System for salt removal from uranium metal

Patent metadata

Field	Value
Publication number	US-12180562-B2
Application number	US-202016845558-A
Country	US
Kind code	B2
Filing date	Apr 10, 2020
Priority date	Apr 10, 2020
Publication date	Dec 31, 2024
Grant date	Dec 31, 2024

Abstract

According to one aspect of the invention, a system to separate salt from uranium. The system has a vessel, a heater, a pump, and a condenser. The vessel is adapted to receive a uranium that has a salt concentration. The heater heats the uranium for a period of time, causing the salt to turn into a salt vapor and the uranium to melt. The melted uranium releases the salt vapor. The pump circulates an inert gas that carries the salt vapor away from the melted uranium. The condenser is adapted to receive the salt vapor.

First claim

The invention claimed is:

1. A system to separate salt from uranium, the system comprising:
(a) a vessel adapted to receive uranium, the uranium having a salt concentration;
(b) a heater placed within the vessel, the heater adapted to heat uranium to approximately 1200° C., the heater heating the uranium to about 1200° C. for a period of time causing the salt to turn into a salt vapor, the heated uranium releasing the salt vapor;
(c) a pump in fluid communication with an interior of the vessel, the pump configured to circulate an inert gas within at least the interior whereby the inert gas carries the salt vapor away from the melted uranium;
(d) a condenser placed within the vessel and in fluid communication with at least the heater and adapted to receive the salt vapor; and
(e) a molybdenum alloy heat shield located between the condenser and the heated uranium.

2. The system of claim 1 wherein the vessel is made from stainless steel or other pure metals or alloys compatible with liquid uranium.

3. The system of claim 1 additionally including a shredder, the shredder adapted to shred the uranium prior to heating.

4. The system of claim 1 wherein the pump is external to the vessel.

5. The system of claim 1 wherein the pump comprises a compressor and a heat exchanger.

6. The system of claim 1 additionally comprising a least one measurement probe.

7. The system of claim 6 wherein the measurement probe is a level probe.

8. The system of claim 6 wherein the measurement probe is a density probe.

9. The system of claim 1 wherein the uranium is received within a crucible within the vessel, the crucible is adapted to be compatible with liquid uranium.

Assignees

• Us Energy
• Us Dept Energy

Inventors

• Williamson Mark A
• Willit James L
• Wiedmeyer Stanley G
• Johnson Terry R
• Figueroa Javier
• Cruse Terry Alan

Classifications

• C22B9/006

  with use of an inert protective material including the use of an inert gas · CPC title

• C22B60/0286

  refining, melting, remelting, working up uranium · CPC title

• F27B2014/004

  Process involving a smelting step, e.g. vaporisation · CPC title

• F27B2014/0875

  Two zones or chambers, e.g. one used for charging · CPC title

• C22B9/05

  Refining by treating with gases, e.g. gas flushing {also refining by means of a material generating gas in situ} · CPC title