Uranium dioxide nuclear fuel pellet having metallic microcells and fabricating method thereof

Patent metadata

Field	Value
Publication number	US-9679666-B2
Application number	US-201314061662-A
Country	US
Kind code	B2
Filing date	Oct 23, 2013
Priority date	Dec 31, 2012
Publication date	Jun 13, 2017
Grant date	Jun 13, 2017

Abstract

Disclosed is a uranium dioxide nuclear fuel pellet, which includes metallic microcell partitions having a high protection capacity for fission products and a high thermal conductivity simultaneously. These metal microcell partitions are arranged in the nuclear fuel pellet to trap fission products. Further disclosed is a method of making the uranium dioxide nuclear fuel pellet. The method includes providing a mixture of uranium dioxide powder and additive powder of Cr-containing compound or Mo-containing compound; compressing the powder mixture to form a green pellet; and then sintering the green pellet under reducing gas environment to form the metallic microcell partitions.

First claim

What is claimed is:

1. A method of making a uranium dioxide nuclear fuel pellet, the method comprising:
providing a mixture of uranium dioxide powder and additive powder consisting essentially of a Cr-containing compound or a Mo-containing compound;
compressing the powder mixture to form a green pellet; and
sintering the green pellet under reducing gas environment to convert at least part of the additive powder into liquid which permeates between grains of the uranium dioxide thereby forming micro-partitions consisting essentially of Cr or Mo and defining microcells in which the uranium dioxide is contained, the reducing gas environment comprising hydrogen gas and water vapor, wherein during sintering the green pellet is maintained to a first temperature under humid hydrogen gas and subsequently cooled to a second temperature under dry hydrogen gas having 0.1% moisture or less, the humid hydrogen gas containing more moisture than the dry hydrogen gas, the second temperature being lower than the first temperature.

2. The method of claim 1 , wherein, in the mixture, a ratio of the additive powder with respect to the uranium dioxide powder is about 0.1%to about 10.0% by weight.

3. The method of claim 1 , wherein the additive powder comprises at least one selected from the group consisting of oxide, nitride, sulfide, fluoride, chloride, stearate, carbonate, nitrate and phosphate.

4. The method of claim 1 , wherein the sintering temperature is about 1600° C. to about 1800° C.

5. The method of claim 1 , wherein the Cr-containing compound or the Mo-containing compound is chromium oxide or molybdenum oxide, wherein sintering causes to form micro-partitions consisting essentially of chromium oxide or molybdenum oxide, which are then changed to the micro-partitions consisting essentially of Cr or Mo by reduction in the reducing gas environment.

6. The method of claim 1 , wherein grains of the uranium dioxide having a size of about 30 μm to about 400 μm are formed during sintering.

7. The method of claim 1 , wherein the humid hydrogen gas having 1.6% moisture therein.

8. The method of claim 1 , wherein prior to being maintained at the first temperature, the green pellet is heated under dry hydrogen gas having 0.1% moisture or less.

9. The method of claim 1 , wherein prior to being maintained at the first temperature, the green pellet is heated at a heating rate of 300° C. per hour under dry hydrogen gas having 0.1% moisture or less.

10. The method of claim 1 , wherein prior to being maintained at the first temperature, the green pellet is heated under dry hydrogen gas having 0.1% moisture or less, wherein the humid hydrogen gas having 1.6% moisture therein.

11. The method of claim 1 , wherein the first temperature is 1720° C. and the second temperature is 1600° C.

12. The method of claim 1 , wherein cooling to the second temperature is at a cooling rate of 300° C. per hour under the dry hydrogen gas having 0.1% moisture or less.

13. The method of claim 1 , wherein subsequent to cooling to the second temperature, the cooled pellet is maintained at the second temperature for 10 hours and subsequently cooled to lower temperature.

Assignees

• Korea Atomic Energy Res
• Korea Hydro & Nuclear Power Co
• Korea Hydro & Nuclear Power Co

Inventors

• Kim Keon-Sik
• Koo Yang-Hyun
• Kim Jong-Hun
• Oh Jangsoo
• Rhee Young Woo
• Kim Dong-Joo
• Yang Jae-Ho

Classifications

• G21C21/02

  Manufacture of fuel elements or breeder elements contained in non-active casings · CPC title

• G21C3/044 Primary

  Fuel elements with porous or capillary structure · CPC title

• G21C3/045

  Pellets · CPC title

• G21C3/17

  Means for storage or immobilisation of gases in fuel elements · CPC title

• G21C3/58

  Solid reactor fuel {Pellets made of fissile material} · CPC title