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Title: 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:
; ; ;
Publication Date:
Research Org.:
Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1399866
Patent Number(s):
9,793,023
Application Number:
14/042,115
Assignee:
Los Alamos National Security, LLC LANL
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. doi:. 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 = {Tue Oct 17 00:00:00 EDT 2017},
month = {Tue Oct 17 00:00:00 EDT 2017}
}

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Works referenced in this record:

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