Methods of producing and recovering plutonium-238

a plutonium and radioisotope technology, applied in chemical to radiation conversion, nuclear engineering, conversion outside reactor/acceleration, etc., can solve the problems of reducing the supply of pu-238, consuming no alternative production process, and limited foreign supplies of pu-238. , to achieve the effect of eliminating time, cost, and hazards for personnel, high purity and improved efficiency

Inactive Publication Date: 2011-11-03
BATTELLE ENERGY ALLIANCE LLC
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  • Application Information

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Problems solved by technology

However, the supply of Pu-238 is decreasing because there has been no domestic production in over twenty years, and foreign supplies of Pu-238 are limited and will be consumed in the near future.
No alternative production processes are currently available.
This process has limited efficiency because, during solid target irradiation times, the Pu-238 can capture one or two neutrons, forming plutonium-239 (Pu-239) or plutonium-240 (Pu-240), which decrease the purity of the Pu-238.
However, the preparation, loading, unloading, target dissolution, and plutonium separation from the Np-237 target is time consuming, costly, and exposes personnel to radiation.

Method used

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  • Methods of producing and recovering plutonium-238
  • Methods of producing and recovering plutonium-238
  • Methods of producing and recovering plutonium-238

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Embodiment Construction

[0012]Methods of producing and recovering Pu-238 are disclosed. The Pu-238 is produced by neutron capture on Np-237. The Np-237 is dissolved to produce a neptunium target solution containing the Np-237. The neptunium target solution is continuously circulated through a neutron field and radiated with neutrons to produce Np-238, which decays to Pu-238. A liquid loop is used to circulate the neptunium target solution through the neutron field. As used herein, the term “liquid loop” means and includes means for transporting or circulating the neptunium target solution, an irradiated neptunium target solution, or an extracted neptunium target solution throughout the neutron field. The Pu-238 is selectively removed from the irradiated neptunium target solution using an organophosphorus extractant and subsequently recovered. The methods of the present invention are cost effective and provide Pu-238 at a higher purity than conventional processes of producing Pu-238. By utilizing a neptuniu...

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Abstract

Methods of producing plutonium-238 are disclosed. One method includes dissolving neptunium-237 in a nitric acid solution to produce a neptunium target solution, subjecting the neptunium target solution to neutron radiation to produce plutonium-238, and removing the plutonium-238 from the neptunium target solution. A second method includes exposing a solution of neptunium-237 to neutron radiation to produce plutonium-238, complexing the plutonium-238 with an organophosphorus compound, and separating the plutonium-238 / organophosphorus compound complex from the solution of neptunium-237. A third method includes dissolving neptunium-237 to form a neptunium-237 target solution, exposing the neptunium-237 to thermal neutrons to produce plutonium-238, utilizing an organophosphorus compound to complex the plutonium-238 and the organophosphorus compound, extracting the plutonium-238 / organophosphorus compound complex from the irradiated neptunium target solution, and recovering the plutonium-238.

Description

CROSS-REFERENCE TO RELATED APPLICATION[0001]This application is related to co-pending U.S. patent application Ser. No. 12 / 468,679 to Meikrantz et al., entitled “METHODS OF PRODUCING CESIUM-131,” filed on May 19, 2009, the disclosure of which is incorporated by reference herein in its entirety.STATEMENT REGARDING FEDERALLY SPONSORED RESEARCH OR DEVELOPMENT[0002]This invention was made with government support under Contract Number DE-AC07-05ID14517 awarded by the United States Department of Energy. The government has certain rights in the invention.TECHNICAL FIELD[0003]The invention, in various embodiments, relates generally to methods of producing and recovering radioisotopes. More specifically, the invention, in various embodiments, relates to methods of producing and recovering plutonium-238 (Pu-238).BACKGROUND[0004]Pu-238 is used to generate electrical power, such as in radioisotope thermoelectric generators and radioisotope heater units, in situations where solar energy or intern...

Claims

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Application Information

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Patent Type & Authority Applications(United States)
IPC IPC(8): C22B60/00
CPCC22B60/04G21G2001/0094G21G1/06
Inventor MEIKRANTZ, DAVID H.WERNER, JAMES E.HENRY, ROGER N.MARTIN, LEIGH R.MINCHER, BRUCE J.BESS, JOHN D.
Owner BATTELLE ENERGY ALLIANCE LLC
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