Deposition of integrated protective material into zirconium cladding for nuclear reactors by high-velocity thermal application
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.
- Inventors:
- Issue Date:
- Research Org.:
- Westinghouse Electric Co., Cranberry Township, PA (United States)
- Sponsoring Org.:
- USDOE
- OSTI Identifier:
- 1823881
- Patent Number(s):
- 10984919
- Application Number:
- 16/264,938
- Assignee:
- Westinghouse Electric Company LLC (Cranberry Township, PA)
- Patent Classifications (CPCs):
-
C - CHEMISTRY C23 - COATING METALLIC MATERIAL C23C - COATING METALLIC MATERIAL
G - PHYSICS G21 - NUCLEAR PHYSICS G21C - NUCLEAR REACTORS
- DOE Contract Number:
- NE0000566
- Resource Type:
- Patent
- Resource Relation:
- Patent File Date: 02/01/2019
- Country of Publication:
- United States
- Language:
- English
Citation Formats
Mazzoccoli, Jason P., Lahoda, Edward J., and Xu, Peng. Deposition of integrated protective material into zirconium cladding for nuclear reactors by high-velocity thermal application. United States: N. p., 2021.
Web.
Mazzoccoli, Jason P., Lahoda, Edward J., & Xu, Peng. Deposition of integrated protective material into zirconium cladding for nuclear reactors by high-velocity thermal application. United States.
Mazzoccoli, Jason P., Lahoda, Edward J., and Xu, Peng. Tue .
"Deposition of integrated protective material into zirconium cladding for nuclear reactors by high-velocity thermal application". United States. https://www.osti.gov/servlets/purl/1823881.
@article{osti_1823881,
title = {Deposition of integrated protective material into zirconium cladding for nuclear reactors by high-velocity thermal application},
author = {Mazzoccoli, Jason P. and Lahoda, Edward J. and Xu, Peng},
abstractNote = {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.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2021},
month = {4}
}
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