Recovery of uranium from an irradiated solid target after removal of molybdenum-99 produced from the irradiated target
Abstract
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.
- Inventors:
- Issue Date:
- Research Org.:
- Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
- Sponsoring Org.:
- USDOE
- OSTI Identifier:
- 1399866
- Patent Number(s):
- 9793023
- Application Number:
- 14/042,115
- Assignee:
- Los Alamos National Security, LLC
- Patent Classifications (CPCs):
-
G - PHYSICS G21 - NUCLEAR PHYSICS G21C - NUCLEAR REACTORS
G - PHYSICS G21 - NUCLEAR PHYSICS G21G - CONVERSION OF CHEMICAL ELEMENTS
- DOE Contract Number:
- AC52-06NA25396
- Resource Type:
- Patent
- Resource Relation:
- Patent File Date: 2013 Sep 30
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CHEMISTRY; 36 MATERIALS SCIENCE
Citation Formats
Reilly, Sean Douglas, May, Iain, Copping, Roy, and Dale, Gregory Edward. Recovery of uranium from an irradiated solid target after removal of molybdenum-99 produced from the irradiated target. United States: N. p., 2017.
Web.
Reilly, Sean Douglas, May, Iain, Copping, Roy, & Dale, Gregory Edward. Recovery of uranium from an irradiated solid target after removal of molybdenum-99 produced from the irradiated target. United States.
Reilly, Sean Douglas, May, Iain, Copping, Roy, and Dale, Gregory Edward. Tue .
"Recovery of uranium from an irradiated solid target after removal of molybdenum-99 produced from the irradiated target". United States. https://www.osti.gov/servlets/purl/1399866.
@article{osti_1399866,
title = {Recovery of uranium from an irradiated solid target after removal of molybdenum-99 produced from the irradiated target},
author = {Reilly, Sean Douglas and May, Iain and Copping, Roy and Dale, Gregory Edward},
abstractNote = {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.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2017},
month = {10}
}
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