Abstract
AbstractThe Basalt Waste Isolation Project has performed initial characterization of the release behavior of radionuclides from ATM-101 spent fuel reacted under hydrothermal conditions. Results to date indicate that 1) 14C, 90Sr, 129I, and 137Cs exhibit preferential release to solution relative to the actinides, 2) 239+240Pu, 241Am, and 244Cm ratios in solution are consistent with stoichiometric dissolution of the spent fuel matrix, whereas uranium concentrations are higher than those predicted for stoichiometric dissolution, 3) 137Cs release varies as a function of the fluid to solid mass ratio, and 4) 14C, 129I, and 137Cs release is affected by fuel particle size and/or fuel washing.
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