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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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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.13 No.3 pp.235-242
DOI:https://doi.org/10.7733/jnfcwt.2015.13.3.235 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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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.11 No.4 pp.325-332
DOI:https://doi.org/10.7733/jnfcwt-k.2013.11.4.325 Download PDF Export Citation
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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 the Fabrication of Uranium-Cadmium Alloy and its Distillation Behavior
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.4 pp.261-267
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Development of Liquid Cadmium Cathode Structure for the Inhibition of Uranium Dendrite Growth
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.1 pp.9-17
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.1 pp.19-32
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.1 pp.57-63
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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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Uranium ingot casting method with Uranium deposit in a Pyroprocessing
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.1 pp.85-89
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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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Assessment of a U Product Purity from Pyroprocessing Spent EBR-II Fuel
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.7 No.3 pp.167-174
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Reference Spent Nuclear Fuel for Pyroprocessing Facility Design
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.3 pp.225-232
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A Conceptual Design Study for a Spent Fuel Pyroprocessing Facility of a Demonstration Scale
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.3 pp.233-244
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.4 pp.283-295
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