Conceptual Designs and Evaluation of the Treatment Process of Square and Cylindrical Concrete Re-Package Drums

Young Hwan Hwang, Sunghoon Hong, Seong-Sik Shin, Seokju Hwang, Jung-Kwon Son, Cheon-Woo Kim, Changgyu Kim, Kwang Soo Park, Taeseob Lim, Donghun Park

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.22 No.2 pp.227-235

DOI:https://doi.org/10.7733/jnfcwt.2024.021 Download PDF Export Citation

Development of Chemical and Biological Decontamination Technology for Radioactive Liquid Wastes and Feasibility Study for Application to Liquid Waste Management System in APR1400

YoungJu Son, Seung Yeop Lee, JaeYeon Jung, Chang-Lak Kim

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.17 No.1 pp.59-73

DOI:https://doi.org/10.7733/jnfcwt.2019.17.1.59 Download PDF Export Citation

Method for Determining Transportation Grade for HIC Containing Spent Resin Using Radioactivity Analysis

Taewook Kim, Kiseop Choi, Kidoo Kang, Jonghyun Ha

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.1 pp.11-15

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Simultaneous Separation and Determination of 14C and 3H in Spent Resins from PWR Nuclear Power Plants

Soon-Dal Park, Jung-Suck Kim, Jong-Goo Kim, Sun-Ho Han, Kwang-Yong Jee

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.3 pp.179-188

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Gasification Characteristics to 14CO2 of 14C Radionuclide Desorbed from Spent Resin by Phosphate Solutions

Ho-Yeon Yang, Jang-Sik Won, Young-Ku Choi, Geun-IL Park, In-Tae Kim, Kwang-Wook Kim, Kee Chan Song, Hwan Seo Park

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.4 pp.311-320

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Ion Adsorption Characteristics of IRN-150 Mixed Resin and Removal Behavior of 14C Radionuclide from Spent Resin by Stripping Solutions

Ho-Yeon Yang, Jang-Sik Won, Young-Ku Choi, Geun IL Park, In-Tae Kim, Kwang-Wook Kim, Kee Chan Song, Hwan Seo Park

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.4 pp.373-384

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Structural Evaluation on HIC Transport Packaging under Accident Conditions

Sung-Hwan Chung, Duck-Hoi Kim, Jin-Se Jung, Ke-Hyung Yang, Heung-Young Lee

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.3 No.3 pp.231-236

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