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Overseas Review on the In-situ Demonstration of EBS for IN-DEBS Development

Minsoo Lee, Heui-Joo Choi, Jong-Youl Lee, Changsoo Lee, Jae-Owan Lee, Inyoung Kim

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.12 No.2 pp.107-119

DOI:https://doi.org/10.7733/jnfcwt.2014.12.2.107 Download PDF Export Citation
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The Method for Evaluating Unsaturated Hydraulic Conductivity of the Bentonite-buffer Using Relative Humidity

Hang-Bok Lee, Jin-Seop Kim, Young-Chul Choi, Heui-Joo Choi, Kyungsu Kim

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.12 No.1 pp.69-77

DOI:https://doi.org/10.7733/jnfcwt.2014.12.1.69 Download PDF Export Citation
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An Analysis of the Water Saturation Processes in the Engineered Barrier of a High Level Radioactive Waste Disposal System

Jeong Hwa Park, Jae-Owan Lee, Sangki Kwon

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.1 pp.23-32

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Effect of a Hydrothermal Reaction on the Expandibility, Layer Charge, and CEC of Smectite Clay

Jae Wwan Lee, Won Jin Cho

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.3 pp.173-179

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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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Development of CANDU Spent Fuel Disposal Concepts for the Improvement of Disposal Efficiency

Jong-Youl Lee, Dong-Geun Cho, Dong-Hak Kook, Min-Soo Lee, Heui-Joo Choi, Yang Lee

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.7 No.4 pp.229-236

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Determination of Water Content in Compacted Bentonite Using a Hygrometer and Its Application

이재완, 조원진

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.7 No.2 pp.101-107

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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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A Study on Establishment of Buffer Zone of Radioactive Waste Repository

Jeong-Hyoung Yoon, Joo Wan Park, Min-Su Ju, Chang-Lak Kim, Jin Baek Park

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.1 pp.45-54

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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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Structural Design Requirements and Safety Evaluation Criteria of the Spent Nuclear Fuel Disposal Canister for Deep Geological Deposition

Young-Joo Kwon, Jong-Won Choi

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.3 pp.229-238

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Analysis of the Disposal Tunnel and Disposal Pit Spacing for the Spent Fuel Repository Layout

Jong-Youl Lee, Yang Lee, Heui-Joo Choi, Jong-won Choi

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.4 pp.393-400

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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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