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Improvement of Pilot-scale Electrokinetic Remediation Technology for Uranium Removal
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.11 No.2 pp.77-83
DOI:https://doi.org/10.7733/jkrws.2013.11.2.77 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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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.3 pp.219-228
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.1 pp.21-26
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.1 pp.27-36
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.1 pp.45-53
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Source Term Characterization for Structural Components in 17 x 17 KOFA Spent Fuel Assembly
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.4 pp.347-353
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.3 pp.181-188
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.1 pp.65-70
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Development of an Oxide Reduction Process for the Treatment of PWR Spent Fuel
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.1 pp.77-84
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Evaluation of Dark Spots Formated on the High Temperature Metal FilterElements
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.3 pp.171-178
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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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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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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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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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Electrochemical Decontamination of Metallic Wastes Contaminated with Uranium Compounds
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.1 No.1 pp.11-23
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A Study on the Electrolytic Reduction Mechanism of Uranium Oxide in a LiCl-Li2O Molten Salt
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.1 No.1 pp.25-39
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