Method to produce salts containing actinide halides

Patent metadata

Field	Value
Publication number	US-11104585-B2
Application number	US-201816029403-A
Country	US
Kind code	B2
Filing date	Jul 6, 2018
Priority date	Jul 6, 2018
Publication date	Aug 31, 2021
Grant date	Aug 31, 2021

Abstract

A method of producing uranium halides is disclosed in which chlorine gas is introduced into a liquid uranium-nickel alloy. NaCl salt is surrounding the crucible containing the liquid uranium-nickel alloy, producing a eutectic mixture of NaCl—UCl 3 . Upon chlorination, the metal halide dissolves in the matrix salt forming a solution. Adding the reactant metal, uranium to the nickel, the alloy is able to remain molten throughout processing. The liquid metal alloy may be removed from the salt bath, while the halogen gas continues to enter the system through the sparge until the desired composition of NaCl—UCl 3 —UCl 4 is achieved. The method and system can be used to produce other metal halide salts such as actinide, lanthanide or transition metal halides contained in a matrix salt consisting of alkali and/or alkaline earth halides.

First claim

The invention claimed is:

1. A method for producing an actinide metal halide, the method comprising:
a) establishing a molten salt bath;
b) generating a liquid alloy containing an actinide metal of the metal halide in a crucible;
c) submerging the crucible containing the liquid alloy in the molten salt bath;
d) contacting the liquid alloy with halogen in a first reaction to form a first metal halide that dissolves in the molten salt bath, wherein the metal is more electropositive than the halogen;
e) removing unreacted liquid alloy from the molten salt bath by removing the crucible from the molten salt bath; and
f) contacting the first metal halide with halogen in the molten salt bath to initiate a second reaction between the halogen and the metal halide to form a second metal halide.

2. The method of claim 1 wherein the molten salt bath generated in the establishing step is comprised of alkali and alkaline earth salts comprising alkali and alkaline earth fluorides, chlorides, bromides, iodides or combinations thereof.

3. The method of claim 1 wherein after the contacting the alloy with halogen step the molten salt bath contains halide of actinide elements selected from the group consisting of Th, U, Np, Pu, Am, Cm, and combinations thereof.

4. The method of claim 1 wherein the liquid alloy contains actinide metals selected from the group consisting of Th, U, Np, Pu, Am, Cm, and combinations thereof.

5. The method of claim 1 , wherein the liquid alloy further comprises an element selected from group consisting of cobalt, iron, nickel, bismuth, gallium, aluminum, cadmium and combinations thereof.

6. The method of claim 1 , wherein a surface of liquid alloy is formed beneath a surface of the molten salt bath and the halogen gas is injected under the surface of the surface of the liquid alloy.

7. The method of claim 1 , wherein the second metal halide is part of a eutectic mixture and the second metal halide is removed from the molten salt bath.

8. The method of claim 1 wherein the alloy containing the actinide metal of the metal halide is generated before the crucible is submerged into the molten salt bath.

9. The method of claim 1 wherein the first reaction is a direct reaction between the liquid alloy and halogen.

10. The method of claim 1 wherein the contacting the alloy with halogen in a first reaction step further comprises providing additional metal to the crucible to allow for continuous operation.

Assignees

• Uchicago Argonne Llc

Inventors

• Williamson Mark A
• Willit James L

Classifications

• G21C19/46

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

• C25C3/34 Primary

  of metals not provided for in groups C25C3/02 - C25C3/32 · CPC title

• C01G43/08

  Chlorides · CPC title

• C01G43/003 Primary

  Preparation involving a liquid-liquid extraction, an adsorption or an ion-exchange · CPC title

• G21C19/50

  of irradiated fluid fuel {, e.g. regeneration of fuels while the reactor is in operation} · CPC title