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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. H. Guber, R. R. Spencer, L. C. Leal, J. A. Harvey, N. W. Hill, G. Dos Santos, R. O. Sayer, D. C. Larson
Nuclear Science and Engineering | Volume 135 | Number 2 | June 2000 | Pages 141-149
Technical Paper | doi.org/10.13182/NSE00-A2130
Articles are hosted by Taylor and Francis Online.
In support of the U.S. Department of Energy need for new data for criticality safety applications, new high-resolution fission cross-section measurements of 233U have been made at the Oak Ridge Electron Linear Accelerator. The measurements were carried out over a 0.4-eV to 700-keV energy range at the 80-m flight station using a fission chamber. Corrections were made for experimental effects to obtain the average fission cross section in this energy range. Results are compared to previous measurements.