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CORROSION AND WEAR RESISTANT COATING ON ZIRCONIUM ALLOY CLADDING
CORROSION AND WEAR RESISTANT COATING ON ZIRCONIUM ALLOY CLADDING
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机译:锆合金熔覆层的耐蚀耐磨涂层
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摘要
The invention relates to compositions and methods for coating a zirconium alloy cladding of a fuel element for a nuclear water reactor. The composition includes a master alloy including one or more alloying elements selected from chromium, silicon and aluminum, a chemical activator and an inert filler. The alloying element(s) is deposited or are co-deposited on the cladding using a pack cementation process. When the coated zirconium alloy cladding is exposed to and contacted with water in a nuclear reactor, a protective oxide layer can form on the coated surface of the cladding.
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