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2026 Nuclear Energy Conference & Expo (NECX)
August 24–27, 2026
Dallas, TX|Hilton Anatole
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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.
T. Cisneros, M. Wargon, B. Harper, K. Hanselman, T. Kawano, S. A. Kuvin, H. Y. Lee
Nuclear Science and Engineering | Volume 200 | Number 1 | March 2026 | Pages S131-S141
Research Article | doi.org/10.1080/00295639.2024.2413787
Articles are hosted by Taylor and Francis Online.
The Molten Chloride Reactor Experiment (MCRE) will be built and operated as part of an Advanced Reactor Demonstration Project Risk Reduction Award. This fast spectrum, chloride salt–fueled molten salt reactor is sensitive to chlorine nuclear data. Recent experimental measurements of the 35Cl (n,p) cross section disagree with 35Cl nuclear data evaluations outside the bounds of the nuclear data uncertainty covariance matrices. To address this challenge, Los Alamos National Laboratory has been charged with measuring the 35Cl (n,p) cross section at the Los Alamos Neutron Science Center and generating an updated 35Cl nuclear data evaluation integrating recent cross-section measurements. This paper evaluates the reactivity impact of using the updated 35Cl evaluation on the MCRE application compared to publicly available evaluations (ENDF/B up to VIII.0 and JENDL-5).