| Redox potential control in molten salt systems for corrosion mitigation J Zhang, CW Forsberg, MF Simpson, S Guo, ST Lam, RO Scarlat, ... Corrosion Science 144, 44-53, 2018 | 160 | 2018 |
| Electrolytic reduction of spent nuclear oxide fuel as part of an integral process to separate and recover actinides from fission products SD Herrmann, SX Li, MF Simpson, S Phongikaroon Separation Science and Technology 41 (10), 1965-1983, 2006 | 142 | 2006 |
| Electrolytic reduction of spent light water reactor fuel bench-scale experiment results S Herrmann, S Li, M Simpson Journal of Nuclear Science and Technology 44 (3), 361-367, 2007 | 136 | 2007 |
| Kinetic analysis of isobutane/butene alkylation over ultrastable H− Y zeolite MF Simpson, J Wei, S Sundaresan Industrial & engineering chemistry research 35 (11), 3861-3873, 1996 | 115 | 1996 |
| Anodic process of electrorefining spent driver fuel in molten LiCl-KCl-UCl3/Cd system SX Li, MF Simpson Mining, Metallurgy & Exploration 22 (4), 192-198, 2005 | 102* | 2005 |
| Developments of spent nuclear fuel pyroprocessing technology at Idaho National Laboratory MF Simpson Idaho National Lab.(INL), Idaho Falls, ID (United States), 2012 | 97 | 2012 |
| Nuclear fuel, reprocessing of MF Simpson, JD Law Nuclear Energy: Selected Entries from the Encyclopedia of Sustainability …, 2012 | 90 | 2012 |
| Actinide recovery experiments with bench-scale liquid cadmium cathode in real fission product-laden molten salt SX Li, SD Herrmann, KM Goff, MF Simpson, RW Benedict Nuclear Technology 165 (2), 190-199, 2009 | 82 | 2009 |
| A description of the ceramic waste form production process from the demonstration phase of the electrometallurgical treatment of EBR-II spent fuel MF Simpson, KM Goff, SG Johnson, KJ Bateman, TJ Battisti, KL Toews, ... Nuclear Technology 134 (3), 263-277, 2001 | 76 | 2001 |
| JUPITER-II molten salt Flibe research: An update on tritium, mobilization and redox chemistry experiments DA Petti, GR Smolik, MF Simpson, JP Sharpe, RA Anderl, S Fukada, ... Fusion Engineering and Design 81 (8-14), 1439-1449, 2006 | 67 | 2006 |
| Thermal properties of LiCl-KCl molten salt for nuclear waste separation K Sridharan, T Allen, M Anderson, M Simpson Univ. of Wisconsin, Madison, WI (United States); Idaho National Lab.(INL …, 2012 | 60 | 2012 |
| A hybrid thermochemical electrolytic process for hydrogen production based on the reverse Deacon reaction MF Simpson, SD Herrmann, BD Boyle International journal of hydrogen energy 31 (9), 1241-1246, 2006 | 55 | 2006 |
| Voltammetric analysis of mixtures of molten eutectic LiCl-KCl containing LaCl3 and ThCl4 for concentration and diffusion coefficient measurement Z Wang, D Rappleye, MF Simpson Electrochimica Acta 191, 29-43, 2016 | 46 | 2016 |
| Quantitative measurement of beryllium-controlled redox of hydrogen fluoride in molten Flibe MF Simpson, GR Smolik, JP Sharpe, RA Anderl, DA Petti, Y Hatano, ... Fusion Engineering and Design 81 (1-7), 541-547, 2006 | 46 | 2006 |
| Development of computational models for the mark-IV electrorefiner—effect of uranium, plutonium, and zirconium dissolution at the fuel basket-salt interface RO Hoover, S Phongikaroon, MF Simpson, SX Li, TS Yoo Nuclear technology 171 (3), 276-284, 2010 | 45 | 2010 |
| Investigation of the effects of uranium (III)-chloride concentration on voltammetry in molten LiCl-KCl eutectic with a glass sealed tungsten electrode D Rappleye, K Teaford, MF Simpson Electrochimica Acta 219, 721-733, 2016 | 44 | 2016 |
| Development of electrorefiner waste salt disposal process for the EBR-II spent fuel treatment project MF Simpson, P Sachdev Nuclear Engineering and Technology 40 (3), 175-182, 2008 | 44 | 2008 |
| Equilibrium model for ion exchange between multivalent cations and zeolite‐A in a molten salt S Phongikaroon, MF Simpson AIChE Journal 52 (5), 1736-1743, 2006 | 43 | 2006 |
| Projected salt waste production from a commercial pyroprocessing facility MF Simpson Science and Technology of Nuclear Installations 2013 (1), 945858, 2013 | 41 | 2013 |
| Diffusion Model for Electrolytic Reduction of Uranium Oxides in a Molten LiCl-Li2O Salt S Phongikaroon, SD Herrmann, MF Simpson Nuclear Technology 174 (1), 85-93, 2011 | 41 | 2011 |
Supathorn PhongikaroonVirginia Commonwealth University在 vcu.edu 的电子邮件经过验证
