Patent Number: 052672891
Section: claims

1. A method for enhancing the wear resistance of a tubular component of a nuclear fuel assembly, comprising: supporting the component in an implantation chamber;  removing ambient air from the chamber;  generating a plasma plume of positively charged metal source material by establishing an electrical discharge arc which travels from a cathode of said source material to an anode of a different material;  passing at least a portion of the plasma plume through an electromagnetic duct which filters constituents other than free, high energy source material ions out of the plume; and  directing the high energy source material positive ions through the chamber onto the negatively charged component.  the ionic compound implants in the component.  generating a cathodic arc plasma of the source material;  filtering the plasma to remove neutral atoms and macroparticles; and  directing the ions of the filtered plasma onto the component.  the component is surrounded by a reactive gas; and  the filtered plasma passes through the reactive gas to produce metal compound ions that implant in the component. 2. The method of claim 1, wherein the chamber is backfilled with a reactive gas which forms an ionic compound with the source material ions, and 3. The method of claim 2, wherein the reactive gas is nitrogen. 4. The method of claim 3, wherein the source material is one of Zr, Ti, Ta, Hf. 5. The method of claim 4, wherein the source material is one of Zr or Ti. 6. The method of claim 1, wherein the component is a zirconium alloy cladding tube for a nuclear fuel rod. 7. The method of claim 1, wherein the component is a zirconium alloy control rod guide tube. 8. A method for treating nuclear fuel assembly components by ion implantation of a metal source material to enhance wear resistance, wherein the improvement comprises; 9. The method of claim 8, wherein 10. The method of claim 9, wherein the reactive gas is nitrogen. 11. The method of claim 8, wherein the component is a zircaloy alloy and the source material is one of Zr or Ti. 12. A zircaloy alloy nuclear fuel assembly component having wear enhancing material implanted from a cathodic arc of filtered plasma to a depth of approximately 2.0 .mu.m in the component. 13. The component of claim 12, wherein the enhancing material is a nitride.