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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.
Junhua Luo, Rong Liu, Li Jiang
Nuclear Science and Engineering | Volume 172 | Number 1 | September 2012 | Pages 122-126
Technical Note | doi.org/10.13182/NSE11-109
Articles are hosted by Taylor and Francis Online.
In this study, activation cross sections were measured for the 71Ga(n,)72m+gGa reaction at three different neutron energies from 13.5 to 14.8 MeV. The fast neutrons were produced via the 3H(d,n)4He reaction on the Pd-300 Neutron Generator. Natural high-purity Ga2O3 powder was used as target material. Induced gamma activities were measured by a high-resolution gamma-ray spectrometer with a high-purity germanium detector. The data for the 71Ga(n,)72m+gGa reaction cross sections are reported to be 1.93 ± 0.12, 1.50 ± 0.09, and 0.91 ± 0.05 mb at 13.5 ± 0.2, 14.1 ± 0.2, and 14.8 ± 0.2 MeV incident neutron energies, respectively. Results are discussed and compared with some corresponding values found in the literature.