专利检索_ .从照射目标恢复的特定同位素专利检索_ .从照射目标恢复的特定同位素专利检索查询

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序号	专利名	申请号	申请日	公开（公告）号	公开（公告）日	发明人
101	원심분리기를 이용한 우라늄 동위원소 분리방법	KR1020050106524	2005-11-08	KR1020070049400A	2007-05-11	김유경; 정영기; 정호민; 정호림
본 발명은 우라늄 농축을 위한 기체 원심분리를, 우라늄-235가 함유된 육불화우라늄 기체와 우라늄-238이 함유된 육불화우라늄 기체 이외에, 분자량이 349와 352 사이인 중간기체를 추가로 첨가하여 행하는 원심분리기를 이용한 우라늄 동위원소 분리방법을 제공한다. 육불화우라늄, 원심분리, 우라늄 동위원소, 기체
102	방사성동위원소 생산용 타겟 회수 및 냉각 장치	KR1019980042744	1998-10-13	KR1020000025597A	2000-05-06	양승대; 전권수; 서용섭; 안순혁; 이지섭; 윤용기; 박현; 이종두; 임상무
PURPOSE: A target recovery and cooling apparatus for producing a radioactive isotope is provided to generate a radioactive isotope easily by the usage of a fluid target such as a liquid or a gas. CONSTITUTION: In a target recovery and cooling apparatus for producing a radioactive isotope, a supplying container(2) supplies a fluid target, and syringe pump(3) takes a fluid target of a constant amount from the supplying container to send the taken fluid target to the next stage. A six-port valve(4) is connected to the syringe pump, and outputs a fluid in the predetermined direction. A target chamber(TC) is supplied with the fluid target from the six-port valve, and generates a radioactive isotope when a proton beam is incident to the fluid target. A helium container(5) is connected to the target chamber, and pushes the fluid target incorporating the radioactive isotope to the six-port valve. A recovery container(6) is connected to the helium container, and extracts the radioactive isotope from the fluid target to recover the fluid target. A cooling part(7) is installed at the front part of the target chamber, and cools a heat generated at the target chamber.
103	AUTOMATIC PROCESS PLATFORM FOR THE PRODUCTION OF ASTATINE-211 [At-211]-RADIOPHARMACEUTICALS	US15530265	2015-06-17	US20180215680A1	2018-08-02	Sture Lindegren; Emma Aneheim
A system and method for automatic production of astatine-211 labeled molecules is described. The invention represents a significant advantage in the preparation of At-211 radiopharmaceuticals including better reproducibility, reduced production time and increased radiation safety. The invention also enables routine automatic synthesis of radiopharmaceuticals in a clinical setting, in conjunction or at short distance from a cyclotron unit capable of producing the radionuclide.
104	Production of copper-67 from an enriched zinc-68 target	US14819271	2015-08-05	US10006101B2	2018-06-26	Jon Stoner; Tim Gardner
An apparatus including a heating element and a sublimation vessel disposed adjacent the heating element such that the heating element heats a portion thereof. A collection vessel is removably disposed within the sublimation vessel and is open on an end thereof. A crucible is configured to sealingly position a solid mixture against the collection vessel.
105	PROCESSES FOR GENERATING GERMANIUM-68 WITH REDUCED VOLATILES	US15806517	2017-11-08	US20180137947A1	2018-05-17	David Pipes; William Uhland; Melissa Perrigo; Mark Owens
Processes for producing germanium-68 from a gallium target body are disclosed. In some embodiments, germanium-68 and gallium are precipitated to remove metal impurities. Germanium-68 and gallium are re-dissolved and loaded onto an ion exchange column to separate germanium-68 from gallium.
106	INTEGRATED STRONTIUM-RUBIDIUM RADIOISOTOPE INFUSION SYSTEMS	US15809103	2017-11-10	US20180093035A1	2018-04-05	Stephen E. Hidem; Aaron M. Fontaine; Janet L. Gelbach; Patrick M. McDonald; Kathryn M. Hunter; Rolf E. Swenson; Julius P. Zodda
Methods for setting up, maintaining and operating a radiopharmaceutical infusion system, that includes a radioisotope generator, are facilitated by a computer of the system. The computer may include pre-programmed instructions and a computer interface, for interaction with a user of the system, for example, in order to track contained volumes of eluant and/or eluate, and/or to track time from completion of an elution performed by the system, and/or to calculate one or more system and/or injection parameters for quality control, and/or to perform purges of the system, and/or to facilitate diagnostic imaging.
107	SCANDIUM NANO-RADIOPHARMACEUTICAL	US15796775	2017-10-28	US20180055955A1	2018-03-01	Navideh Aghaei Amirkhizi; Leila Moghaddam-Banaem; Mitra Athari Allaf; Sodeh Sajadi; Fariba Johari Daha
Disclosed herein is a method for preparing a scandium nano-radiopharmaceutical. The method comprises forming a plurality of scandium-encapsulated dendrimers by encapsulating scandium in polyamidoamine (PAMAM) dendrimers with amine surface groups, and forming a scandium nano-radiopharmaceutical by irradiating the plurality of scandium-encapsulated dendrimers by bombarding neutrons toward the scandium-encapsulated dendrimers.
108	RADIOISOTOPE RECOVERY	US15521207	2015-10-22	US20180025801A1	2018-01-25	Stephen James Archibald; Ping He; Stephen John Haswell; Nicole Pamme; Nathan Joel Brown; Mark Duncan Tarn; Richard Alexander
The present invention relates to a method and an apparatus for separating and recovering a radioisotope from a solution. More particularly, certain embodiments of the invention relate to a method for recovering a radioisotope from a solution by electro-trapping and release using a microfluidic cell (10). The radioisotope may subsequently be used in the preparation of radiopharmaceuticals.
109	Production of radiopharmaceuticals	US15455618	2017-03-10	US09865368B1	2018-01-09	Ioannis Akrotirianakis; Amit Chakraborty; Todd Putvinski; Eric Greaser; Steven Zigler
A computer-implemented method for determining optimized amount of radiopharmaceutical to be produced at a production facility, the radiopharmaceutical being for use in nuclear imaging at customer sites, in order to meet aggregate demands of orders placed by the customer sites (e.g. medical imaging centers, hospitals, etc.), wherein the quantity of radiopharmaceutical is sufficient to meet the aggregate demand while minimizing any overproduction of the radiopharmaceutical.
110	APPARATUS FOR PREPARING MEDICAL RADIOISOTOPES	US15526699	2015-11-17	US20170337997A1	2017-11-23	Keith A. Woloshun; Eric R. Olivas; Gregory E. Dale
Apparatus for radioisotope production includes housing, a plurality of target disks inside the housing and a curved windows positioned convex inward toward the disks. During operation, coolant flows though the housing across the disks and windows while electron beams passes through the window and the disks. The window temperature increases, rising the fastest in the middle of the window where the electron beam hits the window. A flat window would buckle because the center would deform during thermal expansion against the relatively unaffected periphery, but the curved window shape allows the window to endure high thermal and mechanical stress created by a combination of heating from the electron beam(s) and elevated pressure from coolant on the inside of the window. Such a window may be used for applications in which a pressurized coolant acts on only one side of the window.
111	Method for purification of 225AC from irradiated 226RA-targets	US15359053	2016-11-22	US09790573B2	2017-10-17	Josue Manuel Moreno Bermudez; Andreas Turler; Richard Henkelmann; Eva Kabai; Ernst Huenges
The present invention describes a method for purification of 225Ac from irradiated 226Ra-targets provided on a support comprising a leaching treatment of the 225Ra-targets for leaching essentially for the entirety of 223Ac and 226Ra with nitric or hydrochloric acid, followed by a first extraction chromatography for separating 225Ac from 226Ra and other Ra-isotops and a second extraction chromotography for separating 225Ac from 210Po and 210Pb. The finally purified 225Ac can be used to prepare compositions useful for pharmaceutical purposes.
112	METHOD OF MANUFACTURING A RADIATION SOURCE	US15532089	2015-12-04	US20170271038A1	2017-09-21	Matthew David Butts; Charles E. Shanks
An equatorial anthropic radiation source and a method of making an equatorial anthropic radiation source are described. The radiation source is useful in diagnostic imaging applications in healthcare or other industries (e.g. computerized three-dimensional segmental imaging; Crompton scattering imaging techniques; radiation detector check and calibration, in particular CdZnTe detectors commonly used in medical imaging).
113	Integrated strontium-rubidium radioisotope infusion systems	US15490484	2017-04-18	US09750870B2	2017-09-05	Stephen E. Hidem; Aaron M. Fontaine; Janet L. Gelbach; Patrick M. McDonald; Kathryn M. Hunter; Rolf E. Swenson; Julius P. Zodda
Methods for setting up, maintaining and operating a radiopharmaceutical infusion system, that includes a radioisotope generator, are facilitated by a computer of the system. The computer may include pre-programmed instructions and a computer interface, for interaction with a user of the system, for example, in order to track contained volumes of eluant and/or eluate, and/or to track time from completion of an elution performed by the system, and/or to calculate one or more system and/or injection parameters for quality control, and/or to perform purges of the system, and/or to facilitate diagnostic imaging.
114	TECHNIQUES FOR ON-DEMAND PRODUCTION OF MEDICAL ISOTOPES SUCH AS MO-99/TC-99M AND RADIOACTIVE IODINE ISOTOPES INCLUDING I-131	US15436432	2017-02-17	US20170236607A1	2017-08-17	Francis Yu-Hei Tsang
A system and method for radioisotope production uses fast-neutron-caused fission of depleted or naturally occurring uranium targets in an irradiation chamber. Fast fission can be enhanced by having neutrons encountering the target undergo scattering or reflection to increase each neutron's probability of causing fission (n, f) reactions in U-238. The U-238 can be deployed as one or more layers sandwiched between layers of neutron-reflecting material, or as rods surrounded by neutron-reflecting material. The gaseous fission products can be withdrawn from the irradiation chamber on a continuous basis, and the radioactive iodine isotopes (including I-131) extracted.
115	APPARATUS AND METHODS FOR TRANSMUTATION OF ELEMENTS	US15417668	2017-01-27	US20170200521A1	2017-07-13	William Vaden Dent, JR.
Examples of apparatus and methods for transmutation of an element are disclosed. An apparatus can include a neutron emitter configured to emit neutrons with a neutron output, a neutron moderator configured to reduce the average energy of the neutron output to produce a moderated neutron output, a target configured to absorb neutrons when exposed to the moderated neutron output, the absorption of the neutrons by the target producing a transmuted element, and an extractor configured to extract the desired element. A method can include producing a neutron output, reducing the average energy of the neutron output with a neutron moderator to produce a moderated neutron output, absorbing neutrons from the moderated neutron output with the target to generate a transmuted element, and eluting a solution through the target to extract a desired element. In some examples, the target includes molybdenum-98, and the desired element includes technetium-99m.
116	DEVICE AND METHOD FOR THE PRODUCTION OF RADIOISOTOPES	US15470513	2017-03-27	US20170200520A1	2017-07-13	Taylor Ramon WILSON
A dense plasma focus (DPF) to produce positron emitters is provided, where a pulsed device has an anode and a cathode arranged in a vacuum chamber, the anode and cathode being subjected to a high voltage. When the vacuum chamber is filled with a reaction gas and a high voltage generated is applied, a plasma sheath is created and a reaction between the electrodes take place to produce plasmoids resulting in an ion beam that interacts with a reactive gas to produce radio-isotopes.
117	METHOD FOR PRODUCING BETA EMITTING RADIOPHARMACEUTICALS, AND BETA EMITTING RADIOPHARMACEUTICALS THUS OBTAINED	US15115635	2014-12-18	US20170169908A1	2017-06-15	Alberto ANDRIGHETTO
The present invention relates to a method for producing beta emitting radiopharmaceuticals. The method provides to produce, through a primary accelerator, a low energy proton beam, namely with an energy lower than 70 MeV, preferably with an energy ranging from 32 to 45 MeV, more preferably with energy ranging from 38 to 42 MeV; the low energy proton beam is irradiated on a source target so as to generate a neutral atom beam; the neutral atoms are ionized, extracted by acceleration and preferably subjected to a first focusing; the first focused beam is subjected to a mass separation such to generate a isobaric beam of radioisotopes. The isobaric beam therefore is preferably subjected to a second focusing and it is sent for a predetermined time on a deposition target. Then the irradiated deposition target is subjected to chemical treatment so as to obtain pure beta emitting radiopharmaceuticals.
118	Method and apparatus for isolating the radioisotope molybdenum-99	US12588030	2009-10-01	US09587292B2	2017-03-07	Suzanne Lapi; Thomas J. Ruth; Dirk W. Becker; John M. D'Auria
A method of isolating 99Mo produced using a (n,γ) reaction according to example embodiments may include vaporizing a source compound containing 98Mo and 99Mo. The vaporized source compound may be ionized to form ions containing 98Mo and 99Mo. The ions may be separated to isolate the ions containing 99Mo. The isolated ions containing 99Mo may be collected with a collector. Accordingly, the isolated 99Mo may have a relatively high specific radioactivity and, in turn, may be used to produce the diagnostic radioisotope, 99mTc, through radioactive decay.
119	METHOD FOR SEPARATION OF CHEMICALLY PURE OS FROM METAL MIXTURES	US15352304	2016-11-15	US20170058381A1	2017-03-02	Hendrik P. Engelbrecht; Cathy S. Cutler; Leonard Manson; Stacy Lynn Wilder
A method for separating an amount of osmium from a mixture containing the osmium and at least one other additional metal is provided. In particular, method for forming and trapping OsO4 to separate the osmium from a mixture containing the osmium and at least one other additional metal is provided.
120	Apparatus and methods for transmutation of elements	US13918196	2013-06-14	US09576690B2	2017-02-21	William Vaden Dent, Jr.
Examples of apparatus and methods for transmutation of an element are disclosed. An apparatus can include a neutron emitter configured to emit neutrons with a neutron output, a neutron moderator configured to reduce the average energy of the neutron output to produce a moderated neutron output, a target configured to absorb neutrons when exposed to the moderated neutron output, the absorption of the neutrons by the target producing a transmuted element, and an extractor configured to extract the desired element. A method can include producing a neutron output, reducing the average energy of the neutron output with a neutron moderator to produce a moderated neutron output, absorbing neutrons from the moderated neutron output with the target to generate a transmuted element, and eluting a solution through the target to extract a desired element. In some examples, the target includes molybdenum-98, and the desired element includes technetium-99m.

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