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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.
W. Delle, K. Koizlik, M. S. T. Price U.K., E. Wallura
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 284-292
Pyrocarbon | Coated Particle Fuel / Fuel | doi.org/10.13182/NT77-A31888
Articles are hosted by Taylor and Francis Online.
Today, pyrocarbon (PyC) is the most common material used for the coating of nuclear fuel particles for the fuel elements of the high-temperature gas-cooled reactor. During recent years, many procedures have been developed for this material that have yielded a broad spectrum of information and have thereby improved knowledge of PyC. The characterization methods that are suitable for out-line quality control include coating layer density determination by sink float techniques, coating layer thickness by x-ray projection or by contact microscopy, and orientation anisotropy. Many other techniques are available for laboratory use.