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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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Latest News
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.
Kazunari Katayama, Satoshi Fukada, Masabumi Nishikawa
Fusion Science and Technology | Volume 60 | Number 4 | November 2011 | Pages 1379-1382
Detritiation and Isotope Separation | Proceedings of the Ninth International Conference on Tritium Science and Technology (Part 2) | doi.org/10.13182/FST11-A12687
Articles are hosted by Taylor and Francis Online.
In the tritium recovery system of a fusion reactor, tritium extraction processing from tritiated hydrocarbon is needed. In the present study, a flow-type plasma reactor utilizing capacitively coupled plasma followed by the double tube permeator of Pd-Ag was developed and tritium extraction from tritiated methane in helium was demonstrated. When the helium gas containing tritiated methane was passed through plasma, it was observed that the concentration of tritiated methane decreased and the concentration of HT increased. However, the apparent decomposition rate of tritiated methane was considerably smaller than that of methane. Moreover, the amount of extracted tritium by Pd-Ag was smaller than expected.