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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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Spent fuel transfer project completed at INL
Work crews at Idaho National Laboratory have transferred 40 spent nuclear fuel canisters into long-term storage vaults, the Department of Energy’s Office of Environmental Management has reported.
P. E. Gethard, L. R. Zumwalt
Nuclear Technology | Volume 3 | Number 11 | November 1967 | Pages 679-685
Technical Paper and Note | doi.org/10.13182/NT67-A27903
Articles are hosted by Taylor and Francis Online.
The diffusion of strontium and cesium through thin layers (100 μm) of isotropic pyrolytic carbon has been measured over the temperature range 1000 to 1700°C. Diffusion coefficients observed for cesium are orders of magnitude lower than those for strontium. The diffusion rates for both series are much lower than those observed in porous poly crystalline graphite, where little difference is seen between cesium and strontium. When constant chemical potential sources are used, chemical- and self-diffusion measurements for strontium give identical results in the Sr concentration range 0.01 to 0.2 wt%. There is apparently no concentration effect for cesium over the range 1.0 × 10−5 to 0.15 wt%. The difference between strontium and cesium diffusion in pyrolytic carbon is attributed to the greater steric effect of the pyrolytic-carbon defect structure relative to cesium.