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Nuclear Fuel Cycle Analysis Technology to Develop Advanced Nuclear Fuel Cycle
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.4 pp.219-230
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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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Sensitivity Analysis of Depletion Parameters for Heat Load Evaluation of PWR Spent Fuel Storage Pool
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.4 pp.237-245
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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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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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