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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.1 pp.41-48
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Immobilization of Radioactive Rare Earth oxide Waste by Solid Phase Sintering
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.1 pp.49-56
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.1 pp.57-63
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.1 pp.65-70
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The Development of U-recovery by Continuous Electrorefining
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.1 pp.71-76
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Development of an Oxide Reduction Process for the Treatment of PWR Spent Fuel
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.1 pp.77-84
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Construction of the Geological Model around KURT area based on the surface investigations
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.7 No.4 pp.191-205
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Development of CANDU Spent Fuel Disposal Concepts for the Improvement of Disposal Efficiency
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.7 No.4 pp.229-236
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Scaleup of Electrolytic Reactors in Pyroprocessing
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.7 No.4 pp.237-242
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Research Status on the Radionuclide and Colloid Migration in Underground Research Facilities
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.7 No.4 pp.243-253
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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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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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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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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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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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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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