Deposition of integrated protective material into zirconium cladding for nuclear reactors by high-velocity thermal application

摘要

A zirconium alloy nuclear reactor cylindrical cladding has an inner Zr substrate surface (10), an outer volume of protective material (22) consisting of Zr—Al, and an integrated middle volume (20) 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 (20) resulting in structural integrity for the cladding.

主权项

1. A zirconium alloy nuclear reactor cylindrical cladding, subject to a nuclear reactor environment, the cladding having an inner surface and inner volume of zirconium alloy, an outer surface and outer volume of a protective material consisting of Zr—Al, and an integrated middle volume of zirconium oxide, zirconium, and excess sound velocity-impacted protective material, where the highest density of protective material is at the cladding outer surface to protect the cladding from reactor environment and any further oxidation of the zirconium, where the integrated middle volume provides structural integrity for the cladding.