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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.
M. T. Morgan, A. P. Malinauskas
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 457-464
Fission Product Release | Coated Particle Fuel / Fuel | doi.org/10.13182/NT77-A31905
Articles are hosted by Taylor and Francis Online.
Theoretical and experimental aspects of cesium release from Biso-coated high-temperature gas-cooled reactor fuel particles are reviewed. Three types of transport are considered: diffusion through the pyrolytic carbon (PyC) coatings under conditions of a constant source potential, transport due to a continuously depleting source, and diffusion from a depleting source following constant source potential transport. Analysis of all of the release data obtained in this laboratory yields the following relations for the diffusion coefficient DCs characteristic of cesium transport through PyC coatings:For coatings deposited from propylene or propane at ∼1250°C (1523 K):and far coatings deposited from methane at ∼2000°C (2273 K):where T is the absolute temperature.