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Effect of Steady-State Oxidation on Tensile Failure of Zircaloy Cladding
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.20 No.2 pp.161-170
DOI:https://doi.org/10.7733/jnfcwt.2022.013 Download PDF Export Citation
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.17 No.1 pp.15-28
DOI:https://doi.org/10.7733/jnfcwt.2019.17.1.15 Download PDF Export Citation
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.16 No.4 pp.411-420
DOI:https://doi.org/10.7733/jnfcwt.2018.16.4.411 Download PDF Export Citation
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Surface Analysis Study on ZIRLO Cladding Hulls Oxidized at Low Temperatures
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.12 No.3 pp.235-243
DOI:https://doi.org/10.7733/jnfcwt.2014.12.3.235 Download PDF Export Citation
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The Removal of NOx by Mediated Bectrochemical Oxidation Using
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.3 pp.121-129
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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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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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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.3 pp.179-188
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Investigation on the spectroscopic characteristics for Pu oxidation state in acid and alkali medium
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.2 pp.103-108
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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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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.3 pp.255-263
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.1 pp.1-7
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Study of morphology on the Oxidation and the Annealing of High Burn-hp UO2 Spent Fuel
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.3 No.4 pp.301-307
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Simultaneous Assay of 14C and 3H in Evaporator Bottom by Chemical Oxidation Method
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.3 No.3 pp.193-200
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Oxidation Behavior of Simudated Metallic U-Nb Alloys in Air
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.2 No.4 pp.239-244
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