Browse > Article
http://dx.doi.org/10.7733/jnfcwt.2016.14.3.211

Dechlorination/Solidification of LiCl Waste by Using a Synthetic Inorganic Composite with Different Compositions  

Kim, Na-Young (Korea Atomic Energy Research Institute)
Cho, In Hak (Korea Atomic Energy Research Institute)
Park, Hwan-Seo (Korea Atomic Energy Research Institute)
Ahn, Do-Hee (Korea Atomic Energy Research Institute)
Publication Information
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT) / v.14, no.3, 2016 , pp. 211-221 More about this Journal
Abstract
Waste salt generated from a pyro-processing for the recovery of uranium and transuranic elements has high volatility at vitrification temperature and low compatibility in conventional waste glasses. For this reason, KAERI (Korea Atomic Energy Research Institute) suggested a new method to de-chlorinate waste salt by using an inorganic composite named SAP ($SiO_2-Al_2O_3-P_2O_5$). In this study, the de-chlorination behavior of waste salt and the microstructure of consolidated form were examined by adding $B_2O_3$ and $Fe_2O_3$ to the original SAP composition. De-chlorination behavior of metal chloride waste was slightly changed with given compositions, compared with that of original SAP. In the consolidated forms, the phase separation between Si-rich phase and P-rich phase decreases with the amount of $Al_2O_3$ or $B_2O_3$ as a connecting agent between Si and P-rich phase. The results of PCT (Product Consistency Test) indicated that the leach-resistance of consolidated forms out of reference composition was lowered, even though the leach-resistance was higher than that of EA (Environmental Assessment) glass. From these results, it could be inferred that the change in the content of Al or B in U-SAP affected the microstructure and leach-resistance of consolidated form. Further studies related with correlation between composition and characteristics of wasteform are required for a better understanding.
Keywords
Dechlorination; Solidification; Waste salt; Synthetic inorganic composite; Wasteform; Leach resistance;
Citations & Related Records
Times Cited By KSCI : 2  (Citation Analysis)
연도 인용수 순위
1 H.S. Lee, G.I. Park, K.H. Kang, J.M. Hur, J.G. Kim, D.H. Ahn, Y.Z. Cho, and E.H. Kim, "Pyroprocessing Technology Development at KAERI", Nucl. Eng. Technol., 43(4), 317-328 (2011).   DOI
2 Y.G. Lavrinovich, M.A. Kuzin, M.V. Kormilitsyn, S.V. Tomilin, E.Y. Gribakin, and L.V. Zakharova, "Combined Vitrification of Chloride and Phosphate Wastes by Pyroelectrochemical Reprocessing of Nuclear Fuel", At. Energy, 101(6), 894-896 (2006).   DOI
3 D. Lexa, L. Leibowitz, and J. Kropf, "On the Reactive Occlusion of the (uranium trichloride + lithium chloride + potassium chloride) Eutectic Salt in Zeolite 4A", J. Nucl. Mater., 279(1), 57-64 (2000).   DOI
4 M. Lambregts and S.M. Frank, "Characterization of Cesium containing Glass-bonded Ceramic Waste Forms", Micropor. Mesopor. Mater., 64(1-3), 1-9 (2003).   DOI
5 W.L. Ebert, M.A. Lewis, and S.G. Johnson, "The Precision of Product Consistency Tests Conducted with a Glass-bonded Ceramic Waste Form", J. Nucl. Mater., 305(1), 37-51 (2002).   DOI
6 L.R. Morss, M.A. Lewis, M. K. Lichmann, and D. Lexa, "Cerium, Uranium, and Plutonium Behavior in Glass-bonded Sodalite, a Ceramic Nuclear Waste Form", J. Alloys Compd., 303-304, 42-48 (2000).   DOI
7 H.C. Eun, J.H. Choi, T.K. Lee, I.H. Cho, N.Y. Kim, J.U. Yu, H.S. Park, and D.H. Ahn, "Separation Characteristics of $NdCl_3$ from LiCl-KCl Eutectic Salt in a Reactive Distillation Process using $Li_2CO_3$ or $K_2CO_3$", J. Nucl. Fuel Cycle Waste Technol., 13(3), 181-186 (2015).   DOI
8 Y.Z. Cho, T.K. Lee, H.C. Eun, J.H. Choi, I.T. Kim, and G.I. Park, "Purification of used Eutectic (LiCl-KCl) Salt Electrolyte from Pyroprocessing", J. Nucl. Mater., 437(1-3), 47-54 (2013)   DOI
9 G. Leturcq, A. Grandjean, D. Rigaud, P. Perouty, and M. Charlot, "Immobilization of Fission Products Arising from Pyrometallurgical Reprocessing in Chloride Media", J. Nucl. Mater., 347(1-2), 1-11 (2005).   DOI
10 B.L. Meltcalfe and I.W. Donald, "Candidate Wasteforms for the Immobilization of Chloride-Containing Radioactive Waste", J. Non-Cryst. Solids, 348, 225-229 (2004).   DOI
11 Y.G. Lavrinovich, M.V. Kormilitsyn, V.I. Konovalov, I.V. Tselishchev, S.V. Tomilin, and V.M. Chistyakov, "Vitrification of Chloride Waste in the Pyroelectrochemical Method of Reprocessing Irradiated Nuclear Fuel", At. Energy, 95(5), 781-785 (2003).   DOI
12 H.S. Park, I.T. Kim, Y.J. Cho, H.C. Eun, and H.S. Lee, "Stabilization/Solidification of Radioactive Salt Waste by Using $xSiO_2-yAl_2O_3-zP_2O_5$ (SAP) Material at Molten Salt State", Environ. Sci. Technol., 42(24), 9357-9362 (2008).   DOI
13 M.K. Richmann, D.T. Reed, A.J. Kropf, S.B. Aase, and M.A. Lewis, "EXAFS/XANES Studies of Plutonium-loaded Sodalite/Glass Waste Forms", J. Nucl. Mater., 297(3), 303-312 (2001).   DOI
14 S. Donze, L. Montagne, and G. Palavit, "Thermal Conversion of Heavy Metal Chlorides ($PbCl_2$, $CdCl_2$) and Alkaline Chlorides (NaCl, KCl) into Phosphate Glasses", Chem. of Mater., 12(7), 1921-1925 (2000).   DOI
15 H.S. Park, I.T. Kim, H.Y. Kim, S.K. Ryu, and J.H. Kim, "Stabilization/Solidification of Radioactive Molten Salt Waste via Gel-Route Pretreatment", Environ. Sci. Technol., 41(4), 1345-1351 (2007).   DOI
16 H.S. Park, I.T. Kim, Y.J. Cho, H.C. Eun, and J.H. Kim, "Characteristics of Solidified Products containing Radioactive Molten Salt Waste", Environ. Sci. Technol., 41(21), 7536-7542 (2007).   DOI
17 H.S. Park, I.H. Cho, H.C. Eun, I.T. Kim, Y.J. Cho, and H.S. Lee, "Characteristics of Wasteform Composing of Phosphate and Silicate To Immobilize Radioactive Waste Salts", Environ. Sci. Technol., 45(5), 1932-1939 (2011).   DOI
18 I.W. Donald, B.L. Metcalfe, S.K. Fong, and L.A. Gerrard, "The Influence of $Fe_2O_3$ and $B_2O_3$ Additions on the Thermal Properties, Crystallization Kinetics and Durability of a Sodium Aluminum Phosphate Glass", J. Non-Cryst. Solids., 352(28-29), 2993-3001 (2006).   DOI