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Michael J. Carrott

Observed names: Carrott, Michael, Michael Carrott, Michael J Carrott
OpenAlex ID: A5109345843
Recent Developments in the Purex Process for Nuclear Fuel Reprocessing: Complexant Based Stripping for Uranium/Plutonium Separation
2005 · J. Eddie Birkett, Michael J. Carrott, et al. · CHIMIA International Journal for Chemistry · 117
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Development of a New Flowsheet for Co-Separating the Transuranic Actinides: The “EURO-GANEX” Process
2014 · Michael Carrott, Katie Bell, et al. · Solvent Extraction and Ion Exchange · 103
Distribution of plutonium, americium and interfering fission products between nitric acid and a mixed organic phase of TODGA and DMDOHEMA in kerosene, and implications for the design of the “EURO-GANEX” process
2015 · Michael Carrott, Andreas Geist, et al. · Hydrometallurgy · 89
Homogenous recycling of transuranium elements from irradiated fast reactor fuel by the EURO-GANEX solvent extraction process
2019 · Rikard Malmbeck, Daniel Magnusson, et al. · Radiochimica Acta · 78
An overview of solvent extraction processes developed in Europe for advanced nuclear fuel recycling, Part 2 — homogeneous recycling
2021 · Thea Lyseid Authen, Jean-Marc Adnet, et al. · Separation Science and Technology · 70
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Process intensification of element extraction using centrifugal contactors in the nuclear fuel cycle
2022 · Alastair Baker, Alex Fells, et al. · Chemical Society Reviews · 63
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Americium and Plutonium Purification by Extraction (the AMPPEX process): Development of a new method to separate 241Am from aged plutonium dioxide for use in space power systems
2018 · Jamie Brown, Catherine Campbell, et al. · Progress in Nuclear Energy · 26
Screening of TODGA/TBP/OK solvent mixtures for the grouped extraction of actinides
2010 · Jamie Brown, Michael J Carrott, et al. · IOP Conference Series Materials Science and Engineering · 26
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“TRU-SANEX”: A variation on the EURO-GANEX and i -SANEX processes for heterogeneous recycling of actinides Np-Cm
2016 · Michael Carrott, Chris Maher, et al. · Separation Science and Technology · 24
Neptunium (V) Oxidation by Nitrous Acid in Nitric Acid
2012 · Colin Gregson, Colin Boxall, et al. · Procedia Chemistry · 24
Thermal Processing of Chloride-Contaminated Plutonium Dioxide
2019 · Kevin Webb, Robin Taylor, et al. · ACS Omega · 15
The Separation of 241Am from Aged Plutonium Dioxide for Use in Radioisotope Power Systems Using the AMPPEX Process
2016 · Catherine Campbell, Cheryl Carrigan, et al. · Procedia Chemistry · 9
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Experimental testing and process simulation of flowsheets for the co-separation of uranium and plutonium using acetohydroxamic acid as a complexing agent
2024 · Hongyan Chen, Robin Taylor, et al. · Progress in Nuclear Energy · 7
PROGRESS ON 241Am PRODUCTION FOR USE IN RADIOISOTOPE POWER SYSTEMS
2014 · Sherri Baker, K. J. Bell, et al. · Joint Research Centre (European Commission) · 4
Selective Uranium Extraction by DEHiBA: Results of a Flowsheet Test in Centrifugal Contactors
2025 · Michael Carrott, Ellen Cosh, et al. · Solvent Extraction and Ion Exchange
Developments of the Americium and Plutonium Purification by Extraction (AMPPEX) Process and the PuMA 2 Scale-Up Opportunities
2023 · Rebecca Sanderson, Mark Sarsfield, et al. · Nuclear and Emerging Technologies for Space (NETS)
Progress on an Alternative Solvent Extraction Flowsheet for Separating Plutonium from Neptunium
2022 · Catherine Campbell, Michael Carrott, et al. · Nuclear and Emerging Technologies for Space (NETS)
Optimisation of the Americium and Plutonium Purification by Extraction (AMPPEX) Process Flowsheet
2022 · Rebecca Sanderson, Mark Sarsfield, et al. · Nuclear and Emerging Technologies for Space (NETS)
Development of a Grouped Actinide Extraction process for Advanced Nuclear Fuel Recycling
2021 · Robin J. Taylor, Jean-Marc Adnet, et al.
Progress towards reference routes for recycling actinides in future nuclear fuel cycles
2017 · R.G. Taylor, Stéphane Bourg, et al.
Works count: 22
Citation count: 655
H-index: 11
I10-index: 11
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