Residual Salt Separation from Simulated Spent Nuclear Fuel Reduced in a LiCl-Li2O Salt
Author:
Affiliation:
1. Korea Atomic Energy Research Institute
Publisher
Society of Chemical Engineers, Japan
Subject
General Chemical Engineering,General Chemistry
Link
http://www.jstage.jst.go.jp/article/jcej/39/12/39_12_1291/_pdf
Reference8 articles.
1. The physicochemical and electrochemical behavior of lithium oxide in the equimolar NaCl–KCl melt
2. Impurity Evaluation of Fused Lithium Chloride Salt for a Pilot-Scale Spent-Oxide-Fuel Reduction Process
3. Metallization of U3O8via catalytic electrochemical reduction with Li2O in LiCl molten salt
4. Kubaschewski, O. and C. B. Alcock; Metallurgical Thermochemistry, 5th ed., pp. 358–384, Pergamon Press, Oxford, U.K. (1979)
5. Mass-spectrometric study of the vaporization of Li2O(s) and thermochemistry of gaseous LiO, Li2O, Li3O, and Li2O2
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1. An Integrated Mass Balance Model for Pyrochemical Processing;Nuclear Technology;2011-08
2. Advances in the ACP Facility Electrochemical Reduction Process;Nuclear Technology;2010-09
3. Reduction of U3O8 to U by a metallic reductant, Li;Journal of Radioanalytical and Nuclear Chemistry;2009-08-28
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