Analysis of Siting Criteria of Overseas Geological Repository (I): Geology

Haeryong Jung^1*, Hyun-Joo Kim, Min Jung Kim, Jae-Yeol Cheong, Yi-Yeong Jeong and Eun Yong Lee

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.4 pp.305-311

DOI:https://doi.org/10.7733/jkrws.2012.10.4.305 Download PDF Export Citation

Potential repository domain for A-KRS at KURT facility site

Kyung-Su Kim¹⁾, Kyung-Woo Park, Geon-Young Kim, Heui-Joo Choi

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.3 pp.151-159

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A Deterministic Safety Assessment of a Pyro-processed Waste Repository

Youn-Myoung LEE¹⁾, Jongtae JEONG , Jongwon CHOI

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.3 pp.171-188

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Geochemical Characterization of Rock-Water Interaction in Groundwater at the KURT Site

Ji-Hun Ryu¹⁾, Jang-Soon Kwon,Geon-Young Kim ,Yong-Kwon Koh

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.3 pp.189-197

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Hydrogeological Properties of Geological Elements in Geological Model around KURT

Kyung Woo Park ¹⁾, Kyung Su Kim,Yong Kwon Koh ,Jong Won Choi

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.3 pp.199-208

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Removal of Uranium from U-bearing Lime-Precipitate using dissolution and precipitation methods

Eil-Hee Lee, Lee, Dong-Yong Chung, Kwang-Wook Kim, Kune-Woo Lee, Jei-Kwon Moon

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.2 pp.77-85

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An Electrochemical Reduction of TiO₂ Pellet in Molten Calcium Chloride

Sang Mun Jeong, Hyun-Sub Ji, Hyo Yeol Ryu, Ha Myung Jeong, Kwang Ho Jeong

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.2 pp.97-104

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An Evaluation on the Radiation Shielding of the Radwaste Drum Assay Facility

Young-Yong Ji, Kyung-Kil Kwak, Dae-Seok Hong and Jong-Sik Shon

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.2 pp.117-123

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A study on dehydration of rare earth chloride hydrate

Tae-Kyo Lee, Yong-Zun Cho*, Hee-Chul Eun*, Sung-Mo Son*, In-Tae Kim* and Taek-Sung Hwang

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.2 pp.125-132

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Evaluation of Low or High Permeability of Fractured Rock using Well Head Losses from Step-Drawdown Tests

Byung-Woo Kim, Hyoung-Soo Kim*, Geon-Young Kim, Yong-Kwon Koh

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.1 pp.1-11

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Evaluation of Microstructural and Mechanical Property of Medium-sized HT9 Cladding Forged Material for Sodium-cooled Fast Reactor

Jun-Hwan Kim, Kang-Soo Lee, Sung-Ho Kim, Chan-Bock Lee

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.1 pp.21-26

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The State-of-the Art of the Borehole Disposal Concept for High Level Radioactive Waste

Sung-Hoon Ji, Yong-Kwon Koh, Jong-Won Choi

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.1 pp.55-62

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Study on Basic Requirements of Geoscientific Area for the Deep Geological Repository of Spent Nuclear Fuel in Korea

Dae-Seok Bae, Yong-Kwon Koh, Ju-wan Park*, Jin-baek Park* and Jong-soon Song**

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.1 pp.63-75

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Safety Review of Severe Accident Senario for Wet Spent Fuel Storage Facility

Tae-Myung Shin

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.4 pp.231-236

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Patent Analysis for Pyroprocessing of Spent Nuclear Fuels

Jae-Hyung Yoo, Jung-Kuk Kim, Han-Soo Lee, In-Seok Seo, Eun-ka Kim

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.4 pp.247-258

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The Removal of NO_x by Mediated Bectrochemical Oxidation Using

Min-Woo Lee,So-Jin Park,Kune-Woo Lee,Wang-Kyu Choi

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.3 pp.121-129

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Evaluation of Na₂CO₃-H₂O₂ Carbonate Solution Stability

EiI-Hee Lee,Jae-Gwan Lim,Dong-Yong Chung,Han-Beum Yang,Kwang-Wook Kim

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.3 pp.131-139

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Detennination of ¹²⁹I in simulated radioactive wastes using distiIlation technique

Ke Chon Choi,Byung Cheol Song,Sun Ho Han,Yong Joon Park,Kyuseok Song

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.3 pp.141-148

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Groundwater Aow and Tritium Transport Modeling at Kori Nuclear Power Plant 1 Site

Wook Sohn,Soon-Hwan Sohn,Chul-Min Chon,Kue-Yong Kim

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.3 pp.149-159

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Alternative Concept to Enhance the Disposal Emciency for CANDU Spent Fuel Disposal System

Jong-Youl LEE,Dong-Geun CHO,Dong-Hak KOOK,Min-Soo LEE,Heui-Joo CHOI

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.3 pp.169-179

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