Uranium(VI)/Plutonium(IV) Separation from Spent MOX Fuels Using a Single Monoamide Extractant: The PUMAS Process by Michaud Solenne, Duterme Amandine, Costenoble Sylvain, Lengrand Fabien, Vanel Vincent, Moeyaert Pauline, Sarrat Pierre, Sorel Christian, Miguirditchian Manuel

“…In the context of the development of generation IV reactors, solvent extraction process is under development for the reprocessing of spent nuclear fuels. A monoamide extractant was found to be a suitable replacement for TBP. …”
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The Separate Removal of Trace CO and Moist NO from Off-Gases by Adsorption on H-Type Mordenite by Z.-M. Wang, T. Arai, M. Kumagai

“…Three kinds of mordenite were examined for the adsorptive separation and removal of trace amounts of 14 CO 2 and moist NO x contained in the off-gases of reprocessing plants for spent nuclear fuels. It was found that protonation of mordenite eliminated any possible removal of CO 2 by specific adsorption but induced the dissociative adsorption of NO 2 with the formation of nitric acid-like adsorbed species and NO oxidation. …”
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Atomistic Simulation of High-Density Uranium Fuels by Jorge Eduardo Garcés, Guillermo Bozzolo

“…Recent experimental results confirmed early theoretical proposals, along the lines of the results reported in this work, showing that atomistic computational modeling could become a valuable tool to aid the experimental work in the development of nuclear fuels.…”
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Research Areas on Transition to Renewable Energy Sources in Bibliographic Publications by Mammadov Nurmammad, Akbarova Samira

“…Energy transition involves the use of renewable energy sources to replace fossil and nuclear fuels. Energy transition issues are in the spotlight of both the global community and Azerbaijan, where the significant potential of renewable energy sources has served as the basis for integrating renewable energy into the country's energy supply system. …”
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Transmutations of Long-Lived and Medium-Lived Fission Products Extracted from CANDU and PWR Spent Fuels in an Accelerator-Driven System by Alper Buğra Arslan, İlayda Yilmaz, Gizem Bakir, Hüseyin Yapici

“…While the considered ADS is fueled with the spent nuclear fuels extracted from each thermal reactor without the use of additional fuel, fission products extracted from same thermal reactor are also placed into transmutation zone in graphite reflector zone. …”
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