Feasibility Study on Aluminum Under Laser Ablation for Corrosion Resistance in Molten Salt

Peggy T. Milota, Supathorn Phongikaroon

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.22 No.1 pp.67-80

DOI:https://doi.org/10.7733/jnfcwt.2024.001 Download PDF Export Citation

Assessing the Potential of Small Modular Reactors (SMRs) in Spent Nuclear Fuel Management: A Review of the Generation IV Reactor Progress

Hong June Park, Sun Young Chang, Kyung Su Kim, Pascal Claude Leverd, Joo Hyun Moon, Jong-Il Yun

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.21 No.4 pp.571-576

DOI:https://doi.org/10.7733/jnfcwt.2023.037 Download PDF Export Citation

Molten Salt-Based Carbon-Neutral Critical Metal Smelting Process From Oxide Feedstocks

Wan-Bae Kim, Woo-Seok Choi, Gyu-Seok Lim, Vladislav E. Ri, Soo-Haeng Cho, Suk-Cheol Kwon, Hayk Nersisyan, Jong-Hyeon Lee

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.21 No.1 pp.9-22

DOI:https://doi.org/10.7733/jnfcwt.2023.005 Download PDF Export Citation

Phase Behavior of the Ternary NaCl-PuCl₃-Pu Molten Salt

Toni Karlsson, Cynthia Adkins, Ruchi Gakhar, James Newman, Steven Monk, Stephen Warmann

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.21 No.1 pp.55-64

DOI:https://doi.org/10.7733/jnfcwt.2023.011 Download PDF Export Citation

Experimental Observations for Anode Optimization of Oxide Reduction Equipment

David Horvath, James King, Robert Hoover, Steve Warmann, Ken Marsden, Dalsung Yoon, Steven Herrmann

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.20 No.4 pp.383-398

DOI:https://doi.org/10.7733/jnfcwt.2022.040 Download PDF Export Citation

Review, Assessment, and Learning Lesson on How to Design a Spectroelectrochemical Experiment for the Molten Salt System

Dimitris Killinger, Supathorn Phongikaroon

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.20 No.2 pp.209-229

DOI:https://doi.org/10.7733/jnfcwt.2022.017 Download PDF Export Citation

Electrochemical Behaviors of Bi³⁺ Ions on Inert Tungsten or on Liquid Bi Pool in the Molten LiCl-KCl Eutectic

Beom Kyu Kim, Byung Gi Park

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.20 No.1 pp.33-41

DOI:https://doi.org/10.7733/jnfcwt.2022.004 Download PDF Export Citation

Corrosion of Containment Alloys in Molten Salt Reactors and the Prospect of Online Monitoring

Thomas Hartmann, Patricia Paviet

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.20 No.1 pp.43-63

DOI:https://doi.org/10.7733/jnfcwt.2022.005 Download PDF Export Citation

Recycling of Li₂ZrO₃ as LiCl and ZrO₂ via a Chlorination Technique

Min Ku Jeon, Sung-Wook Kim, Keun-Young Lee, Eun-Young Choi

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.19 No.2 pp.271-278

DOI:https://doi.org/10.7733/jnfcwt.2021.19.2.271 Download PDF Export Citation

Interaction of Rare Earth Chloride Salts to Alumina and Mullite in LiCl-KCl at 773 K

D. Horvath, S. Warmann, J. King, K. Marsden, R. Hoover

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.18 No.3 pp.337-346

DOI:https://doi.org/10.7733/jnfcwt.2020.18.3.337 Download PDF Export Citation

Electrochemical Impedance Spectroscopy and Cyclic Voltammetry Methods for Monitoring SmCl₃ Concentration in Molten Eutectic LiCl-KCl

Michael R. Shaltry, Kerry N. Allahar, Darryl P. Butt, Michael F. Simpson, Supathorn Phongikaroon

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.18 No.1 pp.1-18

DOI:https://doi.org/10.7733/jnfcwt.2020.18.1.1 Download PDF Export Citation

Effect of AlF₃ on Zr Electrorefining Process in Chloride-Fluoride Mixed Salts for the Treatment of Cladding Hull Wastes

Chang Hwa Lee, Deok Yoon Kang, Sung-Jai Lee, Jong-Hyeon Lee

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.17 No.2 pp.127-137

DOI:https://doi.org/10.7733/jnfcwt.2019.17.2.127 Download PDF Export Citation

A Study on the Droplet Formation of Liquid Metal in Water-Mercury System as a Surrogate of Molten Salt-Liquid Metal System at Room Temperature

Yong-il Kim, Byung Gi Park

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.16 No.2 pp.165-172

DOI:https://doi.org/10.7733/jnfcwt.2018.16.2.165 Download PDF Export Citation

Density of Molten Salt Mixtures of Eutectic LiCl-KCl Containing UCl3, CeCl3, or LaCl3

C. Zhang, M. F. Simpson

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.15 No.2 pp.117-124

DOI:https://doi.org/10.7733/jnfcwt.2017.15.2.117 Download PDF Export Citation

Electrochemical Reduction of Plutonium Oxide in Molten CaCl2-CaO

Arfon H. Jones, Robert Watson, Tim Paget, Rob Campbell-Kelly, Tom Caldwell, Derek J. Fray

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.13 No.Special pp.1-5

DOI:https://doi.org/10.7733/jnfcwt.2015.13.S.1 Download PDF Export Citation

Pyroprocess Experiments at ENEA Laboratories

Giorgio DE ANGELIS, Elio BAICCHI, Mauro CAPONE, Carlo FEDELI, Massimo SEPIELLI, Giuliano TIRANTI, Mirko DA ROS, Francesca GIACOBBO, Marco GIOLA, Elena MACERATA, Mario MARIANI

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.13 No.Special pp.19-27

DOI:https://doi.org/10.7733/jnfcwt.2015.13.S.19 Download PDF Export Citation

Loss of Li₂O Caused by ZrO₂ During the Electrochemical Reduction of ZrO₂ in Li₂O-LiCl Molten Salt

Wooshin Park^*, Jin-Mok Hur, Eun-Young Choi, Jong-Kook Kim

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.4 pp.229-236

DOI:https://doi.org/10.7733/jkrws.2012.10.4.229 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

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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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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