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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.15 No.1 pp.83-90
DOI:https://doi.org/10.7733/jnfcwt.2017.15.1.83 Download PDF Export Citation
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Study on the Code System for the Off-Site Consequences Assessment of Severe Nuclear Accident
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.14 No.4 pp.423-434
DOI:https://doi.org/10.7733/jnfcwt.2016.14.4.423 Download PDF Export Citation
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Development of Multi-Purpose Containers for Managing LLW/VLLW from D&D
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.14 No.2 pp.157-168
DOI:https://doi.org/10.7733/jnfcwt.2016.14.2.157 Download PDF Export Citation
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TiN Anode for Electrolytic Reduction of UO2 in Pyroprocessing
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.13 No.3 pp.229-233
DOI:https://doi.org/10.7733/jnfcwt.2015.13.3.229 Download PDF Export Citation
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.13 No.1 pp.21-34
DOI:https://doi.org/10.7733/jnfcwt.2015.13.1.21 Download PDF Export Citation
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Policy Initiatives to Establish a National Nuclear Education & Training System
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.12 No.4 pp.253-265
DOI:https://doi.org/10.7733/jnfcwt.2014.12.4.253 Download PDF Export Citation
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Feasibility about the Direct Measurement of 226Ra Using the Gamma-Ray Spectrometry
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.12 No.2 pp.97-105
DOI:https://doi.org/10.7733/jnfcwt.2014.12.2.97 Download PDF Export Citation
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Loss of Li₂O Caused by ZrO₂ During the Electrochemical Reduction of ZrO₂ in Li₂O-LiCl Molten Salt
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.4 pp.229-236
DOI:https://doi.org/10.7733/jkrws.2012.10.4.229 Download PDF Export Citation
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.1 pp.27-36
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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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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.1 pp.45-53
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.4 pp.207-217
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Detennination of 129I in simulated radioactive wastes using distiIlation technique
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.3 pp.141-148
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A Study on Construction and Application of Nuclear Grade ESF ACS Simulator
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.4 pp.319-327
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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.2 pp.151-158
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Thermal behavior of PrCl3 in an oxidizing condition
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.7 No.4 pp.207-212
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Evaluation of 14C Behavior Charateristic in Reactor Coolant from Korean PWR NPP’s
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.7 No.1 pp.1-7
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Stabilization of Radioactive Molten Salt Waste by Using Silica-Based Inorganic Material
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.3 pp.171-177
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.3 pp.199-212
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