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Available Technologies

For more information regarding any of these technologies, please contact Eric Lund, commercialization manager.

Patent Number: 8,781,055
Title: Method and system for radioisotope generation
Portfolio: Radiochemical Processing
Inventor(s): Mattigod, Shas V; Fryxell, Glen E; O'Hara, Matthew J; Toth, James J; Greenwood, Lawrence R; Soderquist, Chuck Z
Abstract: A system and a process for producing selected isotopic daughter products from parent materials characterized by the steps of loading the parent material upon a sorbent having a functional group configured to selectively bind the parent material under designated conditions, generating the selected isotopic daughter products, and eluting said selected isotopic daughter products from the sorbent. In one embodiment, the process also includes the step of passing an eluent formed by the elution step through a second sorbent material that is configured to remove a preselected material from said eluent. In some applications a passage of the material through a third sorbent material after passage through the second sorbent material is also performed.

Patent Number: 8,126,104
Title: Medical Radioisotopes and Methods for Producing the Same (Incorporates 14348-B, 14402-B, 14398-B, 14399-B & 14795-B)
Portfolio: Radiochemical Processing
Inventor(s): Wester, Dennis W; Schenter, Bob; Hollenberg, Glenn W; Rapko, Brian M; Lumetta, Gregg J
Abstract: Methods for producing radioisotopes required for nuclear-medicine procedures using particle accelerators with small dimensions that can easily be located within a standard-sized laboratory are described. In particular, a method for producing Mo-99 from a target consisting of Zr-96 via an (a, n) reaction has several advantages over current methods used to produce Mo-99. The Zr-96 target contains a stable isotope and does not have the proliferation or RDD implications of the U-235 targets that are currently used. A nuclear reactor is not required to produce the Mo-99. The Mo-99 can be isolated from the target material without interference from multiple fission products. The separation of Mo-99 from Zr-96 is straightforward. In addition, rotation of a thin circular target disk or spooling of a metallic wire target that provides for maximum use of the a-particles and quick dissolution of the target material is novel, to the best of our knowledge. The method should be applicable to the production of many other medical radioisotopes by using the appropriate targets and separation procedures.

Patent Number: 7,554,098
Title: Medical Isotope Generator Systems
Portfolio: Radiochemical Processing
Inventor(s): Edwards, Matthew K; O'Hara, Matthew J; Rapko, Brian M; Wester, Dennis W
Abstract: A prototype automated dual-column medical isotope generator system and the necessary separation chemistry have been developed for the production of Y-90 from a generator column containing Sr-90 source. The system enables hands-free "milking" of Y-90 from Sr-90 in a two-column, two-reagent system. The prototype instrument is capable of recovering >95% of yttrium tracer within 10mL of product elution volume. Furthermore, the Y-90 eluting solution has been shown to be compatible with subsequent labeling step using a chelator.

Patent Number: 6,869,588
Title: Stimulus Sensitive Gel With Radioisotope And Methods Of Making
Portfolio: Biomaterials
Sub-Portfolio: Stimuli Sensitive Polymers
Inventor(s): Weller, Richard E; Fisher, Darrell R; Lind, Michael A; Campbell, Allison A; Gutowska, Anna
Abstract: The reversible polymer solution is mixed with the desired radionuclide at room temperature, resulting in a liquid polymer suspension. When exposed to physiological conditions such as pH, temperature or ionic strength, the suspension changes into a solid gel with the radionuclide component entrapped effectively within the reversible gel matrix. The gel matrix may be designed with an adustable dissolution rate to allow anything from slow release of the radioactive material to retaining it permanently in place. The principle objective is to allow the radinuclide to disperse interstitially among the cancer cells to be treated, and to limit the transport of the radionuclide via circulating blood and the lymphatic system to normal organs and tissues. lkw 8.12.96

Patent Number: 6,296,831
Title: Stimulus Sensitive Gel With Radioisotope And Methods Of Making
Portfolio: Biomaterials
Sub-Portfolio: Stimuli Sensitive Polymers
Inventor(s): Weller, Richard E; Fisher, Darrell R; Lind, Michael A; Campbell, Allison A; Gutowska, Anna
Abstract: The reversible polymer solution is mixed with the desired radionuclide at room temperature, resulting in a liquid polymer suspension. When exposed to physiological conditions such as pH, temperature or ionic strength, the suspension changes into a solid gel with the radionuclide component entrapped effectively within the reversible gel matrix. The gel matrix may be designed with an adustable dissolution rate to allow anything from slow release of the radioactive material to retaining it permanently in place. The principle objective is to allow the radinuclide to disperse interstitially among the cancer cells to be treated, and to limit the transport of the radionuclide via circulating blood and the lymphatic system to normal organs and tissues. lkw 8.12.96

Patent Number: 13/766,600
Title: Nuclear Reactor Target Assemblies, Nuclear Reactor Configurations, and Methods for Producing Isotopes, Modifying Materials Within Target Material, and/or Characterizing Material Within a Target Material
Portfolio: Energy Conversion & Efficiency
Sub-Portfolio: Nuclear
Inventor(s): Wittman, Rick; Greenwood, Lawrence R; Toth, James J; Pierson, Bruce D
Abstract: Target assemblies are provided that can include a uranium-comprising annulus. The assemblies can include target material consisting essentially of non-uranium material within the volume of the annulus. Reactors are disclosed that can include one or more discrete zones configured to receive target material. At least one uranium-comprising annulus can be within one or more of the zones. Methods for producing isotopes within target material are also disclosed, with the methods including providing neutrons to target material within a uranium-comprising annulus. Methods for modifying materials within target material are disclosed as well as are methods for characterizing material within a target material.

Patent Number: 8,425,654
Title: Purification Process for 153Gd Produced in Natural Europium Targets
Portfolio: Radiochemical Processing
Inventor(s): Johnsen, Amanda M; McNamara, Bruce K; Soderquist, Chuck Z; Fisher, Darrell R
Abstract: Irradiated europium oxide is dissolved in hydrochloric acid, then converted to dry europium chloride solution in methanol. The use of methanol instead of traditional water eliminates hydrogen gas generation and allows better reduction of europium. The methanol solution is passed through a metallic zinc reductor column to reduce Eu(III) to Eu(II). Zinc, dissolved by reaction with europium, is precipitated with hydrogen sulfide and tetramethylammonium hydroxide, then filtered out of solution. The Eu(II) is precipitated as EuSO4 and filtered out, leaving Gd(III) in solution.

Patent Number: 6,972,414
Title: Method and Apparatus for Production of 213-Bi from the High Activity 225-Ac Source
Portfolio: Radiochemical Processing
Inventor(s): Egorov, Oleg B; O'Hara, Matthew J
Abstract: A prototype automated dual-column medical isotope generator system and the necessary separation chemistry have been developed for the production of Y-90 from a generator column containing Sr-90 source. The system enables hands-free "milking" of Y-90 from Sr-90 in a two-column, two-reagent system. The prototype instrument is capable of recovering >95% of yttrium tracer within 10mL of product elution volume. Furthermore, the Y-90 eluting solution has been shown to be compatible with subsequent labeling step using a chelator.

Patent Number: 5,809,394
Title: Method Of Separating And Purifying Short Half-Life Radionuclides From A Mixture Of Radionuclides*
Portfolio: Radiochemical Processing
Inventor(s): Bray, Lane A; Ryan, Jack L
Abstract: A prototype automated dual-column medical isotope generator system and the necessary separation chemistry have been developed for the production of Y-90 from a generator column containing Sr-90 source. The system enables hands-free "milking" of Y-90 from Sr-90 in a two-column, two-reagent system. The prototype instrument is capable of recovering >95% of yttrium tracer within 10mL of product elution volume. Furthermore, the Y-90 eluting solution has been shown to be compatible with subsequent labeling step using a chelator.

Patent Number: 5,749,042
Title: Bismuth Generator Method
Portfolio: Radiochemical Processing
Inventor(s): Bray, Lane A; Deschane, Jaquetta R
Abstract: A method for purifying a solution of radionuclides or more specifically to a method for separation of 213 Bi from a solutino or mixture of radionuclides (225Ac,225Ra,213Bi) and daughters. As used herin, the term solutino is a subset of the term mixture in accordance with standard definitions. The end product relates to the development of a new 213Bi-Generator concept.

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