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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.15 No.4 pp.381-390
DOI:https://doi.org/10.7733/jnfcwt.2017.15.4.381 Download PDF Export Citation
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Radiological Impact Assessment for the Domestic On-road Transportation of Radioactive Isotope Wastes
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.14 No.3 pp.279-287
DOI:https://doi.org/10.7733/jnfcwt.2016.14.3.279 Download PDF Export Citation
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Structural Safety Analysis of Lifting Device for Spent Fuel Dual-purpose Metal Cask
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.12 No.4 pp.299-314
DOI:https://doi.org/10.7733/jnfcwt.2014.12.4.299 Download PDF Export Citation
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.12 No.4 pp.315-334
DOI:https://doi.org/10.7733/jnfcwt.2014.12.4.315 Download PDF Export Citation
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Understanding and Their Application of GoldSim Transport Pathways to Mass Trasport Simulation
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.12 No.2 pp.135-151
DOI:https://doi.org/10.7733/jnfcwt.2014.12.2.135 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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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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Heat Transfer Analysis around Transport Cask under Transport Hood
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.3 pp.161-167
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Criticality Uncertainty Analysis of Spent Fuel Transport Cask applying Bmnup Credit
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.3 pp.191-198
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.2 pp.73-80
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.2 pp.99-105
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Computational Analysis for a Molten-salt 티ectrowinner with Liquid Cadmium Cathode
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.1 pp.1-7
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A Finite Element Modeling for the Puncture Drop Test of a Cask with the Failure of Impact Limiter
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.7 No.1 pp.9-16
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Development of a Computer Program for the Analysis of Logistics of PWR Spent Fuels
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.2 pp.147-154
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.1 pp.11-15
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Conceptual Reactive Transport Modeling of Long-term Concrete Degradation and Uranium Solubility
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.1 pp.35-44
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.3 pp.199-212
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Safett evaluation of type B transport container for tritium storage vessel
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.2 pp.155-169
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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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