric acid solution is heated to between 90° C. and 105° C.

3. The dissolution process according to claim 1 , wherein the molar concentration of the nitric acid solution is between 1 mol/L and 10 mol/L.

4. The dissolution process according to claim 1 , wherein the nitric acid solution also comprises a neutron poison such as gadolinium.

5. The dissolution process according to claim 1 , wherein mechanical milling is performed throughout the entire duration of immersion.

6. The dissolution process according to claim 1 , wherein the nuclear fuel comprises at least one plutonium oxide and/or at least one mixed oxide of plutonium and of at least one second metal selected from among uranium, thorium, neptunium, americium and curium.

7. The dissolution process according to claim 6 , wherein, the second metal being uranium, the nuclear fuel containing at least one mixed oxide of uranium and plutonium is a MOX fuel.

8. The dissolution process according to claim 1 , wherein the nuclear fuel is irradiated nuclear fuel.

9. The dissolution process according to claim 1 , wherein the nuclear fuel comprises fabrication rejects of non-irradiated nuclear fuel.

10. The dissolution process according to claim 1 , further comprising, when the nuclear fuel is confined within a cladding, a step to de-clad the nuclear fuel, this decladding step being prior to immersion.

11. The dissolution process according to claim 1 , further comprising the implementation of a mill equipped with mechanical milling means.

12. The dissolution process according to claim 11 , wherein the mill is a bead or pebble mill.

13. The dissolution process according to claim 3 , wherein the molar concentration of the nitric acid solution is between 3 mol/L and 8 mol/L.

14. The dissolution process according to claim 12 , wherein the beads or pebbles are in zirconium dioxide.

15. Process for dissolving irradiated nuclear fuel comprising the following successive steps, taken in this order:
(a) dissolving irradiated nuclear fuel by immersion in nitric acid solution, after which a nitric dissolution solution is obtained containing dissolution fines;
(b) separating the dissolution fines from the nitric dissolution solution; and
(c) dissolving the dissolution fines separated at step (b),

wherein the dissolving step (c) comprises immersion of the dissolution fines in a nitric acid solution and mechanical milling of the dissolution fines, the mechanical milling being performed in the nitric acid solution during said immersion.

16. The process according to claim 15 further comprising, when the irradiated nuclear fuel is confined within a cladding, a step to de-clad the irradiated nuclear fuel, this decladding step preceding step (a).

17. The dissolution process according to claim 15 , wherein the irradiated nuclear fuel comprises at least one plutonium oxide and/or at least one mixed oxide of plutonium and of at least one second metal selected from among uranium, thorium, neptunium, americium and curium.

18. The dissolution process according to claim 17 , wherein, the second metal being uranium, the nuclear fuel comprising at least one mixed oxide of uranium and plutonium is MOX fuel.

Assignees

• Orano Cycle
• Commissariat Energie Atomique

Inventors

• Leturcq Gilles
• Delahaye Thibaud

Classifications

• Y02W30/50

  Reuse, recycling or recovery technologies · CPC title

• C01G43/00 Primary

  Compounds of uranium · CPC title

• G21C19/46 Primary

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

• C01G56/00

  Compounds of transuranic elements · CPC title

• Y02E30/30

  Nuclear fission reactors · CPC title