Corrosion and wear resistant coating on zirconium alloy cladding

US9844923B2 · US · B2

Patent metadata
FieldValue
Publication numberUS-9844923-B2
Application numberUS-201514826524-A
CountryUS
Kind codeB2
Filing dateAug 14, 2015
Priority dateAug 14, 2015
Publication dateDec 19, 2017
Grant dateDec 19, 2017

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  1. Title

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  2. Abstract

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  3. Assignees and inventors

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  4. Key dates

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  5. First independent claim

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  6. CPC / IPC classifications

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Abstract

Official abstract text for this publication.

The invention relates to compositions and methods for coating a zirconium alloy cladding of a fuel element for a nuclear water reactor. The composition includes a master alloy including one or more alloying elements selected from chromium, silicon and aluminum, a chemical activator and an inert filler. The alloying element(s) is deposited or are co-deposited on the cladding using a pack cementation process. When the coated zirconium alloy cladding is exposed to and contacted with water in a nuclear reactor, a protective oxide layer can form on the coated surface of the cladding.

First claim

Opening claim text (preview).

What is claimed is: 1. A method of coating a zirconium alloy substrate for use in a nuclear water reactor, comprising: obtaining the zirconium alloy substrate having a surface; combining a master alloy comprising one or more elements selected from the group consisting of chromium, silicon and aluminum, a chemical activator and an inert filler powder to form a coating mixture; obtaining a chamber having a heating zone and an inert or reducing gas atmosphere; surrounding the zirconium alloy substrate with the coating mixture in the chamber; heating the chamber to an elevated temperature; reacting the master alloy with the chemical activator to form a gaseous compound; diffusing the gaseous compound to contact the surface of the zirconium alloy substrate; decomposing the gaseous compound; depositing the one or more elements of the master alloy on the surface of the zirconium alloy substrate; and forming a substantially uniform diffusion coating layer thereon comprising zirconium and the one or more elements of the master alloy. 2. The method of claim 1 , wherein the surrounding includes packing the zirconium alloy substrate in a bed of the coating mixture. 3. The method of claim 1 , wherein the diffusion coating layer is formed on one or both of an interior surface and an exterior surface of the zirconium alloy substrate. 4. The method of claim 1 , further comprising: positioning the zirconium alloy substrate with the substantially uniform diffusion coating layer thereon in a nuclear reactor; exposing and contacting with water the zirconium alloy substrate with the substantially uniform diffusion coating layer thereon; and forming a protective oxide layer on the substantially uniform diffusion coating layer, which comprises one or more of the following Cr 2 O 3 , SiO 2 , and Al 2 O 3 when the one or more elements of the master alloy is chromium, silicon and aluminum, respectively. 5. The method of claim 1 , wherein the diffusion coating layer comprises a Zr—Cr phase, a Zr—Si phase and a Zr—Al phase when the one or more elements of the master alloy is chromium, silicon and aluminum, respectively. 6. The method of claim 1 , wherein the heating is conducted at a temperature from 600° C. to 1100° C. 7. The method of claim 1 , wherein the substrate has a thickness from 1 micron to 200 microns. 8. The method of claim 7 , wherein the coated zirconium alloy substrate is subjected to one or more cold working steps to reduce the overall thickness and achieve a final dimension. 9. The method of claim 8 , wherein the cold working comprises pilgering. 10. The method of claim 8 , further comprising intermediate annealing of the coated zirconium alloy substrate to release residual stress in the coating and cladding.

Assignees

Inventors

Classifications

  • 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

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

  • B32B15/01Primary

    all layers being exclusively metallic {(making layered metal workpieces by pressure cladding B23K20/22; making coatings with a metallic material characterised by its composition C23C30/00)} · CPC title

  • Chemical surface treatment, e.g. corrosion (corrosion prevention in presence of water from scale removal or by modification of the properties of the liquid C02F5/00; inhibiting corrosion by adding corrosion inhibitors C23F11/00) · CPC title

  • G21C3/06Primary

    Casings; Jackets · CPC title

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What does patent US9844923B2 cover?
The invention relates to compositions and methods for coating a zirconium alloy cladding of a fuel element for a nuclear water reactor. The composition includes a master alloy including one or more alloying elements selected from chromium, silicon and aluminum, a chemical activator and an inert filler. The alloying element(s) is deposited or are co-deposited on the cladding using a pack cementa…
Who is the assignee on this patent?
Westinghouse Electric Co Llc
What technology area does this patent fall under?
Primary CPC classification B32B15/01. Mapped technology areas include Operations & Transport.
When was this patent published?
Publication date Tue Dec 19 2017 00:00:00 GMT+0000 (Coordinated Universal Time) (B2). Legal status and post-grant events are not shown on this page.
What related patents are in patentsdb?
We list 8 related publications on this page (citations in our corpus or others sharing the same primary CPC).