Los Alamos National Security, LLC

Triad National Security, LLC

Iain May

Gregory Dale

Sean Douglas Reilly

Roy Copping

Janelle Droessler

Christopher Leibman

Nicholas Hubley

Disclosed herein are embodiments of methods for isolating rare earth elements (REEs) and radioisotopes from coal combustion products, such as fly ash. In particular embodiments, lanthanides, Al, Sc, Y, or compounds comprising lanthanides, AI, Sc, Y, or any combination thereof; or actinides can be isolated using the methods disclosed herein.

Method embodiments for extracting elements from coal combustion products

A processes for recycling uranium that has been used for the production of molybdenum-99 involves irradiating a solution of uranium suitable for forming fission products including molybdenum-99, conditioning the irradiated solution to one suitable for inducing the formation of crystals of uranyl nitrate hydrates, then forming the crystals and a supernatant and then separating the crystals from the supernatant, thus using the crystals as a source of uranium for recycle. Molybdenum-99 is recovered from the supernatant using an adsorbent such as alumina. Another process involves irradiation of a solid target comprising uranium, forming an acidic solution from the irradiated target suitable for inducing the formation of crystals of uranyl nitrate hydrates, then forming the crystals and a supernatant and then separating the crystals from the supernatant, thus using the crystals as a source of uranium for recycle. Molybdenum-99 is recovered from the supernatant using an adsorbent such as alumina.

Recovering and recycling uranium used for production of molybdenum-99

A process for minimizing waste and maximizing utilization of uranium involves recovering uranium from an irradiated solid target after separating the medical isotope product, molybdenum-99, produced from the irradiated target. The process includes irradiating a solid target comprising uranium to produce fission products comprising molybdenum-99, and thereafter dissolving the target and conditioning the solution to prepare an aqueous nitric acid solution containing irradiated uranium. The acidic solution is then contacted with a solid sorbent whereby molybdenum-99 remains adsorbed to the sorbent for subsequent recovery. The uranium passes through the sorbent. The concentrations of acid and uranium are then adjusted to concentrations suitable for crystallization of uranyl nitrate hydrates. After inducing the crystallization, the uranyl nitrate hydrates are separated from a supernatant. The process results in the purification of uranyl nitrate hydrates from fission products and other contaminants. The uranium is therefore available for reuse, storage, or disposal.

Recovery of uranium from an irradiated solid target after removal of molybdenum-99 produced from the irradiated target

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Los Alamos, NM, United States of America

Iain May