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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.7 No.4 pp.254-256
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.7 No.3 pp.133-141
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Considerations for the Successful Verification and Dismantlement of North Korea's Nuclear Program
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.7 No.3 pp.143-151
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.7 No.3 pp.153-160
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Process Analysis on the Decontamination of Internal Surface of UF6 Cylinder
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.7 No.3 pp.161-165
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Assessment of a U Product Purity from Pyroprocessing Spent EBR-II Fuel
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.7 No.3 pp.167-174
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Treatment of Spent lon-Exchange Resins from NPP by Supercritical Water Qxidation(SCW0) Process
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.7 No.3 pp.175-182
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Technical Standards on the Safety Assessment of a HLW Repository in Other Countries
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.7 No.3 pp.183-190
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.7 No.3 pp.191-193
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Thermal Release of LiCl Waste Salt from Pyroprocessing
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.7 No.2 pp.73-78
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Separation of Radionuclide from Dismantled Concrete Waste
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.7 No.2 pp.79-86
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.7 No.2 pp.87-92
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.7 No.2 pp.93-100
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Determination of Water Content in Compacted Bentonite Using a Hygrometer and Its Application
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.7 No.2 pp.101-107
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A sensitive Detection of actinide Species in Solutions Using a Capillary Cell
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.7 No.2 pp.109-114
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.7 No.2 pp.115-124
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액체음극에서의 금속 주시상 성장 억제를 위한 교반기 성능평가
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.7 No.2 pp.125-131
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.7 No.2 pp.132-134
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Evaluation of 14C Behavior Charateristic in Reactor Coolant from Korean PWR NPP’s
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.7 No.1 pp.1-7
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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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