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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.
B. A. Pint, J. Jun, E. Cakmak, D. J. Sprouster, N. Olynik, L. L. Snead
Fusion Science and Technology | Volume 77 | Number 7 | October-November 2021 | Pages 761-765
Technical Paper | doi.org/10.1080/15361055.2021.1898305
Articles are hosted by Taylor and Francis Online.
A series of monometallic thermal convection loops (TCLs) has been conducted to determine the maximum temperature where FeCrAl alloys have compatibility with eutectic lead lithium (Pb-Li) for a dual-coolant fusion blanket. Pre-oxidizing commercial alloy APMT (Fe-21Cr-5Al-3Mo) for 2 h at 1000°C to form a surface α-Al2O3 layer was very effective in reducing the mass loss of specimens in the hot and cold legs of the most recent TCL that was operated for 1000 h with a peak temperature of 700°C. However, unlike previous experiments, the postexposure room temperature ductility of many of the APMT specimens was degraded to <10% total elongation, and many of the specimens at the highest temperature (>680°C) were severely damaged or were not recovered. Wide-angle X-ray scattering found that the pre-formed α-Al2O3 scale transformed to a mixture of trigonal and tetragonal LiAlO2. The overall results suggest that the maximum temperature for FeCrAl is limited to <700°C.