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Geochemical characteristics of a LILW repository : Ⅰ. Groundwater
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.4 pp.297-306
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Geochemical characteristics of the Gyeongju LIL.W Repository : II. Rock and Mineral
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.4 pp.307-327
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.4 pp.329-346
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.4 pp.357-368
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Reductive stripping of Np using a n-butyraldehyde from a loaded TBPphase containing Np
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.3 pp.163-170
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Evaluation of Dark Spots Formated on the High Temperature Metal FilterElements
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.3 pp.171-178
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Analysis of the Thermal and Structural Stability for the CANDU Spent Fuel Disposal Canister
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.3 pp.217-224
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Biosphere Modeling for Dose Assessment of HLW Repository: Development of ACBIO
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.2 pp.73-100
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Thermal Conductivity of Compacted Bentonite and Bentonite-Sand Mixture
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.2 pp.101-109
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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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Sorptionof Eu(III) Th(IV) on Bentonite Colloids Considering Their Precipitation an Colloid Formation
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.2 pp.129-139
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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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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.6 No.1 pp.1-9
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.1 pp.11-15
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A Study on Plasma Etching Reaction of Cobalt for Metallic Surface Decontamination
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.1 pp.17-23
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Selective Separation of Actinide(III) by a nPr-BIP/introbezene Extraction System
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.1 pp.25-33
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Conceptual Reactive Transport Modeling of Long-term Concrete Degradation and Uranium Solubility
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.1 pp.35-44
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A Study on Establishment of Buffer Zone of Radioactive Waste Repository
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.1 pp.45-54
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Longevity Issues in Swelling Clay as a Buffer Material for a HLW Repository
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.1 pp.55-63
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