Temperature and Concentration Dependencies of Chemical Equilibrium for Reductive Dissolution of Magnetite Using Oxalic Acid

Byung-Chul Lee, Wonzin Oh

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.19 No.2 pp.187-196

DOI:https://doi.org/10.7733/jnfcwt.2021.19.2.187 Download PDF Export Citation

Investigation on Dissolution and Removal of Adhered LiCl-KCl-UCl₃ Salt From Electrodeposited Uranium Dendrites using Deionized Water, Methanol, and Ethanol

Dimitris Payton Killinger, Supathorn Phongikaroon

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.18 No.4 pp.549-562

DOI:https://doi.org/10.7733/jnfcwt.2020.18.4.549 Download PDF Export Citation

Magnetite Dissolution by Copper Catalyzed Reductive Decontamination

Seonbyeong Kim, Sangyoon Park, Wangkyu Choi, Huijun Won, Jungsun Park, Bumkyoung Seo

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.16 No.4 pp.421-429

DOI:https://doi.org/10.7733/jnfcwt.2018.16.4.421 Download PDF Export Citation

Influence of Dissolved Ions on Geochemical Dissolution of Uranium in KURT Granite

Wan Hyoung Cho, Min Hoon Baik, Ji-Hun Ryu, Jae Kwang Lee

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.16 No.3 pp.281-290

DOI:https://doi.org/10.7733/jnfcwt.2018.16.3.281 Download PDF Export Citation

Removal of Uranium by an Alkalization and an Acidification from the Thermal Decomposed Solid Waste of Uranium-bearing Sludge

Eil-Hee Lee^*, Han-Beom Yang, Keun-Young Lee, Kwang-Wook Kim, Dong-Yong Chung, Jei-Kwon Moon

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.11 No.2 pp.85-93

DOI:https://doi.org/10.7733/jkrws.2013.11.2.85 Download PDF Export Citation

Studies on the Electrochemical Dissolution for the Treatment of 10 g-Scale Zircaloy-4 Cladding Hull Wastes in LiCl-KCl Molten Salts

Chang Hwa Lee^*, You Lee Lee, Min Ku Jeon, Kweon Ho Kang

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.4 pp.273-280

DOI:https://doi.org/10.7733/jkrws.2012.10.4.273 Download PDF Export Citation

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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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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The Characteristics of an Oxidative Dissolution of Simulated fission Product Oxides in (NH4)2CO3 Containing H2O2

이일희, 임재관, 정동용, 양한범, 김광욱

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.7 No.2 pp.93-100

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The Direct Dissolution of Ion-Exchange Resin by Fenton's Reagent

Kil-Jeong Kim, Jong-Sik Shon, Woo-Seog Ryu

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.1 pp.85-90

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Alternative Method for the Treatment of Chemical Wastes Containing Uranium

Kil-Jeong Kim, Jong Sik Shon, Kwon-Pyo Hong

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.2 pp.179-186

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Determination of Forward Dissolution Rate of Glass by a Single-Pass Flow-Through Test

Seung Soo Kim, Kwan Sik Chun, Jong-won Choi, Sung Ki Kim, Pil-Soo Hahn

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.3 No.4 pp.335-340

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