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Thermal Analysis of a Retrievable CANDU Spent Fuel Disposal Tunnel
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.2 pp.119-128
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Sorptionof Eu(III) Th(IV) on Bentonite Colloids Considering Their Precipitation an Colloid Formation
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.2 pp.129-139
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Uncertainty Cases in Economic Evaluation of Back-End Nuclear Fuel Cycle
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.2 pp.141-145
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Development of a Computer Program for the Analysis of Logistics of PWR Spent Fuels
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.2 pp.147-154
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Current Status and Characterization of CANDU Spent Fuel for Geological Disposal System Design
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.2 pp.155-162
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.1 pp.1-9
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.1 pp.11-15
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A Study on Plasma Etching Reaction of Cobalt for Metallic Surface Decontamination
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.1 pp.17-23
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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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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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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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