Deposition of a protective coating including metal-containing and chromium-containing layers on zirconium alloy for nuclear power applications
View Patent ↗The invention relates to compositions and methods for coating a zirconium alloy cladding of a fuel element for a nuclear water reactor. The coating includes a first tier or layer and a second tier or layer. The first layer includes an elemental metal and the second layer is an oxidation-resistant layer that includes elemental chromium. The first layer serves as an intermediate layer between the zirconium alloy substrate and the second layer. This intermediate layer can be effective to improve adhesion of the second layer to the zirconium alloy substrate. The multilayer coating forms a protective layer which provides improved capability for the zirconium alloy cladding to withstand normal and accident conditions to which it is exposed in the nuclear reactor.
1. A coated composite cladding for a fuel rod in a nuclear water reactor, comprising:
a zirconium alloy elongated tube having a cavity formed therein, an interior surface and an exterior surface, structured to hold nuclear fuel in the cavity;
a first coating composition deposited on the exterior surface of the elongated tube to form a first coating layer, the first coating composition comprising an elemental metal; and
a second coating composition deposited on the first coating layer to form a second coating layer, the second coating composition comprising elemental chromium.
2. The coated composite of claim 1 , wherein the elemental metal is a noble metal.
3. The coated composite of claim 1 , wherein the elemental metal is selected from the group consisting of palladium, nickel, copper and combinations thereof.
4. The coated composite of claim 1 , wherein the elemental metal has a melting point greater than coolant temperature during a nuclear reactor accident.
5. The coated composite of claim 4 , wherein the melting point is greater than 1200° C.
6. The coated composite of claim 1 , wherein the elemental metal has a low neutron absorption cross-section in a range of about 0.1 barn to about 7.0 barns.