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.

Abstract: A cladding tube for nuclear fuel having an outer elongated cladding tube and a zirconium liner which lines the outer cladding tube, the inner wall of the liner having an inner diffusion portion of a zirconium based alloy of tin and/or vanadium.

Abstract: A spring member is formed of at least two layers metallurgically bonded together uniformly and having significantly different rates of irradiation growth, so that the differential growth of the layers results in increased stress in a predetermined direction. The layers may be of different metals or of similar metals which have been treated to give them different growth rates, such as zircaloy with different tin and oxygen content. Examples of other properties which may be used to obtain differential growth rates for the two layers when they are of material with substantially the same constituents are alpha-beta phase transformation temperature, the annealing temperature, the work history, partial recrystallization, and precipitation hardening.