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Title: Alloy waste forms for metal fission products and actinides isolated by spent nuclear fuel treatment

Conference ·
DOI:https://doi.org/10.2172/270551· OSTI ID:379093

Waste form alloys are being developed at Argonne National Laboratory for the disposal of remnant metallic wastes from an electrometallurgical process developed to treat spent nuclear fuel. This metal waste form consists of the fuel cladding (stainless steel or Zircaloy), noble metal fission products (e.g., Ru, Pd, Mo and Tc), and other metallic wastes. The main constituents of the metal waste stream are the cladding hulls (85 to 90 wt%); using the hulls as the dominant alloying component minimizes the overall waste volume as compared to vitrification or metal encapsulation. Two nominal compositions for the waste form are being developed: (1) stainless steel-15 wt% zirconium for stainless steel-clad fuels and (2) zirconium-8 wt% stainless steel for Zircaloy-clad fuels. The noble metal fission products are the primary source of radiation in the metal waste form. However, inclusion of actinides in the metal waste form is being investigated as an option for interim or ultimate storage. Simulated waste form alloys were prepared and analyzed to determine the baseline alloy microstructures and the microstructural distribution of noble metals and actinides. Corrosion tests of the metal waste form alloys indicate that they are highly resistant to corrosion.

Research Organization:
Argonne National Lab. (ANL), Argonne, IL (United States)
Sponsoring Organization:
USDOE, Washington, DC (United States)
DOE Contract Number:
W-31109-ENG-38
OSTI ID:
379093
Report Number(s):
ANL/CMT/CP-87845; CONF-961018-2; ON: DE96014380; TRN: 96:025656
Resource Relation:
Conference: Minerals, Metals and Materials Society (TMS) fall extraction and process metallurgy meeting, Scottsdale, AZ (United States), 27-30 Oct 1996; Other Information: PBD: 1996
Country of Publication:
United States
Language:
English