Effect of HNO3-Cerium(IV) Decontamination on Stainless Steel Canister Materials

by R. E. Westerman, Battelle Pacific Northwest Lab, Richland, United States,
D. B. Mackey, Battelle Pacific Northwest Lab, Richland, United States,



Document Type: Proceeding Paper

Part of: High Level Radioactive Waste Management 1991

Abstract: Stainless steel canisters will be filled with vitrified radioactive waste at the West Valley Demonstration Project (WVDP), West Valley, NY. After they are filled, the sealed canisters will be decontaminated by immersion in a HNO3-Ce(IV) solution, which will remove the oxide film and a small amount of metal from the surface of the canisters. Studies were undertaken in support of waste form qualification activities to determine the effect of this decontamination treatment on the legibility of the weld-bead canister identification label, and to determine whether this decontamination treatment could induce stress-corrosion cracking (SCC) in the AISI 304L stainless steel (SS) canister material. Neither the label legibility nor the canister integrity with regard to SCC were found to be prejudiced by the simulated decontamination treatment.

Subject Headings: Stainless steel | Waste treatment | Radioactive wastes | Concrete | Welding | Cracking | Stress analysis | North America | United States | New York

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