Analysis of the Thermal and Structural Stability for the CANDU Spent Fuel Disposal Canister

이종열, 조동건, 김성기, 최희주, 이양

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.3 pp.217-224

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Thermal Conductivity of Compacted Bentonite and Bentonite-Sand Mixture

Won-Jin Cho, Jae-Owan Lee, Sangki Kwon

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.2 pp.101-109

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Longevity Issues in Swelling Clay as a Buffer Material for a HLW Repository

Jae Owan Lee, Won Jin Cho

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.1 pp.55-63

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Analysis of the Spent Fuel Cooling Time for a Deep Geological Disposal

Jong-Youl Lee, Dong-Geun Cho, Heui-Joo Choi, Jong-Won Choi, Yang Lee

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.1 pp.65-72

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An Experimental Study on the Sorption of Uranium(VI) onto a Bentonite Colloid

Min-Hoon Baik, Won Jin Cho

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.3 pp.235-243

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Engineering-scale Validation Test for the T-H-M Behaviors of a HLW Disposal System

Jae Owan Lee, Jeong Hwa Park, Won Jin Cho

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.2 pp.197-207

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An Experimental Study on the Erosion of a Compacted Calcium Bentonite Block

Min-Hoon Baik, Won Jin Cho

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.3 No.4 pp.341-348

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Hydraulic-Thermal-Mechanical Properties and Radionuclide Release-Retarding Capacity of Kyungju Bentonite

Jae-Owan Lee, Won-Jin Cho, Pil-Soo Hahn

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.2 No.2 pp.87-96

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