selected publications
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academic article
- Design and Control of a Fueled Molten Salt Cartridge Experiment for the Versatile Test Reactor. Nuclear Science and Engineering. 2022
- Effects of temperature, concentration, and uranium chloride mixture on zirconium electrochemical studies in LiCI-KCI eutectic salt. Journal of Nuclear Materials. 476:176-187. 2016
- Separation Of Strontium And Cesium From Ternary And Quaternary Lithium Chloride-Potassium Chloride Salts Via Melt Crystallization. Nuclear Engineering and Technology. 47:867-874. 2015
- Comparison between Numerical Simulations and Experimental Results on Copper Deposition in Rotating Cylinder Hull Cell. Electrochimica Acta. 164:218-226. 2015
- Electrochemical studies and analysis of 1-10 wt% UCl3 concentrations in molten LiCl-KCl eutectic. Journal of Nuclear Materials. 452:389-396. 2014
- Temperature effect on laser-induced breakdown spectroscopy spectra of molten and solid salts. Spectrochimica Acta Part B-atomic Spectroscopy. 97:79-85. 2014
- SEPARATION OF CsCI FROM LiCl-CsCl MOLTEN SALT BY COLD FINGER MELT CRYSTALLIZATION. Nuclear Engineering and Technology. 46:395-406. 2014
- Experimental Study of Salt Bead Dissolutions in Aqueous Solvents. Industrial and Engineering Chemistry Research. 53:13550-13556. 2014
- Separation of CsCl from a ternary CsCl-LiCl-KCl salt via a melt crystallization technique for pyroprocessing waste minimization. Chemical Engineering Science. 89:258-263. 2013
- Investigation Of Fission Product Transport Into Zeolite-A For Pyroprocessing Waste Minimization. Nuclear Technology. 181:337-348. 2013
- Measurements and analysis of oxygen bubble distributions in LiCl-KCl molten salt. Chemical Engineering Research and Design. 91:418-425. 2013
- SELECTIVE REDUCTION OF ACTIVE METAL CHLORIDES FROM MOLTEN LiCl-KCl USING LITHIUM DRAWDOWN. Nuclear Engineering and Technology. 44:767-772. 2012
- Ion exchange kinetics of fission products between molten salt and zeolite-A. Microporous and Mesoporous Materials. 152:185-189. 2012
- Diffusion Model for Electrolytic Reduction of Uranium Oxides in a Molten LiCl-Li2O Salt. Nuclear Technology. 174:85-93. 2011
- Analysis Of Equilibrium Methods For The Computational Model Of The Mark-Iv Electrorefiner. Nuclear Engineering and Technology. 43:547-556. 2011
- Uncertainty studies of real anode surface area in computational analysis for molten salt electrorefining. Journal of Nuclear Materials. 416:318-326. 2011
- Salt-Zeolite Ion-Exchange Equilibrium Studies for a Complete Set of Fission Products in Molten LiCl-KCl . Nuclear Technology. 171:306-315. 2010
- Measurement and Analysis of Gas Bubble Evolution from an Anode in Electrolytic Cells. Industrial and Engineering Chemistry Research. 49:2926-2931. 2010
- Development Of Computational Models For The Mark-Iv Electrorefiner-Effect Of Uranium, Plutonium, And Zirconium Dissolution At The Fuel Basket-Salt Interface. Nuclear Technology. 171:276-284. 2010
- A Computational Model of the Mark-IV Electrorefiner: Phase I-Fuel Basket/Salt Interface. Journal of Engineering For Gas Turbines and Power-transactions of the Asme. 131. 2009
- Computational Model Of The Mark-Iv Electrorefiner: Two-Dimensional Potential And Current Distributions. Nuclear Technology. 173:176-182.