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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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Correlation of l37Cs/60Co Activity Ratio in Radwaste with Primary coolant
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.1 pp.9-17
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.1 pp.29-37
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.1 pp.39-52
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Cesium Release Behavior during the Themal Treatment of High Burn-up Spent PWR Fuel
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.1 pp.53-64
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Measurement of the Gap and Grain Boundary Inventories of Cs, Sr in and I in Domestic Used PWR Fuels
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.1 pp.79-84
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The Direct Dissolution of Ion-Exchange Resin by Fenton's Reagent
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.1 pp.85-90
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.1 pp.91-99
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.4 pp.311-320
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Rock Weathering and Geochemical Characteristics in the KURT
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.4 pp.321-328
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Spatial Distributions of 3H and 14C in the Shielding Concrete of KRR-2
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.4 pp.329-334
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Development of a Simulation Program for the Li-Reduction Process of PWR Spent Fuel
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.4 pp.335-344
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Measurement of the Radiolysis Gases Generated in Several Waste Forms by External Irradiation
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.4 pp.345-352
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A Mathematical Model to Evaluate the Radiological Risks for the Reuse of Decommissioning Site
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.4 pp.353-363
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.4 pp.373-384
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.4 pp.385-391
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Analysis of the Disposal Tunnel and Disposal Pit Spacing for the Spent Fuel Repository Layout
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.4 pp.393-400
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Consideration of Regulatory Systems for Decommissioning of Nuclear Power Plants
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.4 pp.401-409
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A Study on the Wigner Energy Release Characteristics of Irradiated Graphite of KRR-2
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.3 pp.209-216
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.3 pp.217-226
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