Michael Simpson
Michael Simpson
Professor of Materials Science and Engineering, University of Utah
Verified email at - Homepage
Cited by
Cited by
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
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
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
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
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
Nuclear fuel reprocessing
MF Simpson, JD Law
Nuclear Energy, 187-204, 2018
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
Developments of spent nuclear fuel pyroprocessing technology at Idaho National Laboratory
MF Simpson
Idaho National Lab.(INL), Idaho Falls, ID (United States), 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
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
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
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
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
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
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
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
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
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
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
Modeling the Pyrochemical Reduction of Spent UO2 Fuel in a Pilot-Scale Reactor
MF Simpson, SD Herrmann
Nuclear technology 162 (2), 179-183, 2008
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