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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.
A. Jankowiak, F. Jorion, C. Maillard, L. Donnet
Nuclear Science and Engineering | Volume 160 | Number 3 | November 2008 | Pages 378-384
Technical Paper | doi.org/10.13182/NSE160-378
Articles are hosted by Taylor and Francis Online.
This study describes the preparation and characterization of Pu0.5Am0.5O2-x-MgO ceramic/ceramic (cercer) composites with 20 and 30 vol% of Pu0.5Am0.5O2-x. The sintered materials demonstrated very different reduction behavior when exposed to a reducing sintering cycle. The composites were studied by combined X-ray diffraction (XRD) and oxygen-to-metal ratio measurements and exhibited various amounts of body-centered-cubic (bcc) and face-centered-cubic (fcc) phases corresponding to different reduction states of the mixed actinide oxide. The fcc phases correspond to a near stoichiometry phase while the bcc phases are attributed to most reduced phases, which demonstrate a greater similarity with the Am2O3 bcc phase. The XRD results suggest a reduction of Am prior to Pu, which explains this greater similarity. In addition, the 30 vol% composite contains 65 wt% of the bcc phase while the 20 vol% composite exhibits only 29 wt%. This result can be explained by the percolation theory when applied to the oxygen diffusivity and indicates that a threshold value for Pu0.5Am0.5O2-x content in the cercer composite exists where the reduction of the mixed oxide significantly increases.