Method for the control of the composition and physical properties of solid uranium oxides

• US 5,875,385 A
• Filed: 01/15/1997
• Issued: 02/23/1999
• Est. Priority Date: 01/15/1997
• Status: Expired due to Fees

• Current Assignee: Molten Metal Technology Incorporated
• Original Assignee: Molten Metal Technology Incorporated
• Inventors: Stephenson, Michael J., Haas, Paul A., Eby, Robert S.
• Primary Examiner(s): MAI, NGOCLAN THI
• Application Number:
  US08/783,264
• Time in Patent Office: 769 Days
• Field of Search: 423/258, 423/260, 423/261
• US Class Current: 423/260
• CPC Class Codes: C01G 43/01 Oxides; Hydroxides
• CPC Class Codes: C01G 43/025 Uranium dioxide
• CPC Class Codes: Y02P 20/129 Energy recovery, e.g. by cogeneration, H2recovery or pressure recovery turbines

Abstract

The present invention provides a method for varying and controlling the chemical composition and physical properties of the uranium oxide solids produced by the thermal conversion of UF₆. The method allows the production of predominantly UO₂, U₃ O₈, or UO₃ interchangeably from the same reactor simply by controlling the hydrogen and oxygen contents of the feed relative to uranium. The temperature profile of the thermal reactor is established by specifying the preheat of the feed prior to mixing, the feed composition, and the reactor wall temperature to thus vary and control the physical properties of the resulting solids according to the end use of the uranium product.

Claims

1. A method for controlling the composition and physical properties of uranium oxides formed in a high temperature chemical reactor having a reaction zone for the dry thermal conversion of UF₆ comprising the steps of:

1) preheating gaseous reactant streams necessary for the conversion of UF₆ to uranium oxides and HF comprising two or more gas streams wherein at least one of the streams is preheated to a temperature of 700°

-1000°

C. including

a) a first stream formed of a gaseous mixture of UF₆ and O₂, and

b) a second stream formed of a combination of gases containing hydrogen selected from the group consisting of H₂, H₂ O, NH₃ and CH₄ and oxygen in a combined form selected from the group consisting of H₂ O and CO₂ ;

said reactant streams being of a preselected feed composition for control of reaction heat and to favor the formation of predominately one of said uranium oxides;

2) then mixing said heated streams; and

3) injecting the mixed reactant streams directly into said reaction zone while maintaining the temperature and pressure to optimally produce one of said uranium oxides with the desired physical properties.

2. The method of claim 1 wherein said preselected feed composition is selected to provide an excess of H₂ in the reactor off-gas to thereby produce predominately UO₂ and said temperature profile of said reactor is within the range of 700°

to 1100°

C.

3. The method of claim 2 wherein said hydrogen is provided in a feed atom ratio to uranium (H/U) of at least 6 to 1 and said oxygen is provided in a feed atom ratio to uranium (O/U) of approximately 2 to 1.

4. The method of claim 1 wherein said temperature profile of said reactor is 800°

to 1500°

C. to produce a more sintered and less reactive product.

5. The method of claim 1 wherein said preselected feed composition is selected to provide an excess of O₂ in the reactor off-gas to thereby produce predominately U₃ O₈ and said temperature profile of said reactor is maintained within the range of 900°

to 1100°

C.

6. The method of claim 5 wherein said oxygen is provided in a feed atom ratio to uranium (U/O) of approximately 3 to 1 and said hydrogen is provided in a feed ratio to uranium (H/U) of approximately 6 to 1.

7. The method of claim 1 wherein said temperature of said reactor is 800°

to 1500°

C. to produce a more sintered and less reactive product.

8. The method of claim 1 wherein said preselected feed composition is selected to provide an excess of O₂ in the reactor off-gas to thereby favor the production of UO₃ and said temperature profile of said reactor is maintained within the range of 600°

to 900°

C.

9. The method of claim 2 wherein said oxygen is provided in a feed ratio to uranium (O/U) of at least 3 to 1 and said hydrogen is provided in a feed atom ratio to uranium (H/U) of approximately 6 to 1.

10. The method of claim 1 is carried out wherein the temperature profile of the integrated thermal reactor is varied primarily by controlling the temperature of the preheater feed gas, the heat of reaction, and the temperature of the reactor wall to produce uranium oxides having preselected physical properties.

11. The method of claim 8 wherein a fraction of the stoichiometric oxygen requirement is provided with O₂ to increase the heat of reaction and the maximum temperature of the product.

12. The method of claim 8 wherein said temperature profile is controlled by varying the inert gas content of the feed gas.

13. The method of claim 8 wherein said temperature profile is controlled by varying the total pressure of the reactor.

14. The method of claim 8 wherein said temperature profile is controlled by varying the residence time in the reaction zone.

15. The method of claim 1 wherein the pressure of the reactor is varied and controlled to establish and maintain the fluorine content of the final uranium oxide product.

16. The method of claim 15 wherein the pressure of the reactor is reduced to lower the fluoride content of the final uranium oxide product.

17. The method of claim 16 wherein the reactor pressure is reduced to less than 100 torr to minimize the fluoride content of the final uranium oxide product.

18. The method of claim 1 wherein an effective amount of fluoride is left in the uranium solid by control of the feed composition and/or reaction temperature to facilitate compaction and sintering of the final uranium oxide product to higher densities.

19. The method of claim 18 wherein the feed H/U atom ratio near or slightly below the stoichiometric requirement of 6 is used to increase the amount of UF₄ in the uranium solids to increase solid product density.

20. The method of claim 18 wherein the feed O/U atom ratio near or slightly below the stoichiometric ratio of 2 is used to increase the amounts of UF₄ in the uranium solids.