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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, Akito Oizumi, Masahiro Fukushima
Nuclear Science and Engineering | Volume 195 | Number 11 | November 2021 | Pages 1144-1153
Technical Paper | doi.org/10.1080/00295639.2021.1932220
Articles are hosted by Taylor and Francis Online.
Measurements of 243Am and 235U fission reaction rates are conducted with the use of two single fission chambers in the solid-moderated and solid-reflected core at the Kyoto University Critical Assembly (KUCA). Critical irradiation experiments of 243Am and 235U foils are carried out, and the measured result of 243Am/235U is 0.0424 ± 0.0019; also, calculation/experiment values between calculated (MCNP6.1 with JENDL-4.0, ENDF/B-VIII.0, and JEFF-3.3) and measured results of 243Am/235U range among 0.93 ± 0.04, 0.94 ± 0.04, and 0.93 ± 0.04, respectively. Through a comparison between the measured and calculated results, the 243Am fission cross-section data of the three major nuclear data libraries are successfully validated, demonstrating the same accuracy as that of previous minor actinide irradiation experiments at KUCA. Importantly, the comparison also provides the complemental data of integral experiments of 243Am fission reaction rates that confirm the accuracy of the 243Am fission cross-section data.