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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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Thermal behavior of PrCl3 in an oxidizing condition
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.7 No.4 pp.207-212
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.3 No.2 pp.85-93
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.3 No.2 pp.105-112
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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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