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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.18 No.2(E) pp.275-289
DOI:https://doi.org/10.7733/jnfcwt.2020.18.2(E).275 Download PDF Export Citation
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A Study on Radiation Safety Evaluation for Spent Fuel Transportation Cask
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.17 No.4 pp.375-387
DOI:https://doi.org/10.7733/jnfcwt.2019.17.4.375 Download PDF Export Citation
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.17 No.2 pp.167-181
DOI:https://doi.org/10.7733/jnfcwt.2019.17.2.167 Download PDF Export Citation
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Establishment and Application of Nuclear Criticality Safety Validation Methodology
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.16 No.3 pp.315-330
DOI:https://doi.org/10.7733/jnfcwt.2018.16.3.315 Download PDF Export Citation
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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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Safety Evaluation of Radioactive Material Transport Package under Stacking Test Condition
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.1 pp.37-43
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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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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.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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Structural Evaluation on HIC Transport Packaging under Accident Conditions
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.3 No.3 pp.231-236
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