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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.
Cheol Ho Pyeon, Masao Yamanaka, Masahiro Fukushima
Nuclear Science and Engineering | Volume 195 | Number 8 | August 2021 | Pages 877-889
Technical Paper | doi.org/10.1080/00295639.2020.1870861
Articles are hosted by Taylor and Francis Online.
Uncertainty quantification of lead (Pb) and bismuth (Bi) sample reactivity worth is numerically determined using the SCALE6.2 code system and experimental results obtained from the solid-moderated and solid-reflected core at the Kyoto University Critical Assembly (KUCA) to demonstrate the sensitivity coefficients of aluminum (Al) and Bi scattering reactions. From the results of the numerical analyses, the impact of 27Al and 209Bi scattering cross sections obtained using SCALE6.2/TSAR is disclosed on the Bi sample reactivity worth using Al reference and Bi test samples, although the uncertainty itself is small in the Bi sample reactivity worth. In future studies, the actual impact of 209Bi inelastic scattering reactions in liquid Pb-Bi eutectic needs to be considered under numerical simulations of the void reactivity in the accelerator-driven system. Also, in the KUCA experiments, conventional modeling of void evolution by the Al reference sample is expected to be altered by a void (air) in terms of the 27Al elastic and inelastic scattering reactions of the Al reference sample.