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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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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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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.5 No.4 pp.283-295
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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.1 pp.39-52
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Cesium Release Behavior during the Themal Treatment of High Burn-up Spent PWR Fuel
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.1 pp.53-64
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Measurement of the Gap and Grain Boundary Inventories of Cs, Sr in and I in Domestic Used PWR Fuels
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.1 pp.79-84
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Development of a Simulation Program for the Li-Reduction Process of PWR Spent Fuel
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.4 pp.335-344
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Analysis of the Disposal Tunnel and Disposal Pit Spacing for the Spent Fuel Repository Layout
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.4 pp.393-400
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A Structural Analytic Evaluation of a Connote Pad In a Spent Fuel Dry Storage Cask
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.2 pp.139-152
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Assessment of a Pre-conceptual Design of a Spent PWR Fuel Disposal Container
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.1 pp.41-50
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On-Site Transport and Storage of Spent Nuclear Fuel at Kori NPP by KN-12 Transport Cask
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.1 pp.51-58
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.3 No.3 pp.167-176
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Oxidation Behavior of Simudated Metallic U-Nb Alloys in Air
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.2 No.4 pp.239-244
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