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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. Strigl, E. Proksch
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 386-391
Performance and Performance Modeling | Coated Particle Fuel / Fuel | doi.org/10.13182/NT77-A31899
Articles are hosted by Taylor and Francis Online.
For the purpose of postirradiation measurement of the amount of CO formed during irradiation of oxide high-temperature reactor fuel particles, the equilibrium between CO and the various oxide phases inside the kernel has to be reestablished as closely as possible. To this end, the particles have to be heated to irradiation temperature for a certain time. Kinetic measurements have been performed on two types of porous pure UO2 kernels as well as on two types of porous carbon-diluted UO2 kernels. At 1200°C (1473 K), the CO equilibrium is reestablished after some hours in all kernel types. There seems to be no significant influence of any particle or irradiation parameter on that time.