Wear resistant nuclear fuel assembly components
AssigneeSiemens Power Corporation
InventorRaymond A. Busch
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Abstract
Methods and apparatus for improving fretting resistance of zirconium alloy components formed into a shape for use in a nuclear reactor are disclosed in which at least a portion of the outer surface of a component is reacted with material selected from the group consisting of carbon, nitrogen, oxygen and combinations of the foregoing at a temperature below about 700.degree. C. to form a wear resistant layer on the surface of the component.
Claims23
A method for increasing fretting resistance of zirconium alloy components having processed metallugical characteristics for use in a nuclear reactor comprising:
- providing a zirconium alloy component;
- reacting at least a portion of an outer surface of said component at about atmospheric pressure with a material selected from the group consisting of carbon compounds suitable for forming a carbide, cyano or carbonate compounds suitable for forming an oxide, air or oxygen for forming an oxide and combinations of the forgoing, at a temperature below 500.degree. C. to avoid changes in the metallurgical characteristics of the zirconium alloy component, the reaction producing a black wear resistant layer on said surface.
A structural component for use in a fluid cooled nuclear reactor having increased fretting resistance, the component comprising a shaped article formed of a zirconium alloy and having processed metallurgical characteristics, a black wear resistant layer produced on at least a portion of a surface of said article which contacts cooling fluid in said reactor, said black wear resistant layer being produced in a reaction of the metals integral with said surface with a material selected from the group consisting of carbon compounds suitable for forming a carbide, cyano or carbonate compounds suitable for forming an oxide, air or oxygen and combinations of the forgoing at a temperature below 500.degree. C. to avoid changes in the metallurgical characteristics of the zirconium alloy, the article having maintained the metallurgical characteristics in the vicinity of said surface which existed prior to formation of said layer.
Dependencies are inferred from the claim text.