发明名称 RECOVERY OF URANIUM FROM AN IRRADIATED SOLID TARGET AFTER REMOVAL OF MOLYBDENUM-99 PRODUCED FROM THE IRRADIATED TARGET
摘要 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.
申请公布号 US2015085964(A1) 申请公布日期 2015.03.26
申请号 US201314042115 申请日期 2013.09.30
申请人 Los Alamos National Security, LLC 发明人 REILLY Sean Douglas;MAY Iain;Copping Roy;DALE Gregory Edward
分类号 G21G1/04 主分类号 G21G1/04
代理机构 代理人
主权项 1. A process for recovering uranium from an irradiated solid target after recovering molybdenum-99 (Mo-99) produced from the irradiated target, comprising: irradiating a solid target comprising uranium to produce fission products comprising Mo-99, and thereafter dissolving the target to form a solution and conditioning the solution to provide an aqueous nitric acid solution comprising a first acid concentration and a first uranium concentration, and thereafter contacting this solution with a solid sorbent, whereby uranium remains in the nitric acid while the Mo-99 is bound to the sorbent for subsequent retrieval, adjusting the concentration of nitric acid and the concentration of uranium in the solution to concentrations suitable for crystallization of uranyl nitrate hydrates, and thereafter inducing the crystallization of uranyl nitrate hydrates, and separating the uranyl nitrate hydrates crystalline product from a supernatant, and thereby purifying the uranium nitrate hydrates from fission products and other impurities.
地址 Los Alamos NM US