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US09336909B2 Deposition of integrated protective material into zirconium cladding for nuclear reactors by high-velocity thermal application 有权
通过高速热应用将集成的保护材料沉积到核反应堆的锆包层中

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 (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.
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