Assessing the effect of radioactive waste glass dissolution on early-stage radionuclide migration using simplified geological repository Monte Carlo transport models

Abstract The vitrification of radioactive waste within glass and subsequent disposal a geological facility (GDF) requires comprehensive understanding the effect dissolution on GDF performance. This paper aims to analyse both high-level intermediate-level (HLW ILW) source terms radionuclide release into geosphere just above vault (the ‘crown’). Radionuclide migration was simulated in GoldSim for HLW either granite or clay host rocks with bentonite buffer using carbon steel copper canisters, whereas ILW simulations considered rocks, cement backfill, concrete cast-iron canisters. Glass were varied by coupling MATLAB modify initial, residual, resumption rates applying analytical GRAAL model dissolution. results indicate no preference over given canister type but that is preferable steel. suggest granite–bentonite–cast-iron environment yields lowest crown activities as canister, buffer/backfill, rock. Varying (initial, rates) had an understood migration, although changes arguably insignificant considering peak activity ILW.