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Chemical and Mechanical Sustainability of Silver Tellurite Glass Containing Radioactive Iodine-129
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.19 No.3 pp.323-330
DOI:https://doi.org/10.7733/jnfcwt.2021.19.3.323 Download PDF Export Citation
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Characterisation and Durability of a Vitrified Wasteform for Simulated Chrompik III Waste
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.19 No.3 pp.339-352
DOI:https://doi.org/10.7733/jnfcwt.2021.19.3.339 Download PDF Export Citation
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.18 No.3 pp.363-372
DOI:https://doi.org/10.7733/jnfcwt.2020.18.3.363 Download PDF Export Citation
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.18 No.1 pp.31-41
DOI:https://doi.org/10.7733/jnfcwt.2020.18.1.31 Download PDF Export Citation
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Feasibility Study on Vitrification for Rare Earth Wastes of PyroGreen Process
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.11 No.1 pp.1-9
DOI:https://doi.org/10.7733/jkrws.2013.11.1.1 Download PDF Export Citation
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Development on Glass Formulation for Aluminum Metal and Glass Fiber
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.4 pp.247-254
DOI:https://doi.org/10.7733/jkrws.2012.10.4.247 Download PDF Export Citation
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Feasibility Study on the Vitrification of Concentrated Boric Acid Waste
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.2 pp.143-150
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Immobilization of Radioactive Rare Earth oxide Waste by Solid Phase Sintering
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.1 pp.49-56
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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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Characteristics of Vitrification Process and Vitrified Form for Radioactive Waste
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.2 No.3 pp.175-180
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Long-term leach rates of simulated borosilicate waste glasses under a repository condition
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.1 No.1 pp.41-53
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