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Conceptual Reactive Transport Modeling of Long-term Concrete Degradation and Uranium Solubility
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.1 pp.35-44
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A Study on Establishment of Buffer Zone of Radioactive Waste Repository
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.1 pp.45-54
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Longevity Issues in Swelling Clay as a Buffer Material for a HLW Repository
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.1 pp.55-63
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Analysis of the Spent Fuel Cooling Time for a Deep Geological Disposal
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.1 pp.65-72
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.1 pp.73-75
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Separation and Recovery for the Analysis of Radioiodine in RI Wastes
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.4 pp.267-272
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Conceptual Geochemical Modeling of Long-term Hyperalkaline Groundwater and Rock Interaction
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.4 pp.273-281
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.4 pp.283-295
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A Feasibility Study on the Polymer Solidification of Evaporator Conccentrated Wastes
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.4 pp.297-308
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Reliability Evaluation of ACP Components under a Radiation Environment
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.4 pp.309-322
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Status of the International Cooperation Project, DECOVALEX for THM Coupling Analysis
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.4 pp.323-338
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.4 pp.339-350
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A Study on Japanese Experience to Secure the Interim Storage Facility for Nuclear Spent Fuel
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.4 pp.351-357
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.4 pp.358-360
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Stabilization of Radioactive Molten Salt Waste by Using Silica-Based Inorganic Material
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.3 pp.171-177
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.3 pp.179-188
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.3 pp.189-197
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.3 pp.199-212
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Numerical analysis of Off-Gas Flow in Hot Area of the Vitrification Plant
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.3 pp.213-220
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The Direct Decomposition of Ion-Exchange Resins by Fenton's Reagent
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.3 pp.221-227
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