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Heat Transfer Analysis around Transport Cask under Transport Hood
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.3 pp.161-167
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Alternative Concept to Enhance the Disposal Emciency for CANDU Spent Fuel Disposal System
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.3 pp.169-179
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Criticality Uncertainty Analysis of Spent Fuel Transport Cask applying Bmnup Credit
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.3 pp.191-198
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The Test for Verifying a Tip-Over Analysis of a Dry Storage Cask
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.3 pp.245-253
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National Policy and Status on Management of Spent Nuclear Fuel
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.3 pp.285-299
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.3 pp.301-309
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Current Status and Projection of Spent Nuclear Fuel for Geological Disposal System Design
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.1 pp.87-93
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Effect of engineered barriers on the leach rate of cesium from spent PWR fuel
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.3 No.4 pp.329-333
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