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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.4 pp.283-295
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A Feasibility Study on the Polymer Solidification of Evaporator Conccentrated Wastes
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.4 pp.297-308
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Reliability Evaluation of ACP Components under a Radiation Environment
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.4 pp.309-322
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Status of the International Cooperation Project, DECOVALEX for THM Coupling Analysis
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.4 pp.323-338
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.4 pp.339-350
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A Study on Japanese Experience to Secure the Interim Storage Facility for Nuclear Spent Fuel
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.4 pp.351-357
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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.189-197
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.3 pp.199-212
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Numerical analysis of Off-Gas Flow in Hot Area of the Vitrification Plant
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.3 pp.213-220
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The Direct Decomposition of Ion-Exchange Resins by Fenton's Reagent
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.3 pp.221-227
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.3 pp.229-238
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KAERI Underground Research Tunnel(KURT)
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.3 pp.239-255
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Current Status of the Spent Filter Waste and Consideration of Its Treatment Method in KAERI
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.3 pp.257-265
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.2 pp.91-101
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Investigation on the spectroscopic characteristics for Pu oxidation state in acid and alkali medium
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.2 pp.103-108
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Possibility & Limitation of 1D Nano Scale Electron Shielder
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.2 pp.109-112
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Migration and Retardation Properties of Uranium throught a Rock Fracture in a Reducing Environment
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.2 pp.113-122
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.2 pp.123-132
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.2 pp.133-143
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