Browse > Article
http://dx.doi.org/10.7733/jnfcwt.2017.15.1.83

A Basic Study on Capture and Solidification of Rare Earth Nuclide (Nd) in LiCl-KCl Eutectic Salt Using an Inorganic Composite With Li2O-Al2O3-SiO2-B2O3 System  

Kim, Na-Young (Korea Atomic Energy Research Institute)
Eun, Hee-Chul (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.15, no.1, 2017 , pp. 83-90 More about this Journal
Abstract
The pyroprocessing of spent nuclear fuel generates LiCl-KCl eutectic waste salt containing radioactive rare earth nuclides. It is necessary to develop a simple process for the treatment of LiCl-KCl eutectic waste in a hot-cell facility. In this study, capture and solidification of a rare earth nuclide (Nd) in LiCl-KCl eutectic salt using an inorganic composite with a $Li_2O-Al_2O_3-SiO_2-B_2O_3$ system was conducted to simplify the existing separation and solidification process of rare earth nuclides in LiCl-KCl eutectic waste salt from the pyroprocessing of spent nuclear fuel. More than 98wt% of Nd in LiCl-KCl eutectic salt was captured when the mass ratio of the composite was 0.67 over $NdCl_3$ in the eutectic salt. The content of $Nd_2O_3$ in the Nd captured-composite reached about 50wt%, and this composite was directly fabricated into a homogeneous and chemical resistant glass waste in a monolithic form. These results will be utilized in designing a process to simplify the existing separation and solidification process.
Keywords
Spent nuclear fuel; Pyroprocessing; LiCl-KCl eutectic waste salt; Capturing and solidification of rare earth nuclide; Inorganic composite with $Li_2O-Al_2O_3-SiO_2-B_2O_3$ system;
Citations & Related Records
Times Cited By KSCI : 3  (Citation Analysis)
연도 인용수 순위
1 K.R. Kim, D.H. Ahn, J.B. Shim, S. Paek, I.T. Kim, and Y. Jung, "Pyrochemical extraction analysis of an immiscible molten LiCl-KCl/Cd system", J. Nucl. Chem., 304, 329-335 (2015).   DOI
2 D. Rappleye, S.M. Jeong, and M. Simpson, "Application of multivariate analysis techniques to safeguards of the electrochemical treatment of used nuclear fuel", J. Nucl. Energy, 77, 265-272 (2015).   DOI
3 H.S. Lee, G.I. Park, G.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
4 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
5 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 $K_2CO_3$", JNFCWT, 13(3), 181-186 (2015).
6 J.H. Choi, I.H. Cho, H.C. Eun, H.S. Park, Y.Z. Cho, K.R. Lee, G.I. Park, S.H. Kim, C.H. Shin, and J.K. Kim, "Fabrication and physical properties of lanthanide oxide glass wasteform for the immobilization of lanthanide oxide wastes generated form pyrochemical process", J. Radioanal. Nucl. Chem., 299(3), 1731-1738 (2014).   DOI
7 C.W. Kim, J.Y. Kim, S.J. Maeng, J.K. Park, and T.W. Hwang, "Evaluation of Chemical Durability of Vitrified Forms for Simulated Radioactive Waste Using Product Consistency Test(PCT) and Vapor Hydration Test(VHT)", J. Korean Rad. Was. Soci., 4(3), 227-234 (2006)
8 C.M. Jantzen, N.E. Bibler, D.C. Beam, C.L. Crawford, and M.A. Picket, Characterization of the defense waste processing facility(DWPF) environmental assessment(EA) glass standard reference material(U), Westinghouse Savannah River Co Report, 1-96, WSRC-TR-92-346 (1992).
9 J.H. Choi, H.C. Eun, K.R. Lee, I.H. Cho, T.K. Lee, H.S. Park, and D.H. Ahn, "Fabrication of rare earth calcium phosphate glass waste forms for the immobilization of rare earth phosphates generated from pyrochemical process", J. Non-Cryst. Solids, 434, 79-84 (2016).   DOI