Modeling and analysis of a molten-salt electrolytic process for nuclear waste treatment
A pyrochemical processing has become one of the potential technologies for a future nuclear fuel cycle. An integrated multi-physics simulation and electrotransport model of a molten-salt electrolytic process are proposed and discussed with respect to the recovery of pure uranium when using thermoche...
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| Published in | Journal of radioanalytical and nuclear chemistry Vol. 280; no. 2; pp. 401 - 404 |
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| Main Authors | , , , , , , , , , , |
| Format | Journal Article |
| Language | English |
| Published |
Dordrecht
Springer Netherlands
01.05.2009
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| Subjects | |
| Online Access | Get full text |
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| Abstract | A pyrochemical processing has become one of the potential technologies for a future nuclear fuel cycle. An integrated multi-physics simulation and electrotransport model of a molten-salt electrolytic process are proposed and discussed with respect to the recovery of pure uranium when using thermochemical data. This study has been performed to provide information for diffusion boundary layers between the molten salt (KCl-LiCl) and electrode. The diffusion-controlled electrochemical model demonstrate a prediction of the electrotransport behaviors of LWR spent fuel as a function of the time up to the corresponding electrotransport satisfying a given applied current based on a galvanostatic electrolysis. |
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| AbstractList | A pyrochemical processing has become one of the potential technologies for a future nuclear fuel cycle. An integrated multi-physics simulation and electrotransport model of a molten-salt electrolytic process are proposed and discussed with respect to the recovery of pure uranium when using thermochemical data. This study has been performed to provide information for diffusion boundary layers between the molten salt (KCl-LiCl) and electrode. The diffusion-controlled electrochemical model demonstrate a prediction of the electrotransport behaviors of LWR spent fuel as a function of the time up to the corresponding electrotransport satisfying a given applied current based on a galvanostatic electrolysis. |
| Author | Kim, S. H. Ahn, D. H. Bae, J. D. Hwang, I. S. Kwon, S. W. Shim, J. B. Lee, H. S. Park, B. G. Paek, S. Kim, E. H. Kim, K. R. |
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| CitedBy_id | crossref_primary_10_1007_s10967_010_0682_6 crossref_primary_10_1155_2015_407842 crossref_primary_10_1063_5_0173707 crossref_primary_10_13182_NT182_98 crossref_primary_10_1016_j_jallcom_2010_04_228 crossref_primary_10_1016_j_nucengdes_2013_01_009 crossref_primary_10_1002_er_6267 crossref_primary_10_1149_1945_7111_ac7bb1 crossref_primary_10_1021_acs_jpcb_3c03938 |
| Cites_doi | 10.1149/1.2069109 10.13182/NT02-A3322 |
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| Copyright | Akadémiai Kiadó, Budapest, Hungary 2009 |
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| Keywords | Uranium Deposition Uranium Diffusion Boundary Layer Diffusion Layer Thickness Molten Salt |
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| References | J. D. Bae, K. W. Yi, B. G. Park, I. S. Hwang, H. Y. Lee, Development of an Electrochemical-Hydrodynamic Model for Electrorefining Process, Proceedings of Global 2005, Tsukuba, Japan, (Oct. 9–13, 2005). AhluwaliaR.HuaT. Q.Nucl. Technol.200114041 GNEP Technical Integration Office, Global Nuclear Energy Partnership Technology Development Plan, GNEP-TECH-TR-PP-2007-00020, Rev. 0 (July 2007). BenedictM.PigfordT. H.LeviH. W.Nuclear Chemical Engineering19812New YorkMcGraw-Hill Book Company84 B. G. Park, I. S. Hwang, A Time-dependent Simulation of an Electrochemical Process with Liquid Metal and Molten Salt, The 195th Meeting of The Electrochemical Society, Seattle, (May 2–6, 1999). TomczukZ.Uranium Transport to Solid Electrodes in Pyrochemical Reprocessing of Nuclear FuelJ. Electrochemical Soc.199213912352310.1149/1.20691091:CAS:528:DyaK3sXmvV2itA%3D%3D NewmanJ. S.Electrochemical Systems1993Englewood Cliffs, New JerseyPrentice Hall335 LiS. X.SofuT.JohnsonT. A.LaugD. V.Journal of New Material for Electrochemical Systems200032591:CAS:528:DC%2BD3cXlsFGjsr8%3D CFX Solver Theory, Ansys Inc., 2003. A. J. Bard, L. R. Faulkner, Electrochemical Methods, Fundamentals and Applications, 2nd ed., John Wiley & Sons, Inc., 2001, p. 98. 534_CR2 R. Ahluwalia (534_CR3) 2001; 140 S. X. Li (534_CR4) 2000; 3 534_CR6 534_CR10 534_CR5 Z. Tomczuk (534_CR9) 1992; 139 534_CR8 J. S. Newman (534_CR7) 1993 M. Benedict (534_CR1) 1981 |
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| Title | Modeling and analysis of a molten-salt electrolytic process for nuclear waste treatment |
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