Porous UO2 sintered pellet for electroreduction process, and preparation method thereof

Patent metadata

Field	Value
Publication number	US-9303298-B2
Application number	US-201313865786-A
Country	US
Kind code	B2
Filing date	Apr 18, 2013
Priority date	Apr 20, 2012
Publication date	Apr 5, 2016
Grant date	Apr 5, 2016

Abstract

Porous UO 2 sintered pellets to be fed into an electrolytic reduction process for the purpose of metallic nuclear fuel recovery, include one or more hollow spaces formed from the surfaces toward the interiors thereof. When the porous UO 2 sintered pellets are used in the electrolytic reduction process, the efficiency increases.

First claim

What is claimed is:

1. A method for fabricating porous UO 2 sintered pellets to be fed into an electrolytic reduction process for the purpose of metallic nuclear fuel recovery, the porous UO 2 sintered pellets having one or more hollow spaces formed in a surface of the pellets, the one or more, hollow spaces extending inwardly from the surface toward interiors thereof, the method comprising the steps of:
forming a powder containing U 3 O 8 by oxidizing spent nuclear fuel containing uranium dioxide (UO 2 ) (step 1);
compacting the powder formed in step 1 into green pellets with hollow spaces formed therein (step 2);
fabricating UO 2+x sintered pellets by sintering the porous U 3 O 8 green pellets fabricated in step 2 at 1200 to 1600° C., in an atmospheric gas (step 3); and
forming UO 2 sintered pellets by cooling the UO 2+x sintered pellets in step 3 to room temperature, and reducing the same at 1000 to 1400° C., in a reducing atmosphere (step 4).

2. A method for fabricating porous UO 2 sintered pellets to be fed into an electrolytic reduction process for the purpose of metallic nuclear fuel recovery, the porous UO 2 sintered pellets having one or more hollow spaces formed in a surface of the pellets, the one or more, hollow spaces extending inwardly from the surface toward interiors thereof, the method comprising the steps of:
forming a powder containing U 3 O 8 by oxidizing spent nuclear fuel containing uranium dioxide (UO 2 ) (step 1);
compacting the powder formed in step 1 into green pellets with hollow spaces formed therein (step 2); and
fabricating UO 2 sintered pellets by sintering the U 3 O 8 green pellets fabricated in step 2 at 1000 to 1600° C., in an atmospheric gas, and cooling the same for reduction, by changing the atmosphere to a reducing atmospheric gas (step 3).

3. The method as set forth in claim 2 , further comprising a step of homogenizing the powder formed in step 1 prior to compacting the powder in step 2.

4. The method as set forth in claim 3 , wherein the homogenizing is performed by milling.

5. The method as set forth in claim 4 , wherein the milling is performed with a mill selected from a group consisting of a dynamic mill, ball mill, basket mill, attrition mill, bead mill, and hammer mill.

6. The method as set forth in claim 2 , wherein the oxidizing is performed in an oxidizing atmosphere at a temperature ranging between 400° C. and 500° C.

7. The method as set forth in claim 2 , wherein the green pellet is compacted under compaction pressure ranging between 100 and 500 MPa.

8. The method as set forth in claim 2 , prior to the sintering, further comprising capturing of a nuclear fission product by step-wise heating the compacted green pellets to a sintering temperature.

9. The method as set forth in claim 1 , further comprising a step of homogenizing the powder formed in step 1 prior to compacting the powder in step 2.

10. The method as set forth in claim 9 , wherein the homogenizing is performed by milling.

11. The method as set forth in claim 10 , wherein the milling is performed with a mill selected from a group consisting of a dynamic mill, ball mill, basket mill, attrition mill, bead mill, and hammer mill.

12. The method as set forth in claim 1 , wherein the oxidizing is performed in an oxidizing atmosphere at a temperature ranging between 400° C. and 500° C.

13. The method as set forth in claim 1 , wherein the green pellets are compacted under compaction pressure ranging between 100 and 500 MPa.

14. The method as set forth in claim 1 , prior to the sintering, further comprising capturing of a nuclear fission product by step-wise heating the compacted green pellets to a sintering temperature.

15. The method as set forth in claim 1 , wherein the porous UO 2 sintered pellet is configured in a shape of a cylindrical or polygonal pillar.

16. The method as set forth in claim 1 , wherein the one or more hollow spaces pass through the porous UO 2 sintered pellet in a lengthwise direction.

17. The method as set forth in claim 2 , wherein the porous UO 2 sintered pellet is configured in a shape of a cylindrical or polygonal pillar.

18. The method as set forth in claim 2 , wherein the one or more hollow spaces pass through the porous UO 2 sintered pellet in a lengthwise direction.

Assignees

• Korea Atomic Energy Res

Inventors

• Na Sang-Ho
• Song Dae-Yong
• Kim Ki Hong
• Bae Sang-Oh
• Park Jong-Man
• Ji Chul Goo
• Hwang Hyong Jin

Classifications

• G21C21/00

  Apparatus or processes specially adapted to the manufacture of reactors or parts thereof (in general section B, e.g. B23) · CPC title

• G21C3/623

  Oxide fuels · CPC title

• C01G43/01

  Oxides; Hydroxides · CPC title

• C01P2006/12

  Surface area · CPC title

• Y02E30/38

  Cross-Sectional Technologies · mapped topic