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- W64743102 abstract "The US plans to safely dispose of nuclear waste in deep, stable geologic formations. As part of these plans, the US Department of Energy (DOE) is sponsoring research on the designing and testing of waste packages and waste package materials. This report summarizes recent results of waste package materials testing in a salt environment. The results from these tests will be used by waste package designers and performance assessment experts. Release characteristic data are available on two waste forms (spent fuel and waste embedded in glass) which were exposed to leaching tests at various radiation levels, temperatures, pH, volumes, and brine solution and oxygen concentrations simulating expected salt repository conditions. Candidate materials tested or soon to be tested for corrosion resistance and other properties include iron alloys; TiCode-12, the most promising titanium alloy for containment; nickel alloys; and stainless steel. Testing of fluid movement and thermal conductivity through various backfill mixtures shows that these materials can perform satisfactorily. In component interaction testing, no synergistic effects have ruled out any candidate material. 77 references, 37 figures, 30 tables." @default.
- W64743102 created "2016-06-24" @default.
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- W64743102 date "1983-08-01" @default.
- W64743102 modified "2023-09-23" @default.
- W64743102 title "Waste package materials testing for a salt repository: 1982 status report" @default.
- W64743102 hasPublicationYear "1983" @default.
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