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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.
V. Tiwari, T. F. Abbink, J. A. Ocádiz Flores, J. L. Flèche, C. Gueneau, S. Chatain, A. L. Smith, J. Martinet, C. Venard
Nuclear Science and Engineering | Volume 197 | Number 12 | December 2023 | Pages 3035-3057
YMSR Paper | doi.org/10.1080/00295639.2023.2223745
Articles are hosted by Taylor and Francis Online.
A thorough understanding of the corrosion chemistry between molten salt fuel and structural materials (e.g., steel) is key for the advancement of Molten Salt Reactor technology. In this work, we consider more specifically the case of a chloride fuel salt mixture and the thermochemistry of a salt mixture such as (NaCl-MgCl2-PuCl3) in interaction with (Fe, Cr, Ni). The present work aims at the development of a thermodynamic model of the key subsystems NaCl-CrCl2, NaCl-CrCl3, and FeCl2-CrCl2 to predict corrosion products that may form between molten salt and structural materials. The Modified Quasichemical Model in the quadruplet approximation is used to describe the Gibbs energy of the liquid phase. A critical review of the existing phase diagram and thermodynamic data on theses systems is first presented. To alleviate the lack of data, ab initio calculations coupled with a quasi-harmonic approach are performed to estimate the thermodynamic properties for the intermediate solid compounds Na2CrCl4 and Na3CrCl6, which exist in the NaCl-CrCl2 and NaCl-CrCl3 systems, respectively. These atomistic simulation data together with selected experimental data are then used as input for the thermodynamic assessment of the three subsystems.