Abstract: In general, the present invention is directed to novel nuclear fuel rod claddings that have better performance characteristics compared to current claddings, particularly during a severe accident, such as a loss of coolant accident. The present invention provides a duplex cladding having two layers, an inner Mo or Mo-alloy layer and a protective layer disposed on the outside of the Mo or Mo-alloy layer. Optionally, the Mo or Mo-alloy layer may have a coating disposed on its inner surface to provide additional capability with the fuel pellets, thereby creating a triplex cladding.

Abstract: In general, the present invention is directed to novel nuclear fuel rod claddings that have better performance characteristics compared to current claddings, particularly during a severe accident, such as a loss of coolant accident. The present invention provides a duplex cladding having two layers, an inner Mo or Mo-alloy layer and a protective layer disposed on the outside of the Mo or Mo-alloy layer. Optionally, the Mo or Mo-alloy layer may have a coating disposed on its inner surface to provide additional capability with the fuel pellets, thereby creating a triplex cladding.

Abstract: An alloy having improved resistance to hydriding as well as good corrosion resistance, adequate strength, fabricability and irradiation growth. These properties make the new alloy exceptionally suited for use in boiling water reactor components such as fuel channels, fuel cladding and fuel rod spacers. The class of alloys includes zirconium-based alloys having about 0.3-1.2% tin, about 0.8-1.4% chromium, about 0.05-0.7% iron, and the remainder substantially zirconium.

Abstract: An improved method for producing nuclear fuel containers of a composite construction having components providing therein a barrier system for resisting destructive action by volatile fission products or impurities and also interdiffusion of metal constituents, and the product thereof. The composite nuclear fuel containers of the method comprise a casing of zirconium or alloy thereof with a layer of copper overlying an oxidized surface portion of the zirconium or alloy thereof.

Abstract: A method for controlling hydrogen charging of hydride forming metals through a window of a superimposed layer of a non-hydriding metal overlying the portion of the hydride forming metals to be charged.

Abstract: An improved method for producing nuclear fuel containers of a composite construction having components providing therein a barrier system for resisting destructive action by volatile fission products or impurities and also interdiffusion of metal constituents, and the product thereof. The composite nuclear fuel containers of the method comprise a casing of zirconium or alloy thereof with a layer of copper overlying an oxidized surface portion of the zirconium or alloy thereof.

Abstract: Means for discriminating the corrosion susceptibility of alloys of zirconium in an environment of a water cooled, nuclear fission reactor.