Prediction Model for Saturated Hydraulic Conductivity of Bentonite Buffer Materials for an Engineered-Barrier System in a High-Level Radioactive Waste Repository

Gi-Jun Lee, Seok Yoon, Bong-Ju Kim

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.21 No.2 pp.225-234

DOI:https://doi.org/10.7733/jnfcwt.2023.017 Download PDF Export Citation

A Prediction of Thermal Expansion Coefficient for Compacted Bentonite Buffer Materials

Seok Yoon, Geon-Young Kim, Min-Hoon Baik

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.16 No.3 pp.339-346

DOI:https://doi.org/10.7733/jnfcwt.2018.16.3.339 Download PDF Export Citation

Temperature Effect on the Swelling Pressure of a Domestic Compacted Bentonite Buffer

이지현, 이민수, 최희주, 최종원

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.3 pp.207-213

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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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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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