M. Sarsfield, M. Carrott, C. Maher, C. Mason, R. Sanderson, R. J. Taylor, T. Tinsley, D. Whittaker, D. Woodhead
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引用次数: 1
Abstract
ABSTRACT The production of 238Pu from 237Np, to the specifications required for space flight, requires the separation of plutonium from neptunium and a range of fission products. The valuable neptunium is then recycled into targets for further irradiation. At Oak Ridge National Laboratory (ORNL), a solvent extraction process has been developed to separate neptunium and plutonium that uses sodium nitrite to control the neptunium oxidation. This results in a neptunium product contaminated with sodium, which needs to be removed prior to recycling. We have developed a separation process that results in a sodium-free neptunium product with very low levels of plutonium contamination, there by reducing the number of purification steps and thus simplifying the process.
期刊介绍：
Solvent Extraction and Ion Exchange is an international journal that publishes original research papers, reviews, and notes that address all aspects of solvent extraction, ion exchange, and closely related methods involving, for example, liquid membranes, extraction chromatography, supercritical fluids, ionic liquids, microfluidics, and adsorption. We welcome submissions that look at: The underlying principles in solvent extraction and ion exchange; Solvent extraction and ion exchange process development; New materials or reagents, their syntheses and properties; Computational methods of molecular design and simulation; Advances in equipment, fluid dynamics, and engineering; Interfacial phenomena, kinetics, and coalescence; Spectroscopic and diffraction analysis of structure and dynamics; Host-guest chemistry, ion receptors, and molecular recognition.
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