I-129 Waste Form Using Bi-Zn-P-Oxide Glass

摘要

I-129 is a problematic nuclide generated from the recycling of spent fuel by pyroprocess. Gaseous form of radiogenic iodine is trapped by using silver exchanged zeolite (AgX) at Korea Atomic Energy Research Institute (KAERI). We developed the low melting temperature glass system based on Bi_2O_3-P_2O_5 composition. Various additives were added to modify glass properties. We found that ingots containing AgI are formed with ZnO, CaCO_3, MgO, and Na_2CO_3 at around 600°C Analysis of microstructure and chemical durability revealed that AgI was encapsulated by glass matrix and formation of AgI compound is meaningful in fabricating iodine waste form.