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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.
Masaru Nagura, Akihiro Suzuki, Takeo Muroga, Takayuki Terai
Fusion Science and Technology | Volume 56 | Number 2 | August 2009 | Pages 841-845
Tritium Breeding | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 2) | doi.org/10.13182/FST09-A9015
Articles are hosted by Taylor and Francis Online.
Er2O3 is one promising material for use as an insulating coating in a liquid lithium blanket system. In this study, corrosion of bulk Er2O3 in Li with high or low O concentrations was investigated at 600°C. The tests revealed that the corrosion reaction is accelerated under high O condition and suppressed in low O concentration. From these results we assumed the corrosion reaction and tested with more precise condition. The Er2O3 bulk specimen corroded significantly in Li with more than 300 ppm O. Control of O concentration is essential for a Li blanket system with an Er2O3 coating.
