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Nuclear Fuel Cycle Analysis Technology to Develop Advanced Nuclear Fuel Cycle
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.4 pp.219-230
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Sensitivity Analysis of Depletion Parameters for Heat Load Evaluation of PWR Spent Fuel Storage Pool
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.4 pp.237-245
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.2 pp.73-80
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Multilateral Approaches to the Back-end of the Nuclear Fuel Cycle: Challenges and Possibilities
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.4 pp.269-277
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Assessment of Potential Impacts of the Proposals for Multilateralization of Nuclear Fuel Cycle
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.4 pp.339-346
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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.239-245
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The Public Sphere and the Conflict-Structure in Spent Nuclear Fuel Management
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.7 No.1 pp.49-62
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Canadian Public and Stakeholder Engagement Approach to a Spent Nuclear Fuel Management
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.3 pp.179-187
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Reference Spent Nuclear Fuel for Pyroprocessing Facility Design
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.3 pp.225-232
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A Conceptual Design Study for a Spent Fuel Pyroprocessing Facility of a Demonstration Scale
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.3 pp.233-244
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Thermal Analysis of a Retrievable CANDU Spent Fuel Disposal Tunnel
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.2 pp.119-128
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Current Status and Characterization of CANDU Spent Fuel for Geological Disposal System Design
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.2 pp.155-162
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.4 pp.283-295
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.3 pp.229-238
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The Test for Verifying a Tip-Over Analysis of a Dry Storage Cask
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.3 pp.245-253
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National Policy and Status on Management of Spent Nuclear Fuel
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.3 pp.285-299
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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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Current Status and Projection of Spent Nuclear Fuel for Geological Disposal System Design
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.1 pp.87-93
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.3 No.3 pp.167-176
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