Zirconium-coated silicon carbide fuel cladding for accident tolerant fuel application

Patent metadata

Field	Value
Publication number	US-10872701-B2
Application number	US-201615178745-A
Country	US
Kind code	B2
Filing date	Jun 10, 2016
Priority date	Jun 10, 2016
Publication date	Dec 22, 2020
Grant date	Dec 22, 2020

Abstract

The invention relates to a multi-component cladding for a nuclear fuel rod that includes a combination of ceramic and metal components. More particularly, the invention is directed to a cladding that includes a ceramic composite having a zirconium composition deposited thereon to form a zirconium coated ceramic composite. The ceramic composite includes a ceramic matrix and a plurality of ceramic fibers. The cladding is effective to protect the contents of the cladding structure from exposure to high temperature environments during various load conditions of a nuclear reactor.

First claim

What is claimed is:

1. A nuclear fuel rod cladding in a nuclear reactor having a coolant flowing therein, the nuclear fuel rod cladding comprising:
a base ceramic composite structured to form a shape that has an interior surface, an exterior surface, and an inner cavity, comprising:
a ceramic matrix; and
a plurality of ceramic fibers;

nuclear fuel positioned within the inner cavity of the base ceramic composite; and
a coating composition comprising a zirconium component composed of zirconium alloy deposited on the exterior surface of the base ceramic composite to form a coating thereon, which is in contact with the coolant, wherein the coating has a thickness from about 0.004 to about 0.006 inches.

2. The cladding of claim 1 , wherein the ceramic matrix is composed of material selected from the group consisting of silicon carbide and silicon carbide-containing material.

3. The cladding of claim 1 , wherein the plurality of ceramic fibers is composed of a material selected from the group consisting of silicon carbide and a silicon-carbide containing material.

4. The cladding of claim 1 , wherein the plurality of ceramic fibers is selected from the group consisting of individual fibers, woven fibers and braided fibers.

5. The cladding of claim 1 , wherein the ceramic composite is in the shape of a cylindrical tube.

6. A nuclear fuel rod cladding for a nuclear reactor, the nuclear fuel rod cladding comprising:
a ceramic composite tube comprising a silicon carbide matrix and a plurality of silicon carbide fibers; and
a coating deposited on an exterior surface of the ceramic composite tube, wherein the coating comprises zirconium alloy and a thickness in a range of about 0.004 to about 0.006 inches, wherein the coating is configured to contact a coolant in the nuclear reactor.

7. The nuclear fuel rod cladding of claim 6 , wherein the nuclear fuel rod cladding comprises a thickness in a range of 100 microns to 600 microns.

8. The nuclear fuel rod cladding of claim 6 , wherein the nuclear fuel rod cladding consists of the ceramic composite tube and the coating.

9. The nuclear fuel rod cladding of claim 6 , wherein the coating has been deposited by arc spray, liquid phase spray, plasma spray, cold spray, or laser deposition.

10. The nuclear fuel rod cladding of claim 6 , wherein the coating is configured to provide a hermetic seal on the exterior surface of the ceramic composite tube.

11. The nuclear fuel rod cladding of claim 6 , wherein the coating is configured to preclude coolant in the nuclear reactor from contacting the ceramic composite tube.

12. The cladding of claim 6 , wherein the cladding comprises a thickness from 100 microns to 600 microns.

Assignees

• Westinghouse Electric Co Llc

Inventors

• Aleshin Yuriy
• Choi Joonhyung

Classifications

• G21C21/02

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

• G21C3/07 Primary

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

• G21C9/001

  against explosions, e.g. blast shields · CPC title

• Y02E30/30

  Nuclear fission reactors · CPC title

• Y02E30/40

  Cross-Sectional Technologies · mapped topic