论文信息 - I-129 Waste form Using Bi-Zn-P-Oxide Glass

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

Abstract 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 Bi2O3-P2O5 composition. Various additives were added to modify glass properties. We found that ingots containing AgI are formed with ZnO, CaCO3, MgO, and Na2CO3 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.

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