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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. F. Myers, N. L. Baldwin, W. E. Bell
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 501-508
Fission Product Release | Coated Particle Fuel / Fuel | doi.org/10.13182/NT77-A31910
Articles are hosted by Taylor and Francis Online.
A review and analysis of available data on the release of fission gases from high-temperature gas-cooled reactor fuel particles indicates that the release of short-lived nuclides (half-life ≲5.3 days) occurs from the fissile material primarily by a mechanism involving recoil followed by gas-phase and bulk diffusion in the surrounding material at temperatures up to at least 1300°C (1573 K). The gas-phase contribution to the release of short-lived nuclides is dominant at temperatures below 600°C (873 K), and bulk diffusion is dominant at temperatures above 900°C (1173 K). Fission gas release to birth ratio (R/B) varies with half-life to a power of ∼0.2 at 300°C (573 K) and ∼0.5 at 1100°C (1373 K). For the short-lived isotopes, R/B is independent of burnup over the range from 0 to 63% FIMA in UC2 kernels; for dense ThO2 kernels, the data are insufficient to determine the burnup dependence. For the long-lived and stable isotopes, release from dense ThO2 kernels is strongly dependent on burnup. Iodine and tellurium isotopes may be treated as if they were xenon isotopes.