Development of Self-Healing Zirconium Silicide Coatings for Improved Performance of Zirconium- Alloy Fuel Cladding – University of Wisconsin CX(s) Applied: B3.6Date: 41877 Location(s): WisconsinOffices(s): Nuclear Energy
Office of NEPA Policy and Compliance
August 26, 2014
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Development of Self-Healing Zirconium Silicide Coatings for Improved Performance of Zirconium- Alloy Fuel Cladding – University of Wisconsin
CX(s) Applied: B3.6
Date: 41877
Location(s): Wisconsin
Offices(s): Nuclear Energy
The objectives of the proposed research by the University of Wisconsin will be: (1) development of Zr-silicide coatings on Zralloy substrates, (2) corrosion studies of Zr-silicide coatings in normal reactor environment and LOCA conditions, including a fundamental understanding of thermodynamic and kinetic pathways for evolution of self-healing multilayers, (3) radiation testing/studies of Zr-silicide coatings before and after corrosion test, and (4) modeling of corrosion of Zr-silicide coatings in reactor environments. The university will use existing facilities located at the university to test and characterize the coatings and perform ion irradiations of the coatings.
CX(s) Applied: B3.6
Date: 41877
Location(s): Wisconsin
Offices(s): Nuclear Energy
The objectives of the proposed research by the University of Wisconsin will be: (1) development of Zr-silicide coatings on Zralloy substrates, (2) corrosion studies of Zr-silicide coatings in normal reactor environment and LOCA conditions, including a fundamental understanding of thermodynamic and kinetic pathways for evolution of self-healing multilayers, (3) radiation testing/studies of Zr-silicide coatings before and after corrosion test, and (4) modeling of corrosion of Zr-silicide coatings in reactor environments. The university will use existing facilities located at the university to test and characterize the coatings and perform ion irradiations of the coatings.