Durability of containers for storing solidified radioactive wastes. [Cor-Ten A] [electronic resource].
- Aiken, S.C : Savannah River Laboratory, 1976.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
- Physical Description:
- Pages: 30 : digital, PDF file
- Additional Creators:
- Savannah River Laboratory
United States. Department of Energy. Office of Scientific and Technical Information
- Most concepts for the disposal of highly radioactive waste involve converting the waste to a solid form like concrete or glass and storing this solid form in metal containers. Two major factors in the final selection of materials for these containers are the compatibility between waste form and container material and the durability of the material at temperatures and stresses expected during service and possible accidents. Currently, AISI 1020 carbon steel appears to be a better material than other alloys such as Cor-Ten A, Type 304L stainless steel, or Inconel 600 considered. This choice is based on the results of 10,000 hours of heating tests that showed container compatibility with both concrete and glass waste forms. The selection is also based on (1) analyses of the strengths and (2) oxidation resistances of the alloys under the conditions expected during 100 year storage in air and in various impact and thermal accidents. The thinner wall thickness required for satisfactory performance of the stronger, more-oxidation-resistant alloys is offset by their higher cost per pound. 7 figures, 4 tables, 28 references.
- Published through SciTech Connect.
Corrosion/77 NACE meeting, San Francisco, CA, USA, 14 Mar 1977.
Angerman, C.L.; Rankin, W.N.
- Funding Information:
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