Cold Spray Technology for Oxidation-Resistant Nuclear Fuel Cladding

Tuesday, May 25, 2021: 8:30 AM
Mr. Tyler Dabney , University of Wisconsin-Madison, Madison, WI
Dr. Hwasung Yeom , University of Wisconsin-Madison, Madison, WI
Mr. Kyle Quillin , University of Wisconsin-Madison, Madison, WI
Mr. Nicholas Pocquette , University of Wisconsin-Madison, Madison, WI
Dr. Kumar Sridharan , University of Wisconsin-Madison, Madison, WI
Light water reactors (LWR) use zirconium-alloy fuel claddings, the tubes that hold the uranium-dioxide fuel pellets. Zr-alloys have very good neutron transparency, but during a loss of coolant accident or beyond design based accident (BDBA) Zr-alloys can undergo excessive oxidation in reaction with the surrounding steam environment. Relatively thin oxidation-resistant coatings on Zr-alloy cladding tubes can potentially buy coping time in these off-normal scenarios. In this study, cold spray, a solid-state powder-based materials deposition technology has been developed for deposition of oxidation resistant Cr coatings on Zr-alloy cladding tubes, and the ensuing microstructure and properties of the coatings have been investigated. The coatings when deposited under optimum conditions have very good hydrothermal corrosion resistance as well as oxidation resistance in air and steam environments at temperatures in excess of 1100 °C, while maintaining excellent adhesion to the substrate. These and other results of this study, including mechanical property evaluations, will be presented.