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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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Study of morphology on the Oxidation and the Annealing of High Burn-hp UO2 Spent Fuel
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.3 No.4 pp.301-307
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.3 No.3 pp.167-176
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Preliminary Study on the Development of Alternative Methods for the Treatment of TRISO Fuels
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.3 No.3 pp.201-211
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Micro Sampling System for Highly Radioactive Specimen by Laser Ablation
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.3 No.1 pp.17-21
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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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Analysis of High Radioactive Materials in Irradiated DUPIC SIMFUEL Using EPMA
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.2 No.2 pp.125-133
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