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A Finite Element Modeling for the Puncture Drop Test of a Cask with the Failure of Impact Limiter
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.7 No.1 pp.9-16
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Analysis of 99Tc and Its Activity Level in the Korean Soil
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.7 No.1 pp.25-31
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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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Roles and Importance of Microbes in the Radioactive Waste Disposal
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.7 No.1 pp.63-72
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.4 pp.257-263
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Numerical simulation of groundwater flow in LILW Repository site: I. Groundwater flow modeling
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.4 pp.265-282
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.4 pp.283-296
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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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