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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.3 pp.227-234
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Determination of Forward Dissolution Rate of Glass by a Single-Pass Flow-Through Test
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.3 No.4 pp.335-340
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Identification of Uranium Species Released from the Waste Glass in Contact with Bentonite
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.3 No.3 pp.177-181
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