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The Comparison on Treatment Method of Liquid Radioactive Waste in Yonggwang #3&4 and #5&6
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.2 No.3 pp.219-230
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.2 No.2 pp.87-96
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.2 No.2 pp.97-104
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.2 No.2 pp.105-112
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The BIDAS Program : Bioassay Data Analysis Software for Evaluating Radionuclide Intake and Dose
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.2 No.2 pp.113-124
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Analysis of High Radioactive Materials in Irradiated DUPIC SIMFUEL Using EPMA
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.2 No.2 pp.125-133
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A Parametric Study on the Sorption of U(VI) onto Granite
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.2 No.2 pp.135-143
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Thermal Analysis of a Spent Fuel Storage Cask under Normal and Off-Normal Conditions
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.2 No.1 pp.13-22
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.2 No.1 pp.23-34
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A Study on the Improvement of Scaling Factor Determination Using Artificial Neural Network
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.2 No.1 pp.35-40
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.2 No.1 pp.41-51
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Influence of the Monitoring Interval and Intake Pattern for the Evaluation of Intake
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.2 No.1 pp.53-59
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A Study on the Clearance Level(draft) for the Steel Scrap from the KRR-1 & 2 Decommissioning
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.2 No.1 pp.61-67
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Estimation of Radioactive Inventory for a major component of Reactor in Decommissioning
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.2 No.1 pp.69-75
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.1 No.1 pp.1-10
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Electrochemical Decontamination of Metallic Wastes Contaminated with Uranium Compounds
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.1 No.1 pp.11-23
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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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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.1 No.1 pp.55-64
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A Study on the Removal Method of Radioactive Corrosion Product using its Magnetic Property
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.1 No.1 pp.73-79
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.1 No.1 pp.81-92
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