Immobilization of molten salt waste into MZr2(PO4)3 (M=Li, Na, Cs, Sr) |
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| Authors: | Hwan-Seo Park In-Tae Kim Hwan-Young Kim Seung-Kon Ryu Joon-Hyung Kim |
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| Affiliation: | (1) Nuclear Fuel Cycle R&D Group, Korea Atomic Energy Research Institute, 150 Deokjin-dong, Yusung-gu, Daejeon, 305-353, Korea;(2) Nuclear Fuel Cycle R&D Group, Korea Atomic Energy Research Institute, 150 Deokjin-dong, Yusung-gu, Daejeon, 305-353, Korea;(3) Nuclear Fuel Cycle R&D Group, Korea Atomic Energy Research Institute, 150 Deokjin-dong, Yusung-gu, Daejeon, 305-353, Korea;(4) Department of Chemical Engineering, Chungnam National University, 220 Gung-dong, Yusung-gu, Daejeon, 305-764, Korea;(5) Nuclear Fuel Cycle R&D Group, Korea Atomic Energy Research Institute, 150 Deokjin-dong, Yusung-gu, Daejeon, 305-353, Korea |
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| Abstract: | Summary Amorphous zirconium phosphate (Zr(HPO4)2.nH2O, AM-ZP) has been investigated as a material for selective removal of Cs or Sr from molten salt waste at aqueous state and its ceramic waste form. NZP (MZr2P3O12, M=Li, Na, Cs, and Sr), was synthesized by three methods and evaluated their durability by the Product Consistency Test (PCT) method. AM-ZP has a high selectivity on Cs and Sr even in the presence of Li with high concentration. From the leaching data, the leached fractions (LF∞) of each product at a given time in infinite leachate volume can be calculated by a semi-empirical equation. The LF∞ of Li, Na, Cs and Sr on the product prepared by composition-adjusting process were 0.143, 0.078, 0.017, and 0.034, respectively. It can be concluded that AM-ZP is an effective material for selective removal of radionuclides from molten salt waste and its metal-loaded ZP can be changed into a durable waste form close to NZP structure by a composition-adjusting process. |
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