Evaluation of stainless steel zirconium alloys as high-level nuclear waste forms

摘要: Abstract Stainless steel–zirconium (SS–Zr) alloys have been developed for the consolidation and disposal of waste stainless steel, zirconium, noble metal fission products such as Nb, Mo, Tc, Ru, Pd, Ag recovered from spent nuclear fuel assemblies. These remnant metals are left behind following electrometallurgical treatment, a molten salt-based process being demonstrated by Argonne National Laboratory. Two SS–Zr compositions selected baseline form alloys: (a) steel–15 wt% zirconium (SS–15Zr) steel-clad fuels (b) zirconium–8 steel (Zr–8SS) Zircaloy-clad fuels. Simulated were prepared tested to characterize metallurgy SS–15Zr Zr–8SS evaluate their physical properties corrosion resistance. Both multi-phase microstructures, mechanically strong, thermophysical comparable other metals. They also exhibit high resistance in simulated groundwater determined immersion, electrochemical, vapor hydration tests. Taken together, microstructure, property, data indicate that viable materials high-level forms.