Canister Compatibility with Carlsbad Salt
This paper describes the results of the examination of candidate canister alloy specimens heated with Carlsbad salt in sealed capsules for up to 5000 hours and in unsealed capsules for up to 10,000 hours. The compatibility of candidate alloys, for use in fabricating canisters for solidified radioactive waste, with salt from a potential final storage location for waste forms is being evaluated by long term heating tests (1). In these tests, canister alloys are being exposed to salt in a manner similar to that expected during final storage of canisters of solidified waste forms in a salt deposit. Test specimens are being heated at the temperature expected during waste form storage and at higher temperatures to accelerate any reactions that may occur. Reaction rates are determined by examining replicate specimens periodically removed from the test.
KeywordsWaste Form High Level Waste Significant Attack Final Storage Waste Isolation Pilot Plant
Unable to display preview. Download preview PDF.
- 1.W. N. Rankin, “Compatibility Testing of Vitrified Waste Forms,” Presented at Corrosion/78, Houston, TX, National Association of Corrosion Engineers, March 6–10 (1978).Google Scholar
- 2.M. H. Tennant, “Temperatures Generated by Underground Storage of Defense Waste Canisters,” to be presented at Corrosion/80, Houston, TX, National Association of Corrosion Engineers, March 6–10 (1980).Google Scholar
- 3.A. S. Jennings, “Plans for Solidification of Savannah River Plant High Level Wastes,” presented at the 70th Annual AIChE Meeting on Long-Term Management of Defense High Level Waste, American Institute of Chemical Engineers, New York, NY, Nov. 15 (1977).Google Scholar
- 4.L. B. Shappert, “Cask Designers Guide,” USERDA Report ORNL-NSIC68, Oak Ridge National Laboratory, Oak Ridge, TN (1970).Google Scholar
- 5.WIPP Conceprual Design Report, SAND 77–0274(Parts I and II ), Sandia Laboratories, Albuquerque, NM (1977).Google Scholar
- 6.J. W. Braithwaite and M. A. Molecke, “High Level Waste Canister Corrosion Studies Pertinent to Geological Isolation,” Proceedings of Conference on High Level Solid Radioactive Wastes, Denver, CO, NUREG CP-0005 (1979).Google Scholar
- 7.M. A. Molecke, Personal Communication, Sandia Laboratories, Albuquerque, NM, Oct. (1976).Google Scholar
- 8.R. L. Bradaham and W. C. McClain, Editors, Project Salt Vault: ADemonstration of the Disposal of High-Activity Solidified Wastes in Underground Salt Mines, ORNL-4555, UC-70, Waste Disposal and Processing, Oak Ridge National Laboratory, Oak Ridge, TN, April (1971).Google Scholar
- 9.Savannah River Laboratory Quarterly Report, Waste Management,DPST–77–125–2, April–June (1977).Google Scholar