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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.
R. M. Alire
Nuclear Technology | Volume 35 | Number 3 | October 1977 | Pages 651-655
Technical Paper | Material | doi.org/10.13182/NT77-A31873
Articles are hosted by Taylor and Francis Online.
The diffusion coefficients of D2 in Nb—1 wt% Zr were determined in the range from 923 to 1148 K. A hollow-cylinder model, used as the frame of reference, adequately described the transport of D2 through the alloy containing oxygen impurities. The diffusion coefficient is temperature dependent and is best described byD (m2/s) =8.5 ± 7 × 10−8 exp (−48.2 ± 6.7 × 103/RT) .