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U.S. Department of Energy
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Effect of HNO sub 3 -cerium(IV) decontamination on stainless steel waste canisters

Conference ·
OSTI ID:5739610
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 HNO{sub 3}-Ce(IV) solution, which will remove the oxide film and a small amount of metal from the surface of the canisters. Studies were undertaken 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 proposed decontamination treatment. 2 refs., 5 figs.
Research Organization:
Pacific Northwest Lab., Richland, WA (USA)
Sponsoring Organization:
DOE; USDOE, Washington, DC (USA)
DOE Contract Number:
AC06-76RL01830
OSTI ID:
5739610
Report Number(s):
PNL-SA-18551; CONF-910435--68; ON: DE91011243
Country of Publication:
United States
Language:
English