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Title: Ceramic reinforced zirconium alloy nuclear fuel cladding with intermediate oxidation resistant layer

Abstract

The invention relates to compositions and methods for coating a zirconium alloy (e.g., ceramic-containing) cladding tube for use with fuel rods in a nuclear water reactor. The coating includes an intermediate oxidation resistant layer and a SiC containing layer at least partially deposited on the intermediate oxidation resistant layer. The SiC containing layer can include a plurality of fibers. The SiC containing layer may also be on the outer surface of end plugs. The invention provides improved capability for the zirconium alloy cladding to withstand normal and accident conditions in the nuclear water reactor.

Inventors:
Issue Date:
Research Org.:
Westinghouse Electric Co. LLC, Cranberry Township, PA (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1637841
Patent Number(s):
10593434
Application Number:
14/205,967
Assignee:
Westinghouse Electric Company (Cranberry Township, PA)
Patent Classifications (CPCs):
G - PHYSICS G21 - NUCLEAR PHYSICS G21C - NUCLEAR REACTORS
Y - NEW / CROSS SECTIONAL TECHNOLOGIES Y02 - TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE Y02E - REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
DOE Contract Number:  
NE0000566
Resource Type:
Patent
Resource Relation:
Patent File Date: 03/12/2014
Country of Publication:
United States
Language:
English

Citation Formats

Lahoda, Edward J. Ceramic reinforced zirconium alloy nuclear fuel cladding with intermediate oxidation resistant layer. United States: N. p., 2020. Web.
Lahoda, Edward J. Ceramic reinforced zirconium alloy nuclear fuel cladding with intermediate oxidation resistant layer. United States.
Lahoda, Edward J. Tue . "Ceramic reinforced zirconium alloy nuclear fuel cladding with intermediate oxidation resistant layer". United States. https://www.osti.gov/servlets/purl/1637841.
@article{osti_1637841,
title = {Ceramic reinforced zirconium alloy nuclear fuel cladding with intermediate oxidation resistant layer},
author = {Lahoda, Edward J.},
abstractNote = {The invention relates to compositions and methods for coating a zirconium alloy (e.g., ceramic-containing) cladding tube for use with fuel rods in a nuclear water reactor. The coating includes an intermediate oxidation resistant layer and a SiC containing layer at least partially deposited on the intermediate oxidation resistant layer. The SiC containing layer can include a plurality of fibers. The SiC containing layer may also be on the outer surface of end plugs. The invention provides improved capability for the zirconium alloy cladding to withstand normal and accident conditions in the nuclear water reactor.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2020},
month = {3}
}

Patent:

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