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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.17 No.2 pp.127-137
DOI:https://doi.org/10.7733/jnfcwt.2019.17.2.127 Download PDF Export Citation
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.16 No.2 pp.165-172
DOI:https://doi.org/10.7733/jnfcwt.2018.16.2.165 Download PDF Export Citation
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.15 No.4 pp.313-320
DOI:https://doi.org/10.7733/jnfcwt.2017.15.4.313 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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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.4 pp.273-280
DOI:https://doi.org/10.7733/jkrws.2012.10.4.273 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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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.1 pp.27-36
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.1 pp.45-53
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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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A Study on Wasteform Properties of Spent Salt Treated with Zeolite and SAP
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.2 pp.99-105
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.1 pp.65-70
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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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Numerical Heat Transfer Analysis of the Electrowinning Cell in the Pyroprocessing
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.7 No.4 pp.213-218
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Stabilization of Radioactive Molten Salt Waste by Using Silica-Based Inorganic Material
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.3 pp.171-177
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Semi-Continuous Electrowinning of LiCl-Li2O Molten Salt
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.2 No.3 pp.211-217
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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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