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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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Heat Transfer Analysis around Transport Cask under Transport Hood
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.3 pp.161-167
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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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Investigationof Perceptioo of Nuclear Power by the LOCaI Resideots Adjacent to Nuclear Intallations
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.3 pp.181-189
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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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Very Low Level Radioactive Solid Waste Management in CHINA
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.2 pp.87-92
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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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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.2 pp.99-105
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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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Determination of Design Basis for a Storage System for Spent Fuel in Korea
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.2 pp.113-119
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.2 pp.120-122
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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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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.1 pp.23-32
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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.41-48
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