Separation and recovery of molybdenum values from uranium process distillate

Patent metadata

Field	Value
Publication number	US-9567237-B2
Application number	US-201314079351-A
Country	US
Kind code	B2
Filing date	Nov 13, 2013
Priority date	Nov 16, 2012
Publication date	Feb 14, 2017
Grant date	Feb 14, 2017

Abstract

A method for treating process distillate heavies produced during uranium fluoride purification is described. The heavies contain primarily uranium hexafluoride, UF 6 , and molybdenum oxytetrafluoride, MoOF 4 . The uranium hexafluoride is removed via distillation at reduced pressure leaving essentially MoOF 4 containing <0.1% of residual uranium hexafluoride. This mixture is hydrolyzed in water, then treated with a solution of sodium hydroxide until a pH of at least 7.5 is reached. The precipitated sodium diuranate and sodium fluoride are removed by filtration. The filtrate is reacted with calcium chloride to precipitate the molybdenum values as calcium molybdate containing trace quantities of calcium fluoride.

First claim

What is claimed is:

1. A method of manufacturing uranium hexafluoride comprising the steps of:
feeding crude uranium hexafluoride comprising molybdenum impurities into a boiler still for processing;
distilling at an elevated pressure greater than atmospheric pressure said crude uranium hexafluoride in said boiler still such that substantially pure uranium hexafluoride is recovered as a first light distillate product; and
distilling a heavy distillate product from said elevated pressure distillation, the product including uranium hexafluoride and molybdenum oxytetrafluoride, at a reduced pressure lower than atmospheric pressure to recover substantially pure uranium hexafluoride as a second light distillate product.

2. The method according to claim 1 , further comprising the step of hydrolzing a solid heavy distillate product from said reduced pressure distillation with water to form a solution comprising hydrofluoric acid, hydrolyzed molybdenum, and uranyl fluoride.

3. The method according to claim 2 , further comprising the step of reacting the solution with sodium hydroxide to precipitate uranium as sodium diuranate and fluoride as sodium fluoride.

4. The method according to claim 3 , further comprising the step of reacting a liquor from the sodium hydroxide treatment step with a calcium salt to precipitate molybdenum as calcium molybdate.

5. The method according to claim 4 , wherein the calcium salt is calcium chloride.

6. The method according to claim 4 , further comprising the step of isolating the calcium molybdate by filtration and drying.

7. The method according to claim 6 , wherein the isolated calcium molybdate contains less than about 300 ppm uranium.

8. The method according to claim 7 , wherein the isolated calcium molybdate contains less than about 1 ppm uranium.

9. The method of claim 1 , wherein the reduced pressure distillation is conducted at a pressure of less than about 50 kPa.

10. The method of claim 1 , wherein said the reduced pressure distillation is conducted at a pressure of between about 20 kPa and 35 kPa.

11. The method of claim 1 , wherein the reduced pressure distillation is conducted at a pressure of about 28 kPa.

12. The method of claim 1 , wherein the reduced pressure distillation is conducted at a temperature of between about 50° C. and 70° C.

13. The method of claim 1 , wherein the reduced pressure distillation is conducted at a temperature of about 60° C.

14. A method of manufacturing uranium hexafluoride comprising the steps of:
feeding crude uranium hexafluoride comprising molybdenum impurities into a boiler still for processing;
distilling at an elevated pressure greater than atmospheric pressure the crude uranium hexafluoride in the boiler still such that substantially pure uranium hexafluoride is recovered as a first light distillate product;
distilling a heavy distillate product from said elevated pressure distillation step, the product including uranium hexafluoride and molybdenum oxytetrafluoride, at a reduced pressure of less than about 50 kPa to recover substantially pure uranium hexafluoride as a second light distillate product;
hydrolyzing a heavy distillate product from said reduced pressure distillation step with water to form a solution comprising hydrofluoric acid, hydrolyzed molybdenum, and uranyl fluoride;
reacting the solution with sodium hydroxide to precipitate uranium as sodium diuranate and fluoride as sodium fluoride; and
reacting a liquor from said sodium hydroxide treatment step with a calcium salt to precipitate molybdenum as calcium molybdate.

15. The method of claim 14 , wherein said the reduced pressure distillation is conducted at a pressure of between about 20 kPa and 35 kPa.

16. The method of claim 14 , wherein said reduced pressure distillation step is conducted at a temperature of between about 50° C. and 70° C.

17. The method of claim 14 , wherein the calcium molybdate precipitate contains less than about 300 ppm uranium.

18. The method of claim 17 , wherein the calcium molybdate precipitate contains less than about 1 ppm uranium.

19. The method of claim 14 , wherein the reduced pressure distillation is conducted at a pressure of less than about 50 kPa.

Assignees

• Honeywell Int Inc

Inventors

• Nalewajek David
• Beckman Kent

Classifications

• C01G39/00

  Compounds of molybdenum · CPC title

• C01G43/00

  Compounds of uranium · CPC title

• C01G43/063 Primary

  Hexafluoride (UF6) · CPC title

• C01P2006/80

  Compositional purity · CPC title