The patent badge is an abbreviated version of the USPTO patent document. The patent badge does contain a link to the full patent document.

The patent badge is an abbreviated version of the USPTO patent document. The patent badge covers the following: Patent number, Date patent was issued, Date patent was filed, Title of the patent, Applicant, Inventor, Assignee, Attorney firm, Primary examiner, Assistant examiner, CPCs, and Abstract. The patent badge does contain a link to the full patent document (in Adobe Acrobat format, aka pdf). To download or print any patent click here.

Date of Patent:
Oct. 17, 2017

Filed:

Sep. 30, 2013
Applicant:

Los Alamos National Security, Llc, Los Alamos, NM (US);

Inventors:

Sean Douglas Reilly, Los Alamos, NM (US);

Iain May, Los Alamos, NM (US);

Roy Copping, Santa Fe, NM (US);

Gregory Edward Dale, Los Alamos, NM (US);

Assignee:

Los Alamos National Security, LLC, Los Alamos, NM (US);

Attorney:
Primary Examiner:
Int. Cl.
CPC ...
G21G 1/02 (2006.01); G21G 1/08 (2006.01); G21G 1/04 (2006.01); G21C 19/46 (2006.01); G21G 1/00 (2006.01);
U.S. Cl.
CPC ...
G21G 1/04 (2013.01); G21C 19/46 (2013.01); G21G 2001/0036 (2013.01); G21G 2001/0094 (2013.01); Y02W 30/883 (2015.05);
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.


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