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  1. No Access

    Article

    Liquefaction of Latex Glove Waste for Volume Reduction

    The accumulation of dry active wastes such as latex gloves in nuclear facilities has become a serious issue because of the high cost and limited storage area for their management. In this study, the liquefacti...

    Sung-Wook Kim, Maeng-Kyo Oh, Min Ku Jeon in Korean Journal of Chemical Engineering (2024)

  2. No Access

    Article

    Investigation of the chlorination behavior of Li(Ni0.6Co0.2Mn0.2)O2 for recycling

    The chlorination behavior of Li(Ni0.6Co0.2Mn0.2)O2 (NCM(622)), a cathode material for Li-ion batteries, was investigated. Chlorination experiments were conducted in the temperature range of 400–600 ℃ for 1, 2, 4,...

    Min Ku Jeon, Sung-Wook Kim, Hyungsub Kim in Journal of the Korean Ceramic Society (2023)

  3. No Access

    Article

    Recycling of LiMO2 cathode materials by a chlorination-based Li extraction technique

    The recycling of Li(Ni1/3Co1/3Mn1/3)O2 (NCM) and LiCoO2 (LCO), which are cathode materials for Li-ion batteries, was demonstrated via a chlorination-based Li extraction technique. The recycling process follows a ...

    Min Ku Jeon, Sung-Wook Kim, Hyungsub Kim in Korean Journal of Chemical Engineering (2022)

  4. No Access

    Article

    A study on solidification of CaCO3 powder containing C-14 by using a low melting glass material

    CaCO3 powder containing C-14, which has a long half-life, is generated from the treatment process of spent activated carbons from the air cleaning system in a nuclear facility, can be decomposed into CaO and CO2 ...

    Hee-Chul Eun, Hee-Chul Yang, Hyung-Ju Kim in Journal of Radioanalytical and Nuclear Che… (2022)

  5. No Access

    Article

    Chlorination behavior of Li(Ni1/3Co1/3Mn1/3)O2

    The chlorination behavior of Li(Ni1/3Co1/3Mn1/3)O2 (NCM) was investigated as a function of the reaction temperature (400–600 °C) and time (1–8 h) for application in a chlorination-based recycling process. Structu...

    Min Ku Jeon, Sung-Wook Kim, Maengkyo Oh in Korean Journal of Chemical Engineering (2022)

  6. No Access

    Article

    A Study on Treatment of Strong Acidic Wastewater Containing a High Concentration of a Nonionic Surfactant and Ionic Materials with Radioactive Nuclides

    Radioactively contaminated metal components are generated during the operation or decommissioning of a nuclear power plant. These metals can be effectively decontaminated using a foam containing H2SO4 and Ce(IV) ...

    Hee-Chul Eun, Na-On Chang, Song-bok Lee, Min Ku Jeon in Water, Air, & Soil Pollution (2022)

  7. No Access

    Article

    Chlorination behavior of LiCoO2

    The chlorination behavior of LiCoO2 (LCO) was investigated as a function of the reaction temperature (400–600 °C) and time (1–8 h) under a 190 mL/min Ar+10 mL/min Cl2 flow. Based on the results of a structural an...

    Min Ku Jeon, Sung-Wook Kim in Korean Journal of Chemical Engineering (2022)

  8. No Access

    Article

    Recycling of Li(Ni,Co,Mn)O2 via a chlorination technique

    A new approach to recycle Li(Ni,Co,Mn)O2 (NCM, Ni : Co : Mn=1 : 1 : 1) is introduced and experimentally demonstrated. Chlorine gas was employed as a reaction agent to selectively extract Li from NCM. Through a re...

    Min Ku Jeon, Sung-Wook Kim, Hee-Chul Eun in Korean Journal of Chemical Engineering (2022)

  9. No Access

    Article

    Chlorination technique for decontamination of radioactive concrete waste contaminated by Sr

    The feasibility of the chlorination reaction as a decontamination technique for 90Sr-contaminated concrete waste was investigated via thermodynamic and experimental approaches. Thermodynamic calculations suggeste...

    Min Ku Jeon, Sung-Wook Kim, Keun-Young Lee in Journal of Radioanalytical and Nuclear Che… (2021)

  10. No Access

    Article

    Electrolytic behavior of SrCl2 and BaCl2 in LiCl molten salt during oxide reduction in pyroprocessing

    Ba and Sr elements in spent nuclear fuels are supposed to accumulate in LiCl molten salt electrolyte by forming chlorides (i.e., BaCl2, SrCl2) during oxide reduction in pyroprocessing. An electrochemical examinat...

    Sung-Wook Kim, Min Ku Jeon, Eun-Young Choi in Journal of Radioanalytical and Nuclear Che… (2019)

  11. No Access

    Article

    Chemical behavior of grey phases in LiCl molten salt for oxide reduction in pyroprocessing

    Chemical stabilities of SrZrO3, BaZrO3, and Sr0.5Ba0.5ZrO3 in LiCl molten salt were investigated to evaluate dissolution properties of Sr and Ba in grey phases of spent nuclear fuels during oxide reduction. Sr in...

    Sung-Wook Kim, Min Ku Jeon, Wooshin Park in Journal of Radioanalytical and Nuclear Che… (2018)

  12. No Access

    Article

    Thermodynamic investigation on the behavior of rare earth oxides during electrolytic reduction process

    A quantitative analysis on the behavior of rare earth (RE) oxides during the electrolytic reduction process was conducted through thermodynamic calculations. The calculation results can identify the oxide form...

    Min Ku Jeon, Sung-Wook Kim, Eun-Young Choi in Journal of Radioanalytical and Nuclear Che… (2018)

  13. No Access

    Article

    Evaluation of Pt anode stability in repeated electrochemical oxide reduction reactions for pyroprocessing

    The widespread use of Pt anodes in pyroprocessing for oxide reduction inspired us to investigate the stability of a representative Pt anode in repeated UO2 reduction experiments. The formation and subsequent exfo...

    Sang-Kwon Lee, Min Ku Jeon, Sung-Wook Kim in Journal of Radioanalytical and Nuclear Che… (2018)

  14. No Access

    Article

    Reoxidation of uranium in electrolytically reduced simulated oxide fuel during residual salt distillation

    We report that residual salt removal by high-temperature distillation causes partial reoxidation of uranium metal to uranium oxide in electrolytically reduced simulated oxide fuel. Specifically, the content of...

    Eun-Young Choi, Min Ku Jeon in Journal of Radioanalytical and Nuclear Chemistry (2017)

  15. No Access

    Article

    Quantitative calculations on the reoxidation behavior of oxide reduction system for pyroprocessing

    Reoxidation reaction of metallic uranium in the oxide reduction system for pyroprocessing of used nuclear fuels is quantitatively investigated via calculating thermodynamic equilibrium compositions. The calcul...

    Min Ku Jeon, Tae-Sic Yoo, Eun-Young Choi in Journal of Radioanalytical and Nuclear Che… (2017)

  16. No Access

    Article

    Distillation characteristics of LiCl–Li2O electrolyte for UO2 electrolytic reduction process

    As a process improvement, the distillation and recovery of the salts used in UO2 electrolytic reduction is required. The basic characteristics of the distillation of a LiCl–Li2O electrolyte containing UO2 pellets...

    Hyun Woo Kang, Eun-Young Choi, Sung-Wook Kim in Journal of Radioanalytical and Nuclear Che… (2016)

  17. No Access

    Article

    Carbon anode with repeatable use of LiCl molten salt for electrolytic reduction in pyroprocessing

    Carbon was investigated as an anode material for electrolytic reduction in pyroprocessing. UO2 was successfully reduced to U repeatedly using the carbon anode and the LiCl molten salt could be reused. While reusi...

    Sung-Wook Kim, Min Ku Jeon, Hyun Woo Kang in Journal of Radioanalytical and Nuclear Che… (2016)

  18. No Access

    Article

    Electrolytic reduction rate of porous UO2 pellets

    The electrolytic reduction rate of porous UO2 pellets in a LiCl salt was investigated for various applied charges. The degree of reduction (α) value was evaluated from the ratios of cross-sectional areas of the r...

    Min Ku Jeon, Eun-Young Choi, Sung-Wook Kim in Korean Journal of Chemical Engineering (2016)

  19. No Access

    Article

    Introduction of MKZP (Min Ku Zirconium Process) as an alternative to pyroprocessing for used nuclear fuel management

    A new process to co-recover uranium and transuranic nuclides from used nuclear fuels was introduced, which was named ‘MKZP’ (Min Ku Zirconium Process), as an alternative of widely known pyroprocessing. Instea...

    Min Ku Jeon, ** Mok Hur, Do-Hee Ahn in Journal of Radioanalytical and Nuclear Chemistry (2016)

  20. No Access

    Article

    Chlorination reaction kinetics of CsI under cladding hull waste treatment condition: a TGA study

    The reaction between cesium iodide (CsI) and chlorine gas was quantitatively investigated using a thermo-gravimetric analysis system. A comparison between calculated and experimental results on the chlorine mo...

    Min Ku Jeon, Yong Taek Choi, Chang Hwa Lee in Journal of Radioanalytical and Nuclear Che… (2016)

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