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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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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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Detennination of 129I in simulated radioactive wastes using distiIlation technique
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.3 pp.141-148
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Groundwater Aow and Tritium Transport Modeling at Kori Nuclear Power Plant 1 Site
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.3 pp.149-159
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Alternative Concept to Enhance the Disposal Emciency for CANDU Spent Fuel Disposal System
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.3 pp.169-179
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Criticality Uncertainty Analysis of Spent Fuel Transport Cask applying Bmnup Credit
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.3 pp.191-198
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Precipitation-Filtering Method for Reuse of Uranium Electrokinetic Leachate
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.2 pp.63-71
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.2 pp.73-80
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An Evaluation of the Structural Integrity of the Polymer-Modified Cement Waste Form
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.2 pp.81-86
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The Corrosion Behavior of Cold-Rolled 304 Stainless Steel In Salt Spray Environments
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.2 pp.93-98
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Application of MARSSIM for Final Status Survey of the Decommissioning Project
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.2 pp.107-111
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.1 pp.1-11
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Synthetic Study on the Geological and Hydrogeological Model around KURT
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.1 pp.13-21
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An Investigation of Diffusion of Iodide Ion in Compacted Bentonite Containing Ag2O
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.1 pp.33-40
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.1 pp.49-62
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Study on the Geological Structure around KURT Using a Deep Borehole Investigation
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.4 pp.279-291
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Assessment on the Monitoring System for KURT using Optical Fiber Sensor Cable
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.4 pp.293-301
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Recovery of Residual LiCl-KCl Eutectic Salts in Radioactive Rare Earth Precipitates
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.4 pp.303-309
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