Deposition of integrated protective material into zirconium cladding for nuclear reactors by high-velocity thermal application

Patent metadata

Field	Value
Publication number	US-10984919-B2
Application number	US-201916264938-A
Country	US
Kind code	B2
Filing date	Feb 1, 2019
Priority date	Nov 7, 2012
Publication date	Apr 20, 2021
Grant date	Apr 20, 2021

Abstract

A zirconium alloy nuclear reactor cylindrical cladding has an inner Zr substrate surface, an outer volume of protective material, and an integrated middle volume of zirconium oxide, zirconium and protective material, where the protective material is applied by impaction at a velocity greater than 340 meters/second to provide the integrated middle volume resulting in structural integrity for the cladding.

First claim

What is claimed is:

1. A method of forming an integrated gradient network of protective particles into a ZrO 2 layer and a base Zr tube of a nuclear reactor cladding,
the integrated gradient network having
an inner surface and an inner volume of a layer of zirconium alloy,
an outer surface and an outer volume of a layer of a protective material and
an integrated middle volume of a layer of a combination of
zirconium oxide,
zirconium and
excess sound velocity-impacted protective material,

the method comprising the steps of:
a) providing a Zr alloy nuclear reactor cladding having a Zr base alloy layer and a ZrO 2 outer layer;
b) providing a protective material comprised of Zr—Al alloy particles;
c) loading the protective material into a hybrid thermal-kinetic spray deposition or cold spray apparatus; and
d) impacting the nuclear reactor cladding with the protective material
to impact at a velocity greater than sound and sufficient to penetrate through the ZrO 2 layer and into the Zr base alloy layer
to provide an integrated gradient network of
a layer of protective Zr—Al alloy particles,
the layer of the combination of protective particles, ZrO 2 and Zr, and
the Zr base alloy layer;

wherein the highest density of protective material is at the cladding outer surface to protect the cladding from the reactor environment and any further oxidation of the zirconium; and
wherein the integrated middle volume provides structural integrity for the cladding.

2. The method of claim 1 , wherein the impacting velocity is 3½ times greater than 340 m/s.

3. The method of claim 1 further comprising heating the nuclear reactor cladding prior to impacting the nuclear reactor cladding with the protective material.

4. The method of claim 3 wherein the heating step heats an outer surface of the nuclear reactor cladding between 200° C. to 400° C.

5. The method of claim 1 wherein the impacting step is carried out with a hybrid thermal-kinetic deposition process.

6. The method of claim 1 wherein the impacting step is carried out with a cold spray deposition process.

7. The method of claim 6 wherein the cold spray process is carried out at a temperature between 250° C. and 1200° C.

8. The method of claim 1 wherein the protective material has a particle size of approximately between 1 and 500 micrometers.

9. The method of claim 1 wherein the impacting step is performed in an inert environment.

Assignees

• Westinghouse Electric Co Llc

Inventors

• Mazzoccoli Jason P
• Lahoda Edward J
• Xu Peng

Classifications

• C23C4/02

  Pretreatment of the material to be coated, e.g. for coating on selected surface areas · CPC title

• Y02T50/60

  Efficient propulsion technologies, e.g. for aircraft · CPC title

• C23C4/06

  Metallic material · CPC title

• G21C3/07

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

• C23C28/324

  with at least one metal matrix material layer comprising a mixture of at least two metals or metal phases or a metal-matrix material with hard embedded particles, e.g. WC-Me · CPC title