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U.S. Department of Energy
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Prediction of the lifetime of canisters for solidified radioactive wastes

Conference ·
OSTI ID:6766930
The lifetime of canisters for solidified high-level radioactive waste was predicted by extrapolating the thickness of reaction zones on both the inside and outside of candidate canister alloys when these alloys were in contact with typical waste and repository materials. Candidate canister alloys in close contact with both glass and concrete waste forms and with salt from a potential repository site were heated for 20,000 h at temperatures expected during geologic storage of the waste forms. Results showed that 3/8-in.-thick Type 304L stainless steel canisters of waste glass stored in air or in dry salt would not be penetrated by reaction with the contents of the canister and oxidation of the outside of the canister for more than 8000 y. A low-carbon steel canister of waste glass would not be breached in more than 2000 y in dry salt storage. Oxidation would penetrate a similar low-carbon steel canister of waste glass stored in air in about 200 y. Type 304L stainless steel or low-carbon steel canisters of waste concrete stored in air or in dry salt would also be penetrated in about 200 y.
Research Organization:
Du Pont de Nemours (E.I.) and Co., Aiken, SC (USA). Savannah River Lab.
DOE Contract Number:
AC09-76SR00001
OSTI ID:
6766930
Report Number(s):
DP-MS-80-47(Rev.); CONF-801088-T(Rev.)
Country of Publication:
United States
Language:
English