Development of a Simplified Source Term Estimation Model for a Spent Fuel from Westinghouse-type Reactors

조동건, 국동학, 최희주, 최종원

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.3 pp.239-245

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Crevice Corrosion Evaluation of Cold Sprayed Copper

이민수, 최희주

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.3 pp.247-260

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Study on the Synthesis Method of Simulated CRUD for Chemical Decontamination in NPPs

Duk-Won Kang, Jin-Kil Kim, Kyeong-Sook Kim

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.2 pp.91-97

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A Study on Wasteform Properties of Spent Salt Treated with Zeolite and SAP

Hwan-young Kim, Hwan-Seo Park, Kweon-Ho Kang, Byung-gil Ahn, In-Tae Kim

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.2 pp.99-105

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A Study of Adsorption Behaviour of Humic Acid and Americium on the Kaolinite

Myung Ho Lee, Kyu Whan Lee, Kyung Kyun Park, Euo Chang Jung, Kyuseok Song, Hyun Sang Shin

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.2 pp.107-113

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Precipitation behaviors of Cs and Re(/Tc) by NaTPB and TPPCl from a simulated fission products-(Na2CO3-NaHCO3)-H2O2 solution

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

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.2 pp.115-122

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Deposition Velocity of Iodine Vapor (I2) for Radish Plants and Its Root- Translocation Factor : Results of Experimental Exposures

Yong-Ho Choi, Kwang-Muk Lim, In Jun, Doo-Won Park, Dong-Kwon Keum

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.2 pp.151-158

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Groundwater Flow Modeling in a Block-Scale Fractured Rocks considering the Fractured Zones

Nak-Youl Ko, Sung-Hoon Ji, Yong-Kwon Koh, Jon-Won Choi

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.2 pp.159-166

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Some notes on the Timing of Geological Disposal of CANDU Spent Fuels

Heui-Joo Choi, Donghak Kook, Jongwon Choi

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.2 pp.167-172

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Computational Analysis for a Molten-salt 티ectrowinner with Liquid Cadmium Cathode

김광락, 정용주, 백승우, 김지용, 권상운, 윤달성, 김시형, 심준보, 김정국, 안도희, 이한수

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.1 pp.1-7

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Development of Liquid Cadmium Cathode Structure for the Inhibition of Uranium Dendrite Growth

백승우, 윤달성, 김시형, 심준보, 안도희

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.1 pp.9-17

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A Chemical Reaction Calculation and a Semi-Empirical Model for the Dynamic Simulation of an Electrolytic Reduction of Spent Oxide Fuels

박병홍, 허진목, 이한수

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.1 pp.19-32

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Corrosion Behavior of Y2O3 Coating in an Electrolytic Reduction Process

조수행, 홍순석, 강대승, 정명수, 박병홍, 허진목, 이한수

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.1 pp.33-39

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Study of the Formation of Eutectic Melt of Uranium and Thermal Analysis for the Salt Distillation of Uranium Deposits

박성빈, 조동욱, 황성찬, 강영호, 박기민, 전완기, 김정국, 이한수

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.1 pp.41-48

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Immobilization of Radioactive Rare Earth oxide Waste by Solid Phase Sintering

안병길, 박환서, 김환영, 이한수, 김인태

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.1 pp.49-56

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Reuse Technology of LiCl Salt Waste Generated from Electrolytic Reduction Process of Spent Oxide Fuel

조용준, 정진석, 이한수, 김인태

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.1 pp.57-63

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Fundamental Study on a Distillation Separation of a LiCl-KCl Eutectic Salt from Rare Earth Precipitates

양희철, 은희철, 김인태

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.1 pp.65-70

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The Development of U-recovery by Continuous Electrorefining

김정국, 박성빈, 황성찬, 강영호, 이성재, 이한수

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.1 pp.71-76

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Development of an Oxide Reduction Process for the Treatment of PWR Spent Fuel

허진목, 홍순석, 정상문, 이한수

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.1 pp.77-84

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Construction of the Geological Model around KURT area based on the surface investigations

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

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.7 No.4 pp.191-205

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