Designed porosity materials in nuclear reactor components

Patent metadata

Field	Value
Publication number	US-9437335-B2
Application number	US-201314017173-A
Country	US
Kind code	B2
Filing date	Sep 3, 2013
Priority date	Sep 3, 2013
Publication date	Sep 6, 2016
Grant date	Sep 6, 2016

Abstract

A nuclear fuel pellet with a porous substrate, such as a carbon or tungsten aerogel, on which at least one layer of a fuel containing material is deposited via atomic layer deposition, and wherein the layer deposition is controlled to prevent agglomeration of defects. Further, a method of fabricating a nuclear fuel pellet, wherein the method features the steps of selecting a porous substrate, depositing at least one layer of a fuel containing material, and terminating the deposition when the desired porosity is achieved. Also provided is a nuclear reactor fuel cladding made of a porous substrate, such as silicon carbide aerogel or silicon carbide cloth, upon which layers of silicon carbide are deposited.

First claim

The embodiment of the invention in which an exclusive property right or privilege is claimed is defined as follows:

1. A nuclear fuel pellet, comprising:
a porous substrate; and
a plurality of layers of a fuel containing material deposited via atomic layer deposition upon said porous substrate, wherein the total porosity of the nuclear fuel pellet is between about 3 and 30 percent, wherein the porous substrate underlies the deposited layers of the fuel.

2. The nuclear fuel pellet of claim 1 , wherein the fuel containing material is fissile material selected from the group consisting of uranium dioxide, plutonium dioxide, uranium-zirconium, uranium molybdenum and uranium nitride, and combinations thereof.

3. The nuclear fuel pellet of claim 1 , wherein said porous substrate is an aerogel which defines pores which extend through the substrate.

4. The nuclear fuel pellet of claim 1 , wherein the fuel overlays substantially all of the surfaces of the substrate which define pores.

5. The nuclear fuel pellet of claim 1 , wherein the porous substrate has a density less than the density of the fuel.

6. The nuclear fuel pellet of claim 5 , wherein the porous substrate is selected from the group consisting of carbon, tungsten, beryllium oxide, and aluminum nitride.

7. The nuclear fuel pellet of claim 1 , wherein the fuel pellet has an overall density of about 90% of the density of the fuel material.

8. The nuclear fuel pellet of claim 1 , wherein the pores within the pellet have a uniform size and distribution.

9. The nuclear fuel pellet of claim 1 , wherein the pores at the surface of the pellet are smaller than the pores at the center of the pellet and wherein the size of the pores tapers between the center and the surface of the pellet.

10. The nuclear fuel pellet of claim 1 , wherein the fuel pellet has closed pores.

11. The nuclear fuel pellet of claim 1 , wherein the pores are uniformly distributed throughout the pellet and wherein the pores are spaced between about 0.02 mm and about 0.2 mm apart from each other.

12. The nuclear fuel pellet of claim 1 wherein the porosity of the pellet is between about 15 and 30 percent.

13. A nuclear reactor fuel cladding, said cladding comprising:
a porous substrate of silicon carbide, wherein the substrate is substantially a hollow tube, and wherein the porous substrate surrounds nuclear fuel without an underlying liner between said fuel and said porous substrate; and
at least one layer of silicon carbide deposited on the substrate via atomic layer deposition.

14. The nuclear reactor fuel cladding of claim 13 , wherein the porous substrate is a silicon carbide aerogel.

15. The nuclear reactor fuel cladding of claim 13 , wherein the porous substrate is a silicon carbide cloth.

16. The nuclear reactor fuel cladding of claim 13 , wherein the at least one layer of silicon carbide deposition is one atom thick.

17. The nuclear reactor fuel cladding of claim 13 , wherein the coating of silicon carbide is conformal and substantially defect free.

Assignees

• Yacout A M
• Pellin Michael J
• Stan Marius
• Uchicago Argonne Llc

Inventors

• Yacout A M
• Pellin Michael J
• Stan Marius

Classifications

• Y02E30/40

  Cross-Sectional Technologies · mapped topic

• G21C2003/045

  Physics · mapped topic

• G21C21/02 Primary

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

• G21C3/20

  with coating on fuel or on inside of casing; with non-active interlayer between casing and active material {with multiple casings or multiple active layers} · CPC title

• G21C3/07

  characterised by their material, e.g. alloys · CPC title