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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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Design Enhancement of CANDU S/F Storage Basket
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.2 pp.105-115
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An Evaluation on the Radiation Shielding of the Radwaste Drum Assay Facility
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.2 pp.117-123
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A study on dehydration of rare earth chloride hydrate
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.2 pp.125-132
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.1 pp.1-11
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Solubilities and Major Species of Selenium and Technetium in the KURT Groundwater Conditions
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.1 pp.13-19
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.1 pp.21-26
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.1 pp.27-36
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Safety Evaluation of Radioactive Material Transport Package under Stacking Test Condition
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.1 pp.37-43
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.1 pp.45-53
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The State-of-the Art of the Borehole Disposal Concept for High Level Radioactive Waste
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.1 pp.55-62
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.1 pp.63-75
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Influence of Water Salinity on the Hydraulic Conductivity of Compacted Bentonite
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.4 pp.199-206
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.4 pp.207-217
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Nuclear Fuel Cycle Analysis Technology to Develop Advanced Nuclear Fuel Cycle
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.4 pp.219-230
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Safety Review of Severe Accident Senario for Wet Spent Fuel Storage Facility
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.4 pp.231-236
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Sensitivity Analysis of Depletion Parameters for Heat Load Evaluation of PWR Spent Fuel Storage Pool
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.4 pp.237-245
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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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The Removal of NOx by Mediated Bectrochemical Oxidation Using
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.3 pp.121-129
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Evaluation of Na2CO3-H2O2 Carbonate Solution Stability
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.3 pp.131-139
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