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Structural Safety Analysis of Openable Working Table in ACP Hot Cell for Spent Fuel Treatment
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.1 pp.17-24
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.1 pp.25-32
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Melting Characteristics for Radioactive Aluminum Wastes in Electric Arc Furnace
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.1 pp.33-40
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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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The Characterization of Spherical Perticles in Steam Generator Sludge
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.1 pp.59-64
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.1 pp.65-75
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Structural Safety Analysis Of Rear Door in ACP Hotcell Facility for Spent Fuel Treatment
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.1 pp.77-85
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Current Status and Projection of Spent Nuclear Fuel for Geological Disposal System Design
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.1 pp.87-93
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.1 pp.94-96
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.3 No.4 pp.269-278
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.3 No.4 pp.279-291
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PFC Ultrasonic Decontamination Efficiency on the Various Types of Metal Specimens
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.3 No.4 pp.293-300
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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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Separation for the Determination of 59/63Ni in Radioactive Wastes
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.3 No.4 pp.309-317
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Evaluation Model and Experimental Validation of Tritium in Agricultural Plant
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.3 No.4 pp.319-328
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Effect of engineered barriers on the leach rate of cesium from spent PWR fuel
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.3 No.4 pp.329-333
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Determination of Forward Dissolution Rate of Glass by a Single-Pass Flow-Through Test
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.3 No.4 pp.335-340
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An Experimental Study on the Erosion of a Compacted Calcium Bentonite Block
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.3 No.4 pp.341-348
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Analysis of the Disposal Tunnel Spacing and Disposal Pit Pitch for the HLW Repository Design
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.3 No.4 pp.349-358
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