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An Experimental Study on the Sorption of Uranium(VI) onto a Bentonite Colloid
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.3 pp.235-243
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The Test for Verifying a Tip-Over Analysis of a Dry Storage Cask
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.3 pp.245-253
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.3 pp.255-263
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.3 pp.265-273
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Comparison of the Correction Methods for Gamma Ray Attenuation in the Radioactive Waste Drum Assay
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.3 pp.275-284
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National Policy and Status on Management of Spent Nuclear Fuel
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.3 pp.285-299
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.3 pp.301-309
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.2 pp.117-131
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.2 pp.133-138
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A Structural Analytic Evaluation of a Connote Pad In a Spent Fuel Dry Storage Cask
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.2 pp.139-152
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Bio-Denitrification of the Nitrate Waste Solution from the Lagoon Sludge in a Batch Fermenter
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.2 pp.153-159
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.2 pp.161-170
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A Framework of Decommissioning Cost Estimation for Nuclear Research Facilities
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.2 pp.171-178
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Alternative Method for the Treatment of Chemical Wastes Containing Uranium
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.2 pp.179-186
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Engineering-scale Validation Test for the T-H-M Behaviors of a HLW Disposal System
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.2 pp.197-207
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.1 pp.1-7
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.1 pp.9-15
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Structural Safety Analysis of Openable Working Table in ACP Hot Cell for Spent Fuel Treatment
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.1 pp.17-24
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.1 pp.25-32
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Melting Characteristics for Radioactive Aluminum Wastes in Electric Arc Furnace
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.1 pp.33-40
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