Browse > Article
http://dx.doi.org/10.7733/jkrws.2012.10.1.045

Stabilization/Solidification of Radioactive LiCl-KCl Waste Salt by Using SiO2-Al2O3-P2O5 (SAP) inorganic composite: Part 1. Dechlorination Behavior of LiCl-KCl and Characteristics of Consolidation  

Cho, In-Hak (Korea Atomic Energy Research Institute)
Park, Hwan-Seo (Korea Atomic Energy Research Institute)
Ahn, Soo-Na (Korea Atomic Energy Research Institute)
Kim, In-Tae (Korea Atomic Energy Research Institute)
Cho, Yong-Zun (Korea Atomic Energy Research Institute)
Publication Information
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT) / v.10, no.1, 2012 , pp. 45-53 More about this Journal
Abstract
The metal chloride wastes from a pyrochemical process to recover uranium and transuranic elements has been considered as a problematic waste difficult to apply to a conventional solidification method due to the high volatility and low compatibility with silicate glass. In this study, a dechlorination approach to treat LiCl-KCl waste for final disposal was adapted. In this study, a $SiO_2-Al_2O_3-P_2O_5$ (SAP) inorganic composite as a dechlorination agent was prepared by a conventional sol-gel process. By using a series of SAPs, the dechlorination behavior and consolidation of reaction products were investigated. Different from LiCl waste, the dechlorination reaction occurred mainly at two temperature ranges. The thermogravimetric test indicated that the first reaction range was about $400^{\circ}C$ for LiCl and the second was about $700^{\circ}C$ for KCl. The SAP 1071 (Si/Al/P=1/0.75/1 in molar) was found to be the most favorable SAP as a dechlorination agent under given conditions. The consolidation test revealed that the bulk shape and the densification of consolidated forms depended on the SAP/Salt ratios. The leaching test by PCT-A method was performed to evaluate the durability of consolidated forms. This study provided the basic information on the dechlorination approach. Based on the experimental results, the dechlorination method using a $SiO_2-Al_2O_3-P_2O_5$ (SAP) could be considered as one of alternatives for the immobilization of waste salt.
Keywords
Immobilization; Volatile radionulide; Sol-gel method; $SiO_2-Al_2O_3-P_2O_5$; Metal chloride; pyroprocess;
Citations & Related Records
Times Cited By KSCI : 1  (Citation Analysis)
연도 인용수 순위
1 B. L. Metcalfe, I. W. Donald, "Candidate Wasteforms for the Immobilization of Chloridecontaining Radioactive Waste", J. Non-Cryst. Solids., 348, pp. 225-229 (2004).   DOI   ScienceOn
2 L. R. Morss, M. A. Lewis, M. K. Lichmann, D. Lexa, "Cerium, Uranium, and Plutonium Behavior in Glass-bonded Sodalite, a Ceramic Nuclear Waste Form", J. Alloys Compd., 303, pp. 42-48 (2000).
3 D. Lexa, L. Leibowitz, J. Kropf, "On the Reactive Occlusion of the (uranium trichloride + lithium chloride + potassium chloride) Eutectic Salt in Zeolite 4A", J. Nucl, Mater., 279, pp. 57-64 (2000).   DOI   ScienceOn
4 M. K. Lichmann, D. T. Reed, A. J. Kropf, S. B. Aase, M. A. Lewis, "EXAFS/XANES Studies of Plutonium-loaded Sodalite/Glass Waste Forms", J. Nucl. Mater., 297, pp. 303-312 (2001).   DOI   ScienceOn
5 D. E. Day, Z. Wu, C. S. Ray, P. Hrma, "Chemically Durable Iron Phosphate Glass Wate Forms", J. Non-Cryst. Solid, 241, pp. 1-12 (1998).   DOI   ScienceOn
6 M. G. Mesko, D. E. Day, "Immobilization of Spent Nuclear Fuel in Iron Phosphate Glass", J. Nucl. Mater., 273, pp. 27-36 (1999).   DOI   ScienceOn
7 B. G. Ahn, H. S. Park, H. Y. Kim, H. S. Lee, I. T. Kim, "Immobilization of Radioactive Rare Earth Oxide Waste by Solid Phase Sintering", J. of the Korean Radioactive Waste Society, 8(1), pp. 49-56, (2010).
8 G. Leturcq, A. Grandjean, D. Rigaud, P. Perouty, M. Charlot, "Immobilization of Fission Products Arising from Pyrometallurgical Reprocessing in Chloride Media". J. Nucl. Mater., 347, pp. 1-11 (2005).   DOI   ScienceOn
9 Y. Ikeda, Y. Takesima, "Conversion Reaction of Metal Chloridesinto Oxides with Boric Acid", J. Nucl. Sci. Technol., 32, pp. 1138-1145 (1995).   DOI
10 H. S. Park, I. T. Kim, H. Y. Kim, J. H. Kim, "Stabilization of Radioactive Moltne Salt Waste by Using Silica-Based Inorganic Material", J. of the Korean Radioactive Waste Society, 5(3), pp. 171-177, (2007)
11 I. W. Donald, B. L Metcalfe, S. K. Fong, L. A. Gerrard, "The Influence of $Fe_2O_3$ and $B_2O_3$ Addtions on the Thermal Properties, Crystallization Kinetics and Durability of a Sodium Aluminum Phosphate Glass", J. Non-Cryst. Solids., 352, pp. 2993-3001 (2006).   DOI   ScienceOn
12 ASTM C1285-02 "Standard Test Methods for Determining Chemical Durability of Nuclear, Hazardous, and Mixed Waste Glasses and Multiphase Glass Ceramics: The Product Consistency Test (PCT)", (2008).
13 H. S. Park, I. T. Kim, H. Y. Kim, S. K. Ryu, J. H. Kim, "Stabilization/Solidification of Radioactive Molten Salt Waste via Gel-route Pretreatment", Environ. Sci. Technol., 41, pp. 1345-1351 (2007).   DOI   ScienceOn
14 H. S. Park, I. T. Kim, Y. Z. Cho, H. C. Eun, H. S. Lee, "Stabilization/Solidification of Radioactive Salt Waste by Using $xSiO-yAl_2O_3-zP_2O_5$ (SAP) Material at Molten Salt State", Environ. Sci. Technol., 42, pp. 9357-9362 (2008).   DOI   ScienceOn
15 Yu. G. Lavrinovich, M. A. Kuzin, M. V. Kormilisyn, S. V. Tomilin, E. Yu. Gribakin and L.V. Zakharova, "Combined Vitrification of Chloride and Phosphate Waste by Pyroelectrochemical Reprocessing of Nuclear Fuel," At. Energy, 101(6), pp. 894-896 (2006).   DOI   ScienceOn
16 W. L. Ebert. Testing to Evaluate the Suitability of Waste Forms Developed for Electrometallurgically Treated Spent Sodium-Boned Nuclear Fuel for Disposal in the Yucca Mountain Repository, Chemical Engineering Division Argonne National Laboratory Report, pp. 134, ANL-05/43 (2005).