Michael Simpson
Michael Simpson
Professor of Materials Science and Engineering, University of Utah
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TítuloCitado porAño
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
1022006
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
961996
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
802007
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
602005
Nuclear fuel, reprocessing of
MF Simpson, JD Law
Encyclopedia of Sustainability Science and Technology, 7142-7156, 2012
552012
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
542001
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
532009
Developments of spent nuclear fuel pyroprocessing technology at Idaho National Laboratory
MF Simpson
Idaho National Laboratory (INL), 2012
482012
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
472006
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
382006
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 Laboratory …, 2012
322012
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
322006
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
302010
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
292008
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
292006
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
262016
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
252011
Modeling the Pyrochemical Reduction of Spent UO2 Fuel in a Pilot-Scale Reactor
MF Simpson, SD Herrmann
Nuclear Technology 162 (2), 179-183, 2008
242008
A computational model of the Mark-IV electrorefiner: phase I—fuel basket/salt interface
R Hoover, S Phongikaroon, S Li, M Simpson, TS Yoo
Journal of Engineering for Gas Turbines and Power 131 (5), 054503, 2009
222009
Two-site equilibrium model for ion exchange between monovalent cations and zeolite-A in a molten salt
MF Simpson, MLD Gougar
Industrial & engineering chemistry research 42 (18), 4208-4212, 2003
222003
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Artículos 1–20