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U.S. Department of Energy
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Waste package materials testing for a salt repository: 1983 status summary report

Technical Report ·
OSTI ID:6825260
The United States plans to safely dispose of nuclear waste in deep, stable geologic formations. As part of these plans, the US Department of Energy is sponsoring research on the designing and testing of waste packages and waste package materials. This fiscal year 1983 status 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 characteristics data are available on two waste forms (spent fuel and waste-containing glass) that were exposed to leaching tests at various radiation levels, temperatures, pH, glass surface area to solution volume ratios, and brine solutions simulating expected salt repository conditions. Candidate materials tested for corrosion resistance and other properties include iron alloys; TI-CODE 12, the most promising titanium alloy for containment; and nickel alloys. In component interaction testing, synergistic effects have not ruled out any candidate material. 21 refs., 37 figs., 15 tabs.
Research Organization:
Battelle Memorial Inst., Columbus, OH (USA). Office of Nuclear Waste Isolation
DOE Contract Number:
AC02-83CH10140
OSTI ID:
6825260
Report Number(s):
BMI/ONWI-583; ON: DE87005939
Country of Publication:
United States
Language:
English

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