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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.
K. Rehme
Nuclear Technology | Volume 33 | Number 3 | May 1977 | Pages 314-317
Technical Note | Fuel | doi.org/10.13182/NT77-A31793
Articles are hosted by Taylor and Francis Online.
Experiments have been performed on the pressure drop of a spacer grid in rod bundles of 12 rods. Both smooth and rough rod bundles were used in the experiments. The artificial roughness cut into the outer surface of the rods was chosen so as to meet the actual design of a gas-cooled fast breeder reactor. The results of this investigation for a Reynolds number range between Re = 4 × 103 and 7 × 104 indicate that the pressure drop at the spacer grids is higher in a roughened rod bundle than in a smooth rod bundle.