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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.3 pp.189-199
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Temperature Effect on the Swelling Pressure of a Domestic Compacted Bentonite Buffer
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.3 pp.207-213
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.3 pp.215-220
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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.3 pp.239-245
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Study on the Synthesis Method of Simulated CRUD for Chemical Decontamination in NPPs
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.2 pp.91-97
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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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A Study of Adsorption Behaviour of Humic Acid and Americium on the Kaolinite
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.2 pp.107-113
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.2 pp.115-122
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.2 pp.123-133
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Empirical model to estimate the thermal conductivity of granite with various water contents
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.2 pp.135-142
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Feasibility Study on the Vitrification of Concentrated Boric Acid Waste
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.2 pp.143-150
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.2 pp.151-158
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Groundwater Flow Modeling in a Block-Scale Fractured Rocks considering the Fractured Zones
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.2 pp.159-166
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Some notes on the Timing of Geological Disposal of CANDU Spent Fuels
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.2 pp.167-172
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Computational Analysis for a Molten-salt 티ectrowinner with Liquid Cadmium Cathode
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.1 pp.1-7
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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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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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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.1 pp.41-48
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