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Sorptive Removal of Radionuclides (Cobalt, Strontium and Cesium) using AMP/IO-PAN Composites
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.11 No.4 pp.259-269
DOI:https://doi.org/10.7733/jnfcwt-k.2013.11.4.259 Download PDF Export Citation
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Travel Times of Radionuclides Released from Hypothetical Multiple Source Positions in the KURT Site
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.11 No.4 pp.281-291
DOI:https://doi.org/10.7733/jnfcwt-k.2013.11.4.281 Download PDF Export Citation
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Development of Sorption Database (KAERI-SDB) for the Safety Assessment of Radioactive Waste Disposal
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.11 No.1 pp.41-54
DOI:https://doi.org/10.7733/jkrws.2012.11.1.41 Download PDF Export Citation
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.4 pp.237-246
DOI:https://doi.org/10.7733/jkrws.2012.10.4.237 Download PDF Export Citation
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.4 pp.295-303
DOI:https://doi.org/10.7733/jkrws.2012.10.4.295 Download PDF Export Citation
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.1 pp.41-48
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.3 pp.215-220
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Research Status on the Radionuclide and Colloid Migration in Underground Research Facilities
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.7 No.4 pp.243-253
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Separation of Radionuclide from Dismantled Concrete Waste
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.7 No.2 pp.79-86
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Roles and Importance of Microbes in the Radioactive Waste Disposal
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.7 No.1 pp.63-72
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Numerical analysis of Off-Gas Flow in Hot Area of the Vitrification Plant
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.3 pp.213-220
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Current Status of the Spent Filter Waste and Consideration of Its Treatment Method in KAERI
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.3 pp.257-265
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Correlation of l37Cs/60Co Activity Ratio in Radwaste with Primary coolant
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.1 pp.9-17
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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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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.4 pp.311-320
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.4 pp.373-384
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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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Solidification of Molten Salt Waste by Gel-Route Pre-treatment
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.3 No.1 pp.57-65
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