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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.2 pp.133-143
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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.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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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.3 No.2 pp.77-84
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.3 No.2 pp.105-112
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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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Semi-Continuous Electrowinning of LiCl-Li2O Molten Salt
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.2 No.3 pp.211-217
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A Study on the Electrolytic Reduction Mechanism of Uranium Oxide in a LiCl-Li2O Molten Salt
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.1 No.1 pp.25-39
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