Zobrazeno 1 - 6
of 6
pro vyhledávání: '"Perry N. Motsegood"'
Publikováno v:
Journal of Nuclear Materials. 511:297-303
A parametric study of the electrolytic reduction of uranium dioxide in molten lithium chloride – lithium oxide using carbon anodes was conducted to determine the operational parameter values necessary for high yields. Operational parameters evaluat
Autor:
James L. Willit, Perry N. Motsegood, Dev Chidambaram, Augustus Merwin, William C. Phillips, Mark A. Williamson
Publikováno v:
Scientific Reports
Molten mixtures of lithium chloride and metallic lithium are of significant interest in various metal oxide reduction processes. These solutions have been reported to exhibit seemingly anomalous physical characteristics that lack a comprehensive expl
Autor:
Perry N. Motsegood, John E. Baur
Publikováno v:
Journal of Electroanalytical Chemistry. 572:29-40
Three-dimensional random walk simulations were used to model the diffusional interactions between coplanar dual disk microelectrodes. Working curves for the dependence of shielding factor, collection efficiency, and amplification factor on the size o
Publikováno v:
Journal of Chromatography A. 771:89-98
A gradient elution method with conventional electrochemical detection was developed to separate four analogs of the nitroxide 2,2,6,6-tetramethyl-1-piperidinyloxy (TEMPO) free radical in less than 3 min. The corresponding hydroxylamines and oxoammoni
Publikováno v:
ECS Meeting Abstracts. :3453-3453
Pyrochemical processing (often referred to as “pyroprocessing”) of used nuclear fuel utilizes molten salts and molten metals at elevated temperatures as process fluids to separate actinides from fission products. In broad terms, separations are a
Publikováno v:
ECS Meeting Abstracts. :3455-3455
Recycling of used nuclear fuel using pyrochemical methods involves a series of molten salt processes performed at elevated temperatures and results in the separation of actinides from fission products. The first step in the pyrochemical treatment of