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Spent fuel recycling and conditioning topic of U.S.-Japan meeting
Officials with the Department of Energy’s Office of Environmental Management discussed spent nuclear fuel recycling and conditioning with counterparts from Japan during the 13th U.S.-Japan Technical Meeting of the Civil Nuclear Energy Research and Development Working Group, held recently in Santa Fe, N.M.
W. F. Calaway
Nuclear Technology | Volume 39 | Number 1 | June 1978 | Pages 63-74
Nuclear Safety Analysis | Energy Modeling and Forecasting / Chemical Processing | doi.org/10.13182/NT78-A17008
Articles are hosted by Taylor and Francis Online.
The electrochemical evolution of hydrogen from a molten solution of LiF-LiCl-LiBr containing small quantities of LiH and saturated with metallic lithium has been demonstrated. The evolved hydrogen is recovered from the melt by sweeping the hydrogen electrode with a circulating stream of argon and subsequently trapping the hydrogen from the argon with a hot titanium getter bed. It is found that by continually gettering the argon, 100 ± 2% of the hydride present in the molten salt, at a concentration of 1 wppm, is recoverable. Results of metallographic examinations of stainless-steel components in contact with the salt solution during the experiments indicate some evidence of surface attack (10 to 15 µm) and intergranular penetration (30 to 50 µm), but extrapolated corrosion rates are generally small (∼0.2 mm/yr). These results incorporated into a reevaluation of the molten-salt extraction process, as it applied to tritium recovery from a liquid-lithium fusion reactor blanket, indicate a more favorable processing capability than was previously expected.