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TiN Anode for Electrolytic Reduction of UO2 in Pyroprocessing
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.13 No.3 pp.229-233
DOI:https://doi.org/10.7733/jnfcwt.2015.13.3.229 Download PDF Export Citation
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Residual Liquid Behavior Calculation for Vacuum Distillation of Multi-component Chloride System
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.12 No.3 pp.179-189
DOI:https://doi.org/10.7733/jnfcwt.2014.12.3.179 Download PDF Export Citation
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Study on Governing Equations for Modeling Electrolytic Reduction Cell
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.12 No.3 pp.245-251
DOI:https://doi.org/10.7733/jnfcwt.2014.12.3.245 Download PDF Export Citation
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Loss of Li₂O Caused by ZrO₂ During the Electrochemical Reduction of ZrO₂ in Li₂O-LiCl Molten Salt
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.4 pp.229-236
DOI:https://doi.org/10.7733/jkrws.2012.10.4.229 Download PDF Export Citation
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An Electrochemical Reduction of TiO₂ Pellet in Molten Calcium Chloride
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.2 pp.97-104
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Patent Analysis for Pyroprocessing of Spent Nuclear Fuels
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.4 pp.247-258
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Study on Pre-treatment Method for Vitrification of Concentrated Wastes
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.3 pp.221-227
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.1 pp.19-32
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Corrosion Behavior of Y2O3 Coating in an Electrolytic Reduction Process
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.1 pp.33-39
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Development of an Oxide Reduction Process for the Treatment of PWR Spent Fuel
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.1 pp.77-84
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Reductive stripping of Np using a n-butyraldehyde from a loaded TBPphase containing Np
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.3 pp.163-170
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Development of a Simulation Program for the Li-Reduction Process of PWR Spent Fuel
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.4 pp.335-344
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.3 No.2 pp.105-112
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A Study on the Electrolytic Reduction Mechanism of Uranium Oxide in a LiCl-Li2O Molten Salt
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.1 No.1 pp.25-39
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