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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.3 pp.199-212
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KAERI Underground Research Tunnel(KURT)
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.3 pp.239-255
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.2 pp.91-101
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A Study on Ventilation System of Underground Low-Intermediate Radioactive Waste Repository
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.1 pp.65-78
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Measurement of the Radiolysis Gases Generated in Several Waste Forms by External Irradiation
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.4 pp.345-352
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.2 pp.133-138
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Alternative Method for the Treatment of Chemical Wastes Containing Uranium
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.2 pp.179-186
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Low and Intermediate Level Radioactive Waste Certification Program Plan
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.2 pp.187-195
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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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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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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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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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Identification of Uranium Species Released from the Waste Glass in Contact with Bentonite
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.3 No.3 pp.177-181
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.3 No.3 pp.183-192
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Simultaneous Assay of 14C and 3H in Evaporator Bottom by Chemical Oxidation Method
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.3 No.3 pp.193-200
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Development of ACBIO: A Biosphere Template Using AMBER for a Potential Radioactive Waste Repository
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.3 No.3 pp.213-229
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Characteristics of the Decontamination by the Melting of Aluminum Waste
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.3 No.2 pp.95-104
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Ventilation System Strategy for a Prospective Korean Radioactive Waste Repository
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.3 No.2 pp.135-148
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Determination of 241Am and 244Cm in Radwaste Samples
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.3 No.1 pp.1-7
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.3 No.1 pp.41-47
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JNFCWT
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- E-mail: krs@krs.or.kr