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Небесная энциклопедия

Космические корабли и станции, автоматические КА и методы их проектирования, бортовые комплексы управления, системы и средства жизнеобеспечения, особенности технологии производства ракетно-космических систем

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Мониторинг СМИ

Мониторинг СМИ и социальных сетей. Сканирование интернета, новостных сайтов, специализированных контентных площадок на базе мессенджеров. Гибкие настройки фильтров и первоначальных источников.

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Применить Всего найдено 2178. Отображено 100.
02-02-2012 дата публикации

Isotope production target

Номер: US20120027152A1
Автор: Madicken Munk, Stephen Todd Keller, Steven Richard Reese, Todd Stephen Palmer
Принадлежит: Oregon State, Oregon State Board of Higher Education

An isotope production target may include an outer diameter wall and an inner diameter wall. An isotope source may be located between the inner diameter wall and the outer diameter wall, and the isotope source may comprise fissile material interspersed with one or more voided regions. A central region may be located within the inner diameter wall, and the central region may be configured to house a neutron thermalization volume.

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Номер записи: 1
26-04-2012 дата публикации

Electrochemical cell and method for separating carrier-free 18f-from a solution on an electrode

Номер: US20120097549A1
Автор: Kurt Hamacher
Принадлежит: FORSCHUNGSZENTRUM JUELICH GMBH

Disclosed is an electrochemical cell and a method for separating carrier-free radionuclides from a solution on an electrode. 18 F − is precipitated in an electrochemical cell from an aqueous solution on an anode, which is diamond-coated. Subsequently, the electrochemical cell is dried and supplied with a liquid containing a transfer catalyst, the anode is preferably switched to serve as the cathode, and 18 F − is transferred to the liquid phase.

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Номер записи: 2
14-06-2012 дата публикации

Electrochemical phase transfer devices and methods

Номер: US20120145557A1
Автор: Christian Rensch, Christoph Boeld, Marko Baller, Victor Samper
Принадлежит: General Electric Co

Devices and methods for electrochemical phase transfer utilize at least one electrode formed from either glassy carbon or a carbon and polymer composite. The device includes a device housing defining an inlet port ( 42 ), an outlet port ( 44 ) and an elongate fluid passageway ( 36 ) extending therebetween. A capture electrode ( 12 ) and a counter electrode are positioned within said housing such that the fluid passageway extends between the capture and counter electrodes.

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Номер записи: 3
28-03-2013 дата публикации

Universal mounting system for calibration source for use in pet scanners

Номер: US20130075599A1
Автор: Keith C. Allberg
Принадлежит: RADQUAL LLC

A universal mounting adapter is configured for interchangeably mounting a calibration source to two or more different imaging devices. The two imaging devices have different mounting brackets so they cannot be used with the same conventional calibration source. The present adapter includes mounting mechanisms for both types of bracket, allowing the attached calibration source to be moved from one imaging device to the other, while maintaining the calibration source in a prescribed geometry within the respective imaging device. This can be performed without the need for any tools.

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Номер записи: 4
09-05-2013 дата публикации

ECONOMICAL PRODUCTION OF ISOTOPES USING QUANTIZED TARGET IRRADIATION

Номер: US20130114775A1
Автор: CRAWFORD Douglas, HOWE Steven D., NAVARRO Jorge, RING Terry
Принадлежит: UNIVERSITIES SPACE RESEARCH ASSOCIATION

A process for producing isotopes by continuously flowing a liquid stream, carrying capsules of target nuclei (NP-237) in solution, through a nuclear reactor (a TRIGA style nuclear reactor). Upon removal from the core of the nuclear reactor and after allowing for the decay of Np-238 to Pu-238, the capsules are emptied and the mixture of elements and isotopes are chemically separated using solvent extraction or ion exchange. Isotopes that are capable of further processing into Pu-238 are recycled to the core for further processing 1. An apparatus for producing isotopes , comprising:hollow tubing configured to be arranged around a nuclear reactor core and further configured to contain a circulating capsule-bearing fluid, said capsules containing a solution of a material to be irradiated;a pump configured to force said circulating capsule-bearing fluid through said hollow tubing;a capsule loading station configured to introduce a solution of starting material into capsules;a capsule introduction station configured to introduce the capsules into said capsule-bearing fluid;a capsule withdrawal station configured to withdraw irradiated capsules from said circulating fluid and remove irradiated sample from said capsules;a separation station configured to receive said irradiated sample and separate a desired isotope from incomplete products and undesired products.2. A method for producing isotopes , comprising:encapsulating starting material-containing solution in capsules;introducing said capsules into hollow tubing containing a circulating fluid, said hollow tubing configured to pass through a water shield of a nuclear reactor in proximity to a core of said nuclear reactor allowing said starting material to absorb neutrons generated from said nuclear reactor core as it moves through said hollow tubing with said circulating fluid;pumping said circulating fluid through said hollow tubing;removing capsules containing irradiated solution from said hollow tubing, and removing ...

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Номер записи: 5
30-05-2013 дата публикации

METHOD OF PRODUCING RADIOACTIVE MOLYBDENUM

Номер: US20130136221A1
Автор: Akiyama Hiroaki, Ishida Takuya, KIMURA Akihiro, KITAGISHI Shigeru, NAGAKURA Masaaki, NISHIKATA Kaori, SUZUKI Kunihiko, TSUCHIYA Kunihiko
Принадлежит: JAPAN ATOMIC ENERGY AGENCY

To provide a method of producing radioactive molybdenum solution suitable for extracting Tc to be used as radioactive diagnostic drug by way of establishing a production process for high-density MoOpellets with a lower amount of insoluble content when dissolving the pellets. The method has the steps of: preparing MoOpowder, fabricating a MoOpellet by filling said MoOpowder in a heated die and sintering in an air, oxidizing said MoOpellet, producing neutron-irradiated MoOpellets by irradiating a neutron on said oxidized MoOpellet, and obtaining radioactive molybdenum solution by dissolving said neutron-irradiated MoOpellet. 1. A method of producing radioactive molybdenum solution comprising a step of preparing MoOpowder , a step of fabricating a MoOpellet by filling said MoOpowder in a heated die and sintering in an air , a step of oxidizing said MoOpellet , a step of producing neutron-irradiated MoOpellets by irradiating a neutron on said oxidized MoOpellet , and a step of obtaining radioactive molybdenum solution by dissolving said neutron-irradiated MoOpellet.2. The method of producing radioactive molybdenum solution according to claim 1 , wherein said step of oxidizing said MoOpellet is performed by means that said MoOpellet is exposed in ozone gas at a reaction temperature range grater than equal to a room temperature and less than 120° C. or baked preliminarily in an air at a temperature equal to or more than 350° C. and less than 500° C.3. The method of producing radioactive molybdenum solution according to claim 1 , wherein said step of obtaining radioactive molybdenum solution by dissolving said neutron-irradiated MoOpellet is performed by using a dissolving apparatus with ultrasonic device for said neutron-irradiated MoOpellet in 6M NaOH solution.4. A method of producing radioactive molybdenum solution comprising a step of preparing MoOpowder claim 1 , a step of fabricating a MoOpellet by sintering said MoOpowder in a heated die in an air at a temperature ...

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Номер записи: 6
04-07-2013 дата публикации

METHOD OF PRODUCING RADIONUCLIDES

Номер: US20130170593A1
Автор: Jansen David Randall, Kolar Zvonimir Ivica, Krijger Geert Cornelis, Zeevaart Jan Rijn
Принадлежит: The South African Nuclear Energy Corporation Ltd.

The invention relates to a method of producing radionuclides. According to the method, a target medium comprising at least a target nuclide material is irradiated in an irradiation zone with neutron irradiation. Radionuclides form in the target nuclide material as a result of the irradiation, and at least some of the formed radionuclides are ejected from the target nuclide material. The ejected radionuclides are then captured and collected in a carbon-based recoil capture material which does not have an empty cage structure at crystallographic level. 1. A method of producing radionuclides , which includesin an irradiation zone, irradiating a target medium comprising at least a target nuclide material, with neutron irradiation, thereby causing radionuclides to form in the target nuclide material, with at least some of the formed radionuclides being ejected from the target nuclide material; andcapturing and collecting the ejected radionuclides in a carbon-based recoil capture material which does not have an empty cage structure at crystallographic level.2. The method according to claim 1 , wherein the target nuclide material is selected from the group consisting of a pure metal and a metal compound.3. The method according to claim 2 , wherein the metal of the target nuclide material is selected from the group of metal elements in the Periodic Table of Elements extending from scandium claim 2 , of atomic number 21 claim 2 , to bismuth claim 2 , of atomic number 83 claim 2 , both elements included claim 2 , with the non-metal elements arsenic claim 2 , selenium claim 2 , bromine claim 2 , krypton claim 2 , tellurium claim 2 , iodine and xenon thus being excluded.4. The method according to claim 3 , wherein the metal of the target nuclide material is tin.5. The method according to claim 1 , wherein the recoil capture material is selected from amorphous carbon claim 1 , carbon allotropes claim 1 , and mixtures thereof.6. The method according to claim 1 , wherein the ...

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Номер записи: 7
04-07-2013 дата публикации

Systems and methods for processing irradiation targets through a nuclear reactor

Номер: US20130170927A1
Автор: Earl F. Saito, Jeffrey M. Hare, John F. Berger, Martin W. Brittingham, Stephen K. Morales, Yogeshwar Dayal
Принадлежит: GE HITACHI NUCLEAR ENERGY AMERICAS LLC

Apparatuses and methods produce radioisotopes in instrumentation tubes of operating commercial nuclear reactors. Irradiation targets may be inserted and removed from instrumentation tubes during operation and converted to radioisotopes otherwise unavailable during operation of commercial nuclear reactors. Example apparatuses may continuously insert, remove, and store irradiation targets to be converted to useable radioisotopes or other desired materials at several different origin and termination points accessible outside an access barrier such as a containment building, drywell wall, or other access restriction preventing access to instrumentation tubes during operation of the nuclear plant.

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Номер записи: 8
11-07-2013 дата публикации

SYSTEMS AND METHODS FOR HARVESTING AND STORING MATERIALS PRODUCED IN A NUCLEAR REACTOR

Номер: US20130177118A1
Автор: Brittingham Martin W., Dayal Yogeshwar, Heinold Mark R.
Принадлежит: GE-HITACHI NUCLEAR ENERGY AMERICAS, LLC

Systems produce desired isotopes through irradiation in nuclear reactor instrumentation tubes and deposit the same in a robust facility for immediate shipping, handling, and/or consumption. Irradiation targets are inserted and removed through inaccessible areas without plant shutdown and placed in the harvesting facility, such as a plurality of sealable and shipping-safe casks and/or canisters. Systems may connect various structures in a sealed manner to avoid release of dangerous or unwanted matter throughout the nuclear plant, and/or systems may also automatically decontaminate materials to be released. Useable casks or canisters can include plural barriers for containment that are temporarily and selectively removable with specially-configured paths inserted therein. Penetrations in the facilities may limit waste or pneumatic gas escape and allow the same to be removed from the systems without over-pressurization or leakage. Methods include processing irradiation targets through such systems and securely delivering them in such harvesting facilities. 1. A system for delivering and harvesting irradiation targets through a nuclear reactor , the system comprising:a loading/offloading system providing irradiation targets, wherein the loading/offloading system is outside of an access barrier of the nuclear reactor;a penetration pathway connecting the loading/offloading system to one of a plurality of instrumentation tubes extending into the nuclear reactor inside the access barrier, wherein the penetration pathway is traversable by the irradiation targets to the instrumentation tube; anda harvesting terminal connected to the penetration pathway via the loading / offloading system such that irradiation targets may be deposited in the harvesting terminal from the instrumentation tube.2. The system of claim 1 , wherein the harvesting terminal includes at least one storage cask claim 1 , and wherein the storage cask is connected to the loading/offloading system via a ...

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Номер записи: 9
18-07-2013 дата публикации

DEVICE AND METHOD FOR THE PRODUCTION OF RADIOISOTOPES

Номер: US20130182807A1
Автор: Wilson Taylor Ramon
Принадлежит:

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. 1. A device for producing isotopes , the device comprising:a first chamber including an anode and at least one accelerating gas;a second chamber including at least one target gas or target liquid; anda voltage source configured to apply a voltage between the anode and the first chamber; whereina reaction of the accelerated gas is produced in the first chamber as a result of the applied voltage, the reaction resulting in a plasma; anda nuclear reaction between the plasma and the target gas is produced in the second chamber.2. The device of claim 1 , wherein the nuclear reaction results in a production of one or more isotopes.3. The device of claim 1 , whereina beam window separates the first chamber and the second chamber; andthe plasma travels from the first chamber to the second chamber through the beam window.4. The device of claim 3 , wherein the beam window comprises Beryllium.5. The device of claim 1 , wherein the second chamber includes conduits to insert or remove components of the nuclear reaction without disturbing the first chamber.6. The device of claim 1 , wherein the anode is an elongated hollow cylinder.7. The device of claim 6 , wherein the anode is covered with a thermal and electrical insulator.8. The device of claim 7 , wherein the thermal and electrical insulator comprises a glass layer.9. The device of claim 6 , whereinthe elongated anode includes a recess at a first end opposite to a second end that is coupled to the voltage source; andthe plasma is created at the first ...

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Номер записи: 10
08-08-2013 дата публикации

Method and apparatus of deactivating explosives and chemical warfare with high-energy neutrons generated from deuterium tritium fusion reaction

Номер: US20130202073A1
Автор: Panteleev Milen K., Shaban Yasser R.
Принадлежит:

A non-destructive assay of deactivation of the contents of explosives and chemical warfare on-field (and or in lab) is presented with high-energy neutrons at 14, 4 and 2 MeV. The elements and substances present in the munitions are transmuted into passive elements through neutron-alpha nuclear reactions. Deactivating of the explosives on-field is presented with a unique and compact neutron generator fueled with deuterium gas and tritium breeder. Several high explosives and chemical warfare are presented in the transmutation with physical analysis. The present method and technique can be employed on-field as an improvised explosive device and as a precise explosive device in labs and centers. 1. An apparatus of neutrons generator with tritium breeder as given by its structure; a vacuum cylinder attached to a mechanical or turbo pump , an element of feeding the first fusion fuel , an element of ionizing the fusion fuel with electrochemical apparatus porous or mesh made of platinum , an element of separating the positive and negative ions with dc voltage supplied by an external high-current power supply , an element of first accelerating grid biased by an external high-voltage dc power supply , an element of lithium grid or mish placed at the exit of the first accelerating grid , an element of inner lithium blanket circling the lithium grid , an element of second accelerating grid biased by an external dc high-voltage higher or equal to the voltage of the first accelerating grid , and element of reflecting the neutrons circling the vacuum cylinder with chopped portion , and an element of thermalizing the neutrons from 14.1 MeV to 4 MeV , and an element of thermalizing the neutrons from 14.1 MeV to 2.1 MeV.2. An apparatus of neutrons generator with the given components in any structural vacuum configuration.3. An apparatus of ionizing the fusion fuel with electrochemical technique being a part of the given neutrons generator such as gold , silver or any element or ...

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Номер записи: 11
08-08-2013 дата публикации

ADDING ENRICHMENT MODULES

Номер: US20130202385A1
Автор: Bradtke Christian, Strukamp Heinrich
Принадлежит: URENCO Limited

An apparatus configured to receive material from a first isotope enrichment module and feed the received material into a second isotope enrichment module and a first storage region of a material storage apparatus; and receive material from the second isotope enrichment module and feed the received material into a second storage region of the material storage apparatus. A corresponding method is also described and an apparatus and corresponding method for controlling feed rates of material into the storage apparatus are also described. 1. A connection apparatus configured to:receive a first material from a first isotope enrichment module and feed the received first material into a second isotope enrichment module and a first storage region of a material storage apparatus; andreceive a second material from the second isotope enrichment module and feed the received second material into a second storage region of the material storage apparatus.2. An apparatus according to claim 1 , wherein the first material is a first isotope depleted material claim 1 , the second material is a second isotope depleted material and the material storage apparatus is an isotope depleted material storage apparatus.3. An apparatus according to claim 1 , which is configured to connect a new enrichment module to an existing enrichment module by:receiving the first material from the first isotope enrichment module and feeding the received first material into an added second isotope enrichment module and a first storage region of the material storage apparatus; andreceiving the second material from the added second isotope enrichment module and feeding the received second material into a second storage region of the material storage apparatus.4. An apparatus according to ; and the second isotope enrichment module connected to receive the first material from the apparatus.5. An apparatus according to claim 1 , further comprising the material storage apparatus.6. An apparatus according to claim 5 ...

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Номер записи: 12
10-10-2013 дата публикации

METHODS OF GENERATING ENERGETIC PARTICLES USING NANOTUBES AND ARTICLES THEREOF

Номер: US20130266106A1
Автор: Cooper Christopher H., Cooper William K., Cummings Alan G., Loan James F.
Принадлежит: SELDON TECHNOLOGIES, LLC

There is disclosed a method of generating energetic particles, which comprises contacting nanotubes with a source of hydrogen isotopes, such as DO, and applying activation energy to the nanotubes. In one embodiment, the hydrogen isotopes comprises protium, deuterium, tritium, and combinations thereof. There is also disclosed a method of transmuting matter that is based on the increased likelihood of nuclei interaction for atoms confined in the limited dimensions of a nanotube structure, which generates energetic particles sufficient to transmute matter and exposing matter to be transmuted to these particles. 1. A method of generating energetic particles , said method comprising contacting nanotubes with hydrogen isotopes , and applying activation energy to said nanotubes.2. The method of claim 1 , wherein said hydrogen isotopes comprises protium claim 1 , deuterium claim 1 , tritium claim 1 , and combinations thereof.3. The method of claim 1 , wherein said hydrogen isotopes are provided from a source that is in a solid claim 1 , liquid claim 1 , gas claim 1 , plasma claim 1 , or supercritical phase.4. The method of claim 1 , wherein said hydrogen isotopes are provided from a source that are bound in a molecular structure.5. The method of claim 1 , wherein hydrogen isotopes are provided via DO.6. The method of claim 1 , wherein said activation energy comprises thermal claim 1 , electromagnetic claim 1 , or the kinetic energy of a particle.7. The method of claim 6 , wherein said electromagnetic energy comprises one or more sources chosen from x-rays claim 6 , optical photons claim 6 , y-rays claim 6 , microwave radiation claim 6 , infrared radiation claim 6 , ultraviolet radiation claim 6 , phonons claim 6 , radiation in the frequencies ranging from gigahertz to terahertz claim 6 , or combinations thereof.8. The method of claim 6 , wherein said particle containing kinetic energy is chosen from neutrons claim 6 , protons claim 6 , electrons claim 6 , beta radiation ...

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Номер записи: 13
14-11-2013 дата публикации

SYSTEM AND METHOD FOR COLLECTING 3HE GAS FROM HEAVY WATER NUCLEAR REACTORS

Номер: US20130301768A1
Автор: Didsbury Richard, Rodrigo Lakshman, Sur Bhaskar
Принадлежит:

A method of collecting He from a nuclear reactor may include the steps of a) providing heavy water at least part of which is exposed to a neutron flux of the reactor, b) providing a cover gas in fluid communication with the heavy water, c) operating the nuclear reactor whereby thermal neutron activation of deuterium in the heavy water produces tritium (H) and at least some of the tritium produces He gas by βdecay and at least a portion of the 3He gas escapes from the heavy water and mixes with the cover gas, d) extracting an outlet gas stream, the outlet gas stream comprising a mixture of the cover gas and the 3He gas and e) separating the 3He gas from the outlet gas stream. 1. A method of collecting He from a nuclear reactor , the method comprising:a. providing heavy water at least part of which is exposed to a neutron flux of the reactor;b. providing a cover gas in fluid communication with the heavy water;{'sup': 3', '3', '−', '3, 'c. operating the nuclear reactor whereby thermal neutron activation of deuterium in the heavy water produces tritium (H) and at least some of the tritium produces He gas by βdecay and at least a portion of the He gas escapes from the heavy water and mixes with the cover gas;'}{'sup': '3', 'd. extracting an outlet gas stream, the outlet gas stream comprising a mixture of the cover gas and the He gas; and'}{'sup': '3', 'e. separating the He gas from the outlet gas stream.'}2. The method of claim 1 , further comprising outputting a He gas stream for further processing.3. The method of claim 2 , further comprising treating the outlet gas stream to provide a treated cover gas stream.4. The method of claim 3 , further comprising mixing at least a portion of the treated cover gas stream into the cover gas in fluid communication with the heavy water.5. The method of claim 1 , wherein the step of extracting the outlet gas stream is performed while nuclear reactor is operating.6. The method of claim 5 , wherein the outlet gas stream is extracted ...

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Номер записи: 14
14-11-2013 дата публикации

PROCESSES, SYSTEMS, AND APPARATUS FOR CYCLOTRON PRODUCTION OF TECHNETIUM-99M

Номер: US20130301769A1
Автор: BENARD Francois, Buckley Kenneth R., DODD Maurice G., Hanemaayer Victoire, KLUG Julius Alexander, KOVACS Michael S., MANUELA Cornelia Hoehr, MORLEY Thomas J., RUTH Thomas J., Schaffer Paul, Valliant John, Zeisler Stefan K.
Принадлежит: Triumf

A process for producing technetium-99m from a molybdenum-100 metal powder, comprising the steps of: 1. A process for refining molybdenum-100 metal powders , comprising:{'sub': 2', '2, 'oxidizing a commercial-grade Mo-100 metal powder in a solution comprising about 3% to about 40% hydrogen peroxide (HO) to produce molybdenum oxide;'}{'sub': 2', '2', '2', '2, 'heating the solution comprising molybdenum oxide and HOto denature excess HO;'}drying the molybdenum oxide;{'sub': '3', 'in a first stage in an atmosphere comprising less than about 5% hydrogen, heating the dried molybdenum oxide at temperature from a range of about 300° C. to about 500° C. for a period of time from a range of about 15 minutes to about 3 hours to form MoO;'}{'sub': '2', 'in a second stage in an atmosphere comprising less than about 5% hydrogen, increasing the temperature to a range of about 600° C. to about 850° C. for a period of time from a range of about 15 minutes to about 3 hours to form MoO;'}in a third stage in an atmosphere comprising at least about 75% hydrogen, increasing the temperature to a range of about 1,000° C. to about 1,300° C. for a period of time from a range of about 15 minutes to about 3 hours to form a refined Mo-100 metal; andrecovering the refined Mo-100 metal.2. A process for producing a hardened target plate coated with a molybdenum-100 metal , comprising:suspending and intermixing a refined molybdenum-100 metal powder having grain sizes of less than about 10 microns, and a binder, in a polar organic solvent;inserting into the molybdate-100 mixture, a cathode plate comprising a transition metal and an anode plate comprising conductive metal;applying a potential from about 300 V to about 1,300 V to the anode plate and cathode plate;recovering the cathode plate from the molybdate-100 mixture; andsintering the cathode plate at a temperature from a range of about 1,200° C. to about 1,900° C. for a period of time from about 3 h to about 8 h.3. The process of claim 2 , ...

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Номер записи: 15
19-12-2013 дата публикации

Method of Producing Isotopes In A Nuclear Reactor With An Irradiation Target Retention System

Номер: US20130336436A1
Автор: ALLEN Melissa, GILMAN Nicholas, HATTON Heather, II William Earl, Russell
Принадлежит:

Example embodiments are directed to methods of producing desired isotopes in commercial nuclear reactors using instrumentation tubes conventionally found in nuclear reactor vessels to expose irradiation targets to neutron flux found in the operating nuclear reactor. Example embodiments include assemblies for retention and producing radioisotopes in nuclear reactors and instrumentation tubes thereof. Example embodiments include one or more retention assemblies that contain one or more irradiation targets and are useable with example delivery systems that permit delivery of irradiation targets. Example embodiments may be sized, shaped, fabricated, and otherwise configured to successfully move through example delivery systems and conventional instrumentation tubes while containing irradiation targets and desired isotopes produced therefrom. 1. A method of producing isotopes in a nuclear reactor with an irradiation target retention system , the method comprising:inserting at least one irradiation target into an irradiation target retention assembly, the irradiation target configured to substantially convert to a desired radioisotope when exposed to a neutron flux in the operating nuclear reactorconnecting the irradiation target retention assembly to a cable of a delivery system;driving the irradiation target retention assembly on the cable into tubing of the delivery system using a drive mechanism, the tubing being connected to an instrumentation tube of the nuclear reactor;inserting the irradiation target retention assembly on the cable into the instrumentation tube using the drive mechanism;irradiating the at least one irradiation target;removing the irradiation target retention assembly on the cable from the nuclear reactor using the drive mechanism; andharvesting the desired radioisotope from the irradiation target retention assembly.2. The method of claim 1 , wherein the inserting the irradiation target retention assembly on the cable into the instrumentation tube ...

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Номер записи: 16
19-12-2013 дата публикации

APPARATUS AND METHODS FOR TRANSMUTATION OF ELEMENTS

Номер: US20130336437A1
Автор: Dent, JR. William Vaden
Принадлежит:

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. 1. An apparatus for the generation of technetium-99m from molybdenum-98 , the apparatus comprising:a neutron generator configured to emit neutrons with a neutron output;{'sub': '1', 'a neutron moderator having a diameter Dand configured to reduce an average energy of the neutron output to produce a moderated neutron output;'}{'sub': '2', 'one or more sections having a diameter Dand comprising molybdenum-containing material configured to absorb neutrons when exposed to the moderated neutron output, the absorption of the neutrons by the molybdenum-containing material producing molybdenum-99 from molybdenum-98; and'}an extractor configured to extract technetium-99m from the one or more sections.2. The apparatus of claim 1 , wherein the neutron output comprises neutrons produced at a rate of about 1×10to about 1×10neutrons per second.3. The apparatus of claim 1 , wherein the average energy of the neutron output is about 2.4 MeV to about 14 MeV.4. The apparatus of claim 1 , wherein the neutron moderator substantially surrounds the ...

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Номер записи: 17
02-01-2014 дата публикации

Method of preparing radioisotope nanostructure with ligand-metal framework and application

Номер: US20140005407A1
Автор: Jin Ho MOON, Jong Bum Kim, Min Seok Oh, Seong-Ho Choi, Sung Hee Jung
Принадлежит: Korea Atomic Energy Research Institute KAERI

This invention relates to a method of preparing a radioisotope nanostructure having a ligand-metal framework, and a radioisotope nanostructure prepared thereby. The method of preparing the radioisotope nanostructure of the invention has a simple preparation process and can thus be applied to mass production of a radioisotope nanostructure. Also, because this radioisotope nanostructure is nano-sized spherical particles and has no reactive group, it can be easily dispersed in a fluid, and this nanostructure is physically and chemically stable and thus can be utilized as a radioisotope tracer in the fields of refineries, chemistry, cement, agriculture, water resources, marine, etc. Furthermore, this nanostructure can be used for diagnosis and/or treatment in medical fields, and can be applied to checking whether a nanomaterial is harmful. In addition, this nanostructure is expected to be applicable in a variety of fields using radioisotopes.

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Номер записи: 18
30-01-2014 дата публикации

PRODUCTION OF TECHNETIUM FROM A MOLYBDENUM METAL TARGET

Номер: US20140029710A1
Автор: Gagnon Katherine, McQuarrie Stephen, Wilson John
Принадлежит: THE GOVERNORS OF THE UNIVERSITY OF ALBERTA

Recycling of isotopically enriched molybdenum metal targets that are suitable for the large scale cyclotron production of Tc or Tc includes the charged particle irradiation of an enriched molybdenum metal target to produce a technetium isotope, separation of the technetium isotope following irradiation of the molybdenum, re-claiming the molybdenum metal and reformation of the molybdenum target for a further irradiation step. This process may then be repeated. Separation of the technetium isotope preferably is achieved by oxidative dissolution of the molybdenum thereby removing it from a target support plate, and forming molybdate and pertechnetate. The technetium isotope is isolated by various means, such as the ABEC process. To reuse the molybdenum, additional steps of isolating the molybdate and reducing it back to molybdenum metal are required. The recovered molybdenum metal may then be reformed as a target for example by pressing or pressing and sintering, followed by bonding to a target support plate. 1. A method of the preparation of a technetium isotope , comprising: separating the technetium isotope following irradiation of the molybdenum metal;', 're-claiming the molybdenum metal; and', 'reforming the molybdenum metal into a further molybdenum target for a further irradiation step by bonding the molybdenum metal to a target support., 'irradiating a molybdenum metal target with charged particles to produce a technetium isotope;'}2. The method of in which bonding the molybdenum metal to the target support comprises applying heat and pressure to a pellet of the molybdenum metal.3. The method of in which the pressure is applied under vacuum.4. The method of in which reforming the molybdenum metal comprises pressing molybdenum metal powder and sintering the resulting pressed molybdenum metal powder to produce a pellet of the molybdenum metal before bonding the molybdenum metal pellet to a support.5. The method of in which the sintering is carried out under a ...

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Номер записи: 19
01-01-2015 дата публикации

PROCESS OF GENERATING GERMANIUM

Номер: US20150003576A1
Автор: Perrigo Melissa Dianne, Pipes David Wayne, Uhland William C.
Принадлежит:

The present disclosure generally relates to a new process for generating germanium-68 from an irradiated target body. The process includes irradiation of the target body followed by various extraction techniques to generate the germanium-68. 1. A process for generating a radioisotope , the process comprising:bombarding a target body including a starting material, wherein the bombardment of the starting material produces a radioisotope within the target body;allowing the bombarded target body to decay;stripping the bombarded target body with an acidic mixture to create a stripped solution;extracting the radioisotope from the stripped solution using a non-polar solvent to remove the acidic mixture and create a non-polar solvent fraction including the radioisotope;washing the non-polar solvent fraction including the radioisotope; and,extracting the radioisotope from the non-polar solvent fraction using water.2. The process of claim 1 , wherein the radioisotope is germanium-68.3. The process of claim 1 , wherein the starting material is an alloy comprising gallium.4. The process of claim 3 , wherein the alloy includes a metal selected from the group consisting of nickel claim 3 , indium claim 3 , tin claim 3 , iron claim 3 , ruthenium claim 3 , osmium claim 3 , chromium claim 3 , rhenium claim 3 , molybdenum claim 3 , tungsten claim 3 , manganese claim 3 , cobalt claim 3 , rhodium and combinations thereof.5. The process of claim 3 , wherein the alloy includes from about 10% to about 80% gallium claim 3 , by weight of the alloy.6. The process of claim 3 , wherein the alloy includes gallium and nickel.7. The process of claim 6 , wherein the alloy includes from about 60% to about 75% gallium and from about 25% to about 40% nickel claim 6 , by weight of the alloy.8. The process of claim 1 , wherein the acidic mixture includes hydrochloric acid and nitric acid.9. The process of claim 1 , wherein the acidic mixture includes copper (II) nitrate trihydrate and nitric acid.10. ...

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Номер записи: 20
05-01-2017 дата публикации

TARGET ASSEMBLY AND ISOTOPE PRODUCTION SYSTEM HAVING A VIBRATING DEVICE

Номер: US20170004897A1
Автор: Eriksson Tomas, Holmgren Bert
Принадлежит:

Target assembly for an isotope production system. The target assembly includes a target body having a production chamber and a beam cavity that is adjacent to the production chamber. The production chamber is configured to hold a target liquid. The beam cavity opens to an exterior of the target body and is configured to receive a particle beam that is incident on the production chamber. The target assembly also includes a vibrating device that is secured to the target body. The vibrating device is configured to cause vibrations that are experienced within the production chamber. 1. A target assembly for an isotope production system , the target assembly comprising:a target body having a production chamber and a beam cavity that is adjacent to the production chamber, the production chamber configured to hold a target liquid, the beam cavity opening to an exterior of the target body and being configured to receive a particle beam that is incident on the production chamber; anda vibrating device secured to the target body, the vibrating device configured to cause vibrations that are experienced within the production chamber,2. The target assembly of claim 1 , wherein the target body includes first and second body sections that are secured to each other and have fixed positions relative to each other claim 1 , the production chamber being defined by at least one of the first body section or the second body section claim 1 , the vibrating device being secured to at least one of the first body section or the second body section.3. The target assembly of claim 1 , wherein the vibrating device is secured to a designated surface of the target body claim 1 , the target body comprising a solid material claim 1 , wherein a continuous path of the solid material exists between the designated face and a surface that defines the production chamber.4. The target assembly of claim 3 , wherein a cooling channel extends through the solid material of the target body and proximate to the ...

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Номер записи: 21
13-01-2022 дата публикации

METHOD FOR PREPARING AT LEAST ONE GENERATOR WITH A HIGH RADIUM-228 CONTENT

Номер: US20220013246A1
Автор: Dureau Rémy, Torgue Julien
Принадлежит:

A method for preparing one or more generators with a high radium-228 content from an aqueous solution comprising thorium-232 and radium-228. The generator(s) can be used, in particular, for producing thorium-228, from which radium-224, then lead-212 and bismuth-212 can be obtained. The method and the generator(s) that it can be used to prepare are therefore applicable, in particular, in the manufacture of radiopharmaceuticals made from lead-212 or bismuth-212, which can be used in nuclear medicine and, in particular, in targeted alpha radiotherapy for the treatment of cancers. 1. A method for preparing at least one generator comprising radium-228 from an aqueous solution A1 comprising thorium-232 and radium-228 , comprising at least the steps of:a) circulating in a first chromatography column a volume V1 of the aqueous solution A1, the first chromatography column comprising a first stationary phase consisting of a solid material which selectively retains radium with respect to thorium;b) washing at least once the first stationary phase with an aqueous solution A2;c) eluting the radium-228 from the first stationary phase with a volume V3 of an aqueous solution A3 comprising an agent complexing radium-228, the volume V3 being between 0.005% and 1% of the volume V1 of the aqueous solution A1 having circulated in the first chromatography column, whereby an aqueous solution A4 which comprises radium-228 complexes is obtained;d) dissociating the radium-228 complexes present in the aqueous solution A4 by modifying a pH of the aqueous solution A4, whereby an aqueous solution A5 comprising the radium-228 in a decomplexed form is obtained;e) loading a second chromatography column with the aqueous solution A5, the second chromatography column comprising a second stationary phase consisting of a same material as the first stationary phase; andf) washing at least once the second stationary phase with an aqueous solution A6, whereby the at least one generator is obtained.2. The ...

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Номер записи: 22
14-01-2016 дата публикации

Targeted Isotope Production System

Номер: US20160012928A1
Автор: Congedo Thomas V., Guler Cenk, Heibel Michael D., Sutton Joanna C.
Принадлежит: WESTINGHOUSE ELECTRIC COMPANY LLC

A system and method for employing the in-core movable detectors of a commercial nuclear powered electric generating facility to transmute a user-specified target material into a desired isotope. The process is conducted remotely resulting in a shielded end product available for shipment for further processing. 1. A targeted isotope production system for a moveable in-core nuclear reactor detector system for mapping temperature or neutron flux in a core of a nuclear reactor , the in-core nuclear reactor detector system having a first multiple path linear transfer device that upon command , receives a detector and feeds the detector into a second multiple path linear transfer device that feeds the detector along a desired path to a selected radial core location , the second multiple path linear transfer device is alternately operable , upon command , to feed the detector through a storage conduit to a separate storage location , the targeted isotope production system comprising:a target material container drive assembly that is connected to an input to the first multiple path linear transfer device;a third multiple path linear transfer device that has an input that is connected to the storage conduit and upon command is operable to connect the storage conduit to one of at least two outlets on the third multiple path linear transfer device, a first of the two outlets is connected to the separate storage location and a second outlet; anda target material storage container is connected to a second of the two outlets on the third multiple path linear transfer device.2. The target isotope production system of wherein the target material storage container has a quick disconnect coupling connecting it to the second outlet.3. The target isotope production system of wherein the target material container drive assembly is a cable drive system to which the target material is attached.4. The target isotope production system of wherein the target material container drive assembly ...

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Номер записи: 23
14-01-2021 дата публикации

SYSTEMS AND TECHNIQUES FOR CALIBRATING RADIOISOTOPE DELIVERY SYSTEMS WITH A GAMMA DETECTOR

Номер: US20210012917A1
Автор: NUNN Adrian
Принадлежит:

An infusion system may include a radioisotope generator that generates a radioactive eluate via elution, a beta detector, a gamma detector, and a controller. The beta detector and the gamma detector may be positioned to measure beta emissions and gamma emissions, respectively, emitted from the radioactive eluate. In some examples, the controller is configured to calibrate the infusion system using the gamma detector. For example, the controller may generate a radioactive eluate and measure the activity of the radioactive eluate using both the beta detector and the gamma detector. The high accuracy of the activity measured by the gamma detector may be used to calibrate the infusion system. In subsequent use, the infusion system calibrated using the gamma detector may adjust measurements made to monitor and/or control patient infusion procedures. 1. An infusion system comprising:a frame that carries a beta detector, a gamma detector, and a controller communicatively coupled to the beta detector and the gamma detector,wherein the frame is further configured to receive a strontium-rubidium radioisotope generator that generates a radioactive eluate via elution,the beta detector is positioned to measure beta emissions emitted from the radioactive eluate,the gamma detector is positioned to measure gamma emissions emitted from the radioactive eluate, andthe controller is configured to determine an activity of the radioactive eluate based on the beta emissions measured by the beta detector, determine an activity of the radioactive eluate based on the gamma emissions measured by the gamma detector, and calibrate the infusion system based on comparison of the activity of the radioactive eluate measured by the beta detector to the activity of the radioactive eluate measured by the gamma detector.2. The infusion system of claim 1 , wherein controller is configured to determine of an activity of rubidium in the radioactive eluate based on the beta emissions measured by the beta ...

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Номер записи: 24
16-01-2020 дата публикации

SHIELDING ASSEMBLY FOR A RADIOISOTOPE DELIVERY SYSTEM HAVING MULTIPLE RADIATION DETECTORS

Номер: US20200016284A1
Автор: CHERUNDOLO Brian, DENNIS Joseph, MOYERS Clif, NUNN Adrian, SCHIMMOELLER Andrew
Принадлежит:

A shielding assembly may be used in a nuclear medicine infusion system that generates and infuse radioactive liquid into a patient undergoing a diagnostic imaging procedure. In some examples, the shielding assembly has multiple compartments each formed of a shielding material providing a barrier to radioactive radiation. For example, the shielding assembly may have a first compartment configured to receive a radioisotope generator that generates a radioactive eluate via elution, a second compartment configured to receive a beta detector, and a third compartment configured to receive a gamma detector. In some examples, the compartments are arranged to minimize background radiation emitted by the radioisotope generator and detected by the gamma detector to enhance the quality of the measurements made by the gamma detector. 1. A system comprising: a first compartment configured to receive a radioisotope generator that generates a radioactive eluate via elution;', 'a second compartment configured to receive a beta detector, and', 'a third compartment configured to receive a gamma detector., 'a shielding assembly that has a plurality of compartments each formed of a shielding material providing a barrier to radioactive radiation, comprising2. The system of claim 1 , wherein the third compartment is configured to receive an eluate-receiving container such that both the gamma detector and the eluate-receiving container can be positioned in the third compartment.3. The system of claim 2 , wherein the third compartment comprises a sidewall defining an opening through which the eluate-receiving container can be inserted.4. The system of claim 3 , wherein the gamma detector is positioned to detect gamma emissions emitted by a static portion of the radioactive eluate received by the eluate-receiving container.5. The system of claim 3 , further comprising a removable insert positioned in the opening claim 3 , wherein the removable insert defines a cavity configured to receive ...

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Номер записи: 25
21-01-2016 дата публикации

METHOD AND SYSTEM FOR PROVIDING FUEL IN A NUCLEAR REACTOR

Номер: US20160019985A1
Автор: Hyde Roderick A., Ishikawa Muriel Y., JR. Lowell L., Myhrvold Nathan P., Wood
Принадлежит: SEARETE LLC

Exemplary embodiments provide automated nuclear fission reactors and methods for their operation. Exemplary embodiments and aspects include, without limitation, re-use of nuclear fission fuel, alternate fuels and fuel geometries, modular fuel cores, fast fluid cooling, variable burn-up, programmable nuclear thermostats, fast flux irradiation, temperature-driven Surface area/volume ratio neutron absorption, low coolant temperature cores, refueling, and the like.

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Номер записи: 26
21-01-2016 дата публикации

Apparatus and Method for Stripping Tritium from Molten Salt

Номер: US20160019993A1
Автор: Holcomb David E., Wilson Dane F.
Принадлежит:

A method of stripping tritium from flowing stream of molten salt includes providing a tritium-separating membrane structure having a porous support, a nanoporous structural metal-ion diffusion barrier layer, and a gas-tight, nonporous palladium-bearing separative layer, directing the flowing stream of molten salt into contact with the palladium-bearing layer so that tritium contained within the molten salt is transported through the tritium-separating membrane structure, and contacting a sweep gas with the porous support for collecting the tritium.

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Номер записи: 27
18-01-2018 дата публикации

IRRADIATION TARGET HANDLING DEVICE

Номер: US20180019031A1
Автор: Heibel Michael D., McArdle Matthew D.
Принадлежит: WESTINGHOUSE ELECTRIC COMPANY LLC

A device that will enable material to be irradiated as needed to produce a desired transmutation product inside the core of a nuclear reactor. The device provides a means for monitoring neutron flux in the vicinity of the material being irradiated to allow determination of the amount of transmutation product being produced. The device enables the irradiated material to be inserted into the reactor and held in place at desired axial positions and to be withdrawn from the reactor when desired without shutting down the reactor. The majority of the device may be re-used for subsequent irradiations. The device also enables the simple and rapid attachment of unirradiated target material to the portion of the device that transmits the motive force to insert and withdraw the target material into and out of the reactor and the rapid detachment or the irradiated material from the device for processing. 1. An irradiation target handling device having an isotope production cable assembly comprising:a drive cable constructed to be compatible with the drive mechanism requirements for an existing nuclear reactor drive mechanism for cable drive systems used to insert and withdraw sensors within nuclear reactor cores, having a spirally wound, self-powered radiation detector wrapped around an axial length of the drive cable proximate one end designed to be inserted into a flux thimble in a core of a nuclear reactor with a length of the self-powered radiation detector sufficient to provide a preselected signal output with a minimal axial length from end to end of the spiral, so the self-powered radiation detector provides an output indicative of reactor flux at the self-powered radiation detector position in a reactor core to enable an axial position of a target material supported by and proximate the one end of the drive cable to be optimized;a one of a female end or male end of a quick disconnect coupling attached to the one end of the drive cable; anda target holder element cable ...

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Номер записи: 28
18-01-2018 дата публикации

METHOD OF PREPARING OF IRRADIATION TARGETS FOR RADIOISOTOPE PRODUCTION AND IRRADIATION TARGET

Номер: US20180019032A1
Автор: Schmid Wolfgang, Schuster Beatrice
Принадлежит:

The invention provides a method of preparing irradiation targets for radioisotope production in instrumentation tubes of a nuclear power reactor, the method comprising the steps of: providing a powder consisting of an oxide of a rare earth metal having a purity of greater than 99% and, optionally, an organic binder; pelletizing the powder and optionally the organic binder to form a substantially spherical green body having a diameter of from between 1 to 10 mm; and sintering the spherical green body in solid phase at a temperature of at least 70 percent of a solidus temperature of the rare earth metal oxide powder and for a time sufficient to form a round sintered rare earth metal oxide target having a sintered density of at least 80 percent of the theoretical density. 1. A method for preparing irradiation targets for radioisotope production in instrumentation tubes of a nuclear power reactor , the method comprising the steps of:providing a powder consisting of an oxide of a rare earth metal having a purity of greater than 99% and, optionally, an organic binder;pelletizing the powder and optionally the organic binder to form a substantially spherical green body having a diameter of from between 1 to 10 mm; andsintering the green body in solid phase at a temperature of at least 70 percent of a solidus temperature of the rare earth metal oxide powder and for a time sufficient to form a substantially spherical sintered rare earth metal oxide target having a sintered density of at least 80 percent of the theoretical density.2. The method of wherein the rare earth metal is selected from the group consisting of Nd claim 1 , Sm claim 1 , Y claim 1 , Dy claim 1 , Ho claim 1 , Er claim 1 , Tm claim 1 , Yb and Lu.3. The method of wherein the rare earth metal is Sm claim 2 , Y claim 2 , Ho or Yb.4. The method of wherein the powder of the rare earth metal oxide has a purity of greater than 99 percent.5. The method of claim wherein the rare earth metal is monoisotopic.6. The ...

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Номер записи: 29
18-01-2018 дата публикации

METHOD OF PREPARING OF IRRADIATION TARGETS FOR RADIOISOTOPE PRODUCTION AND IRRADIATION TARGET

Номер: US20180019033A1
Автор: Bathelt Robert, Goesswein Karl, Schuster Beatrice
Принадлежит: AREVA GMBH

The invention provides a method of preparing irradiation targets for radioisotope production in instrumentation tubes of a nuclear power reactor, the method comprising the steps of: providing a powder of an oxide of a rare earth metal having a purity of greater than 99%; consolidating the powder in a mold to form a round green body having a green density of at least 50 percent of the theoretical density; and sintering the spherical green body in solid phase at a temperature of at least 70 percent of a solidus temperature of the rare earth metal oxide powder and for a time sufficient to form a round sintered rare earth metal oxide target having a sintered density of at least 80 percent of the theoretical density. 1. A method for preparing irradiation targets for radioisotope production in instrumentation tubes of a nuclear power reactor , the method comprising the steps of:providing a powder of an oxide of a rare earth metal having a purity of greater than 99%;consolidating the powder in a mold to form a substantially spherical green body having a green density of at least 50 percent of the theoretical density; andsintering the green body in solid phase at a temperature of at least 70 percent of a solidus temperature of the rare earth metal oxide powder and for a time sufficient to form a substantially spherical sintered rare earth metal oxide target having a sintered density of at least 80 percent of the theoretical density.2. The method of wherein the rare earth metal is selected from the group consisting of Nd claim 1 , Sm claim 1 , Y claim 1 , Dy claim 1 , Ho claim 1 , Er claim 1 , Tm claim 1 , Yb and Lu.3. The method of wherein the rare earth metal is Sm claim 2 , Y claim 2 , Ho or Yb.4. The method of wherein the powder of the rare earth metal oxide has a purity of greater than 99 percent.5. The method of wherein the rare earth metal is monoisotopic.6. The method of wherein the powder is consolidated at a pressure in a range of between 1 and 600 MPa.7. The ...

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Номер записи: 30
18-01-2018 дата публикации

Production of n-13 ammonia radionuclide

Номер: US20180019034A1
Автор: Francis Y. Tsang
Принадлежит: GLOBAL MEDICAL ISOTOPE SYSTEMS LLC

A method of producing 13 N-ammonia for use in medical imaging is provided, which includes irradiating 14 N (having a natural abundance of 99.64%) with a collimated bremsstrahlung radiation (gamma-ray beam) obtained by directing high-energy electrons onto a high-Z converter. The 14 N to be irradiated may be in the form of liquid ammonia ( 14 NH 3 ) or ammonia gas to directly produce 13 N-ammonia ( 13 NH 3 ) or in the form of liquid nitrogen to indirectly produce 13 N-ammonia through conversion of the irradiated liquid nitrogen (N 2 ) via known conversion processes to 13 N-ammonia. The photons have an energy level above the threshold of the 14 N(γ,n) 13 N reaction (about 10.5 MeV).

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Номер записи: 31
17-01-2019 дата публикации

PROCESS OF GENERATING GERMANIUM

Номер: US20190019591A1
Автор: Perrigo Melissa Dianne, Pipes David Wayne, Uhland William C.
Принадлежит:

The present disclosure generally relates to a new process for generating germanium-68 from an irradiated target body. The process includes irradiation of the target body followed by various extraction techniques to generate the germanium-68. 1. A process for generating a radioisotope , the process comprising:bombarding a target body including a starting material, wherein the bombardment of the starting material produces a radioisotope within the target body;{'sub': '3', 'allowing the bombarded target body to decay; stripping the bombarded target body with an acidic mixture to create a stripped solution, wherein the acidic mixture includes (a) copper (II) nitrate trihydrate and nitric acid, or (b) 3 M to 6 M hydrochloric acid (HCl) and 6 M to 15 M nitric acid (HNO);'}extracting the radioisotope from the stripped solution using a non-polar solvent to remove the acidic mixture and create a non-polar solvent fraction including the radioisotope;washing the non-polar solvent fraction including the radioisotope; and,extracting the radioisotope from the non-polar solvent fraction using water.2. The process of claim 1 , wherein the radioisotope is germanium-68.3. The process of claim 1 , wherein the starting material is an alloy comprising gallium.4. The process of claim 3 , wherein the alloy includes a metal selected from the group consisting of nickel claim 3 , indium claim 3 , tin claim 3 , iron claim 3 , ruthenium claim 3 , osmium claim 3 , chromium claim 3 , rhenium claim 3 , molybdenum claim 3 , tungsten claim 3 , manganese claim 3 , cobalt claim 3 , rhodium and combinations thereof.5. The process of claim 3 , wherein the alloy includes from about 10% to about 80% gallium claim 3 , by weight of the alloy.6. The process of claim 3 , wherein the alloy includes gallium and nickel.7. The process of claim 6 , wherein the alloy includes from about 60% to about 75% gallium and from about 25% to about 40% nickel claim 6 , by weight of the alloy.8. The process of claim 1 , ...

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Номер записи: 32
16-01-2020 дата публикации

Solution Target for Cyclotron Production of Radiometals

Номер: US20200020457A1
Автор: Byrne John, DeGrado Timothy R., Pandey Mukesh K.
Принадлежит:

Methods of producing and isolating Ga, Zr, Cu, Zn, Y, Cu, Tc, Ti, N, Mn, or Sc and solution targets for use in the methods are disclosed. The methods of producing Ga, Zr, Cu, Zn, Y, Cu, Tc, Ti, N, Mn, or Sc include irradiating a closed target system with a proton beam. The system can include a solution target. The methods of producing isolated Ga, Zr, Cu, Zn, Y, Cu, Tc, Ti, Mn, or Sc further include isolating Ga, Zr, Cu, Zn, Y, Cu, Tc, Ti, Mn, or Sc by ion exchange chromatography. An example target includes a target body including a target cavity for receiving the target material; a housing defining a passageway for directing a particle beam at the target cavity; a target window for covering an opening of the target cavity; and a coolant gas flow path disposed in the passageway upstream of the target window. 1. A method for synthesizing a resin for trapping an analyte , the method comprising:(a) providing a cationic exchange resin having carboxylate groups;(b) activating carboxylate groups of the cationic exchange resin with an activating agent; and(c) reacting activated carboxylate groups of the cationic exchange resin with a hydroxylamine salt in the presence of a base to produce the resin.2. The method of wherein:the activating agent comprises an alkyl ester of chloroformic acid.3. The method of wherein:the activating agent comprises methyl chloroformate.4. The method of wherein:the base comprises an amine.5. The method of wherein:the base is a tertiary amine.6. The method of wherein:the base is triethylamine.7. The method of wherein:the hydroxylamine salt is hydroxylamine hydrochloride.8. The method of wherein:step (b) is undertaken in the presence of a solvent for the activating agent.9. The method of wherein:the solvent comprises a halogenated alkane.10. The method of wherein:the solvent is dichloromethane.11. The method of further comprising:removing the solvent under vacuum.12. The method of wherein:the analyte is a radionuclide.13. The method of wherein:{' ...

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Номер записи: 33
21-01-2021 дата публикации

EARLY DETECTION OF RADIOISOTOPE GENERATOR END LIFE

Номер: US20210020322A1
Автор: NUNN Adrian
Принадлежит:

An infusion system () including a radioisotope generator () that generates a radioactive eluate via an elution, an activity detector () configured to measure an activity of a first radioisotope in the radioactive eluate generated by the radioisotope generator, and a controller (). The controller can track a cumulative volume of radioactive eluate generated by the radioisotope generator and also track the activity of the first radioisotope in the radioactive eluate generated by the radioisotope generator. The controller can determine a predicted volume of the radioactive eluate generated by the radioisotope generator at which the activity of the first radioisotope in the radioactive eluate will reach a threshold based on the tracked cumulative volume of the radioactive eluate and the tracked activity of the first radioisotope. This information can be useful for proactively removing the radioisotope generator from service and/or replacing the radioisotope generator with a fresh generator. 1. An infusion system comprising:a radioisotope generator that generates a radioactive eluate via an elution,an activity detector configured to measure an activity of a first radioisotope in the radioactive eluate generated by the radioisotope generator; and track a cumulative volume of radioactive eluate generated by the radioisotope generator;', 'track the activity of the first radioisotope in the radioactive eluate generated by the radioisotope generator; and', 'determine a predicted volume of the radioactive eluate generated by the radioisotope generator at which the activity of the first radioisotope in the radioactive eluate will reach a threshold based on the tracked cumulative volume of the radioactive eluate and the tracked activity of the first radioisotope., 'a controller configured to2. The infusion system of claim 1 , wherein the radioactive eluate generated by the radioisotope generator comprises a second radioisotope with a shorter radioactive half-life than the first ...

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Номер записи: 34
21-01-2021 дата публикации

Thorium Molten Salt System Using Internally Generated Proton-Induced Neutrons

Номер: US20210020323A1
Автор: Hassan Yassin A., Shao Lin
Принадлежит: Texas Thorium, LLC

A method of generating power using a Thorium-containing molten salt fuel is disclosed. One example includes the steps of providing a vessel containing a molten salt fuel, generating a proton beam externally to the vessel, where the externally generated proton beam being of an energy level sufficient to interact with the salt in the vessel to produce a (p, n) reaction resulting in the generation of a neutron at the first energy level. Neutrons generated within the vessel through the (p, n) reactions caused by the externally generated proton's interaction with the at least one salt are utilized to produce a fission reaction where the fission reaction increases the heat content of the molten salt within the vessel. In the example, a heat exchanger is used to extract heat from the molten salt within the vessel and power is generated from the extracted heat. 1. A method of generating power using a Thorium-containing molten salt fuel , the method comprising the steps of:providing a vessel containing a molten salt fuel, the molten salt fuel comprising Thorium and at least one salt containing an atom capable of interacting with a proton of sufficient energy to produce a (p, n) reaction resulting in the generation of a neutron at a first energy level;providing a lid to the vessel, the lid comprising a top and a bottom with at least one opening through the lid containing an impeller pump assembly configured to recirculate the molten salt fuel in the vessel, at least two openings through the lid containing input and output piping for a sealed heat exchanger coil positioned adjacent the bottom of the lid, and at least one opening through which is a window configured to permit the passage of protons;attaching the lid to the vessel;generating a proton beam externally to the vessel, the externally generated proton beam being of an energy level sufficient to interact with the at least one salt in the vessel to produce a (p, n) reaction resulting in the generation of a neutron at ...

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Номер записи: 35
21-01-2021 дата публикации

Thorium Molten Salt System Using Internally Generated Proton-Induced Neutrons

Номер: US20210020324A1
Автор: Hassan Yassin A., Shao Lin
Принадлежит: Texas Thorium, LLC

A method of generating power using a Thorium-containing molten salt fuel is disclosed. One example of the disclosed method includes the steps of providing a vessel containing a molten salt fuel, the molten salt fuel comprising Thorium and at least one salt containing a nucleus capable of interacting with a proton of sufficient energy to produce a (p, n) reaction resulting in the generation of a neutron at a first energy level and generating a proton beam externally to the vessel, where the externally generated proton beam being of an energy level sufficient to interact with the at least one salt in the vessel to produce a (p, n) reaction resulting in the generation of a neutron at the first energy level. In the example, the externally generated proton beam is directed into the vessel such that at least some protons forming the beam will interact with an atom forming a part of the at least one salt contained in the vessel to causing interaction between the externally generated proton beam and the at least one salt contained in the vessel to produce (p, n) reactions resulting in the generation of neutrons within the vessel and an absorption reaction involving the generated neutrons and Thorium within the vessel. Neutrons generated within the vessel through the (p, n) reactions caused by the externally generated proton's interaction with the at least one salt are utilized to produce a fission reaction where the fission reaction increases. the heat content of the molten salt within the vessel. In the example, a heat exchanger is used to extract heat from the molten salt within the vessel and power is generated from the extracted heat. 1. A method for generating heat in a Thorium containing molten salt , the method comprising the steps of:providing a molten salt assembly comprising a main body, a lid, a tubular member positioned inside the main body, and a quantity of Thorium-containing molten salt within the main body;generating a proton beam having an average energy ...

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Номер записи: 36
25-01-2018 дата публикации

RADIOISOTOPE RECOVERY

Номер: US20180025801A1
Автор: Alexander Richard, Archibald Stephen James, Brown Nathan Joel, Haswell Stephen John, He Ping, Pamme Nicole, Tarn Mark Duncan
Принадлежит:

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 (). The radioisotope may subsequently be used in the preparation of radiopharmaceuticals. 1. A method for separating and recovering a radioisotope from an aqueous solution comprising the radioisotope , the method comprising:using a microfluidic device comprising a chamber;flowing the aqueous solution to the chamber, the chamber comprising a first electrode and a second electrode;generating a first electric field between the first and second electrodes, thereby trapping the radioisotope on the first electrode;flowing an organic-based solution to the chamber comprising the first and the second electrodes; andgenerating a second electric field between the first and the second electrodes;wherein the second electric field has an opposing polarity to the first electric field, thereby releasing the radioactive isotope from the first electrode into the organic-based solution; andwherein the first electrode is formed from a carbon rod or section thereof.2. The method of claim 1 , further comprising one or more of the features selected from:flowing the aqueous solution at a flow rate of at least 0.1 mL/min;flowing the organic-based solution at a flow rate of at least 0.05 mL/min;applying a voltage of no greater than 30 V across the first and second electrodes to generate the first electric field; andapplying a voltage of no greater than 10 V across the first and second electrodes to generate the second electric field.35-. (canceled)6. The method of claim 1 , wherein the chamber has a volume of no greater than approximately 50 μL.7. The method of claim 1 , wherein the first electrode has a flat surface comprising a plurality of recesses and/or the first electrode has a polished ...

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Номер записи: 37
25-01-2018 дата публикации

RADIONUCLIDE GENERATION SYSTEM

Номер: US20180025802A1
Автор: ARNDT Oliver, JAAFAR Leila, RICHTER Thomas Fabian, STOLL Uwe, WISTUBA Lothar
Принадлежит:

A radionuclide generation system comprises a tube system configured to permit insertion and removal of irradiation targets into an instrumentation finger of a nuclear reactor, and an irradiation target drive system configured to insert the irradiation targets into the instrumentation finger and to remove the irradiation targets from the instrumentation finger. The radionuclide generation system further comprises an instrumentation and control unit which is linked to an online core monitoring system and being configured to calculate an optimum irradiation time for the irradiation targets based on the actual state of the reactor as provided by the online core monitoring system. 1. A radionuclide generation system , the system comprising:a tube system configured to permit insertion and removal of irradiation targets into an instrumentation finger of a nuclear reactor,an irradiation target drive system configured to insert the irradiation targets into the instrumentation finger and to remove the irradiation targets from the instrumentation finger, andan instrumentation and control unit,the instrumentation and control unit being linked to an online core monitoring system and being configured to calculate an optimum irradiation time for the irradiation targets based on the actual state of the reactor as provided by the online core monitoring system.2. The radionuclide generation system according to claim 1 , wherein information provided by the online core monitoring system to the instrumentation and control unit includes at least one of: neutron flux claim 1 , activation values from an existing ball measuring system claim 1 , burn-up claim 1 , reactor power claim 1 , loading claim 1 , rod position(s) claim 1 , flow rate claim 1 , inlet-temperature claim 1 , pressure claim 1 , time synchronization.3. The radionuclide generation system according to claim 1 , wherein further parameters are calculated by the instrumentation and control unit from the information provided by ...

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Номер записи: 38
25-01-2018 дата публикации

IRRADIATION TARGET PROCESSING SYSTEM

Номер: US20180025803A1
Автор: JAAFAR Leila, Kannwischer Wilfried, RICHTER Thomas Fabian, Sykora Alexander
Принадлежит:

An irradiation target processing system for insertion and retrieving irradiation targets into and from an instrumentation tube in a nuclear reactor core comprises, a target retrieving system, target insertion system and transport gas supply system, mounted on a movable support, wherein: the target retrieving system comprises a target exit port coupled to a target storage container and exhaust system; the target insertion system comprises a target filling device, target retention tubing with target supply junction connectable to the instrumentation tube, and a target diverter coupled to the target filling device, target retention tubing and target retrieving system; and the transport gas supply system comprises a first gas supply tubing coupled to the exit port of the target retrieving system, a second gas supply tubing coupled to a junction for supplying gas to the instrumentation tube, and a transport gas supply junction coupled to the first and second gas supply tubing. 120-. (canceled)21. An irradiation target processing system for insertion and retrieving irradiation targets into and from an instrumentation tube in a nuclear reactor core , the system comprising:a target retrieving system comprising a target exit port configured to be coupled to a target storage container and an exhaust system;a target insertion system comprising a target filling device, a target retention tubing, a target diverter coupled to the target filling device, the target retention tubing and the target retrieving system, and a target supply junction at the target retention tubing, wherein the target supply junction is configured to be connected to the instrumentation tube; anda transport gas supply system comprising a first gas supply tubing, a second gas supply tubing, and a transport gas supply junction coupled to the first and second gas supply tubing, wherein the first gas supply tubing is coupled to the exit port of the target retrieving system, and the second gas supply tubing is ...

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Номер записи: 39
10-02-2022 дата публикации

TECHNETIUM 99M ISOLATION SYSTEM AND TECHNETIUM 99M ISOLATION METHOD

Номер: US20220044836A1
Автор: TAKAHASHI Naruto
Принадлежит:

An initial introduction control part introduces an aqueous solution containing molybdenum 99 and technetium 99m, and an organic solvent being capable of dissolving the technetium 99m into an extraction tank. A micro-mixing control part micro-mixes the aqueous solution and the organic solvent by heating and stirring a mixed solution of the aqueous solution and the organic solvent introduced into the extraction tank with a heater, while applying ultrasonic to the mixed solution. A separation control part separates the mixed solution micro-mixed into two phases of aqueous solution and an organic solvent. A taking-out introduction control part passes the organic solvent separated into two phases through an adsorption column be capable of adsorbing molybdenum 99 and introduces the organic solvent into an evaporation elution tank. An evaporation control part evaporates the organic solvent and leaves residue by reducing pressure inside the evaporation elution tank and heating the organic solvent introduced into the evaporation elution tank with a heater, while applying ultrasonic to the organic solvent. An elution control part introduces physiological saline solution into the residue and elutes technetium 99m into the physiological saline solution from the residue. 1. A technetium 99m isolation system comprising:an initial introduction control part introducing an aqueous solution containing molybdenum 99 and technetium 99m, and an organic solvent being capable of dissolving the technetium 99m into an extraction tank;a micro-mixing control part micro-mixing the aqueous solution and the organic solvent by heating and stirring a mixed solution of the aqueous solution and the organic solvent introduced into the extraction tank with a heater, while applying ultrasonic to the mixed solution;a separation control part separating the mixed solution micro-mixed into two phases of aqueous solution and an organic solvent;a taking-out introduction control part passing the organic ...

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Номер записи: 40
29-01-2015 дата публикации

NUCLIDE TRANSMUTATION METHOD AND NUCLIDE TRANSMUTATION DEVICE

Номер: US20150030115A1
Автор: Itou Takehiko, Iwamura Yasuhiro, Muta Kenji, Tsuruga Shigenori
Принадлежит: MITSUBISHI HEAVY INDUSTRIES, LTD.

A nuclide transmutation device and method which enable nuclide transmutation to be performed in a small-scale device compared with large-scale devices are disclosed. The device comprises a structure, and high and low deuterium concentration units are disposed on either side of the structure so as to sandwich the structure therebetween, wherein an electrolytic solution containing heavy water is supplied to the high deuterium concentration unit and is electrolyzed to generate deuterium, thereby producing a state of high deuterium concentration near the high deuterium concentration unit side surface and placing the low deuterium concentration unit in a state of low deuterium concentration relative to the high deuterium concentration unit, causing the deuterium to penetrate through the structure from the high deuterium concentration unit toward the low deuterium concentration unit, and subjecting a substance to nuclide transmutation by reaction with the deuterium.

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Номер записи: 41
23-01-2020 дата публикации

TARGET IRRADIATION SYSTEMS FOR THE PRODUCTION OF RADIOISOTOPES

Номер: US20200027618A1
Автор: Fisher Benjamin D., Onderwater Thomas G.
Принадлежит:

A target irradiation system including an irradiated target removal system having a body defining a central bore, an elevator received within the central bore, and a docking surface for placing the irradiated target removal system in fluid communication with a vessel penetration of a reactor. A target canister slidably receives the radioisotope target therein, and the elevator is configured to receive the target canister. The elevator is lowered into the reactor when irradiating the radioisotope target, and the irradiated target removal system forms a portion of a pressure boundary of the reactor during target irradiation. 1. A target irradiation system for irradiating a radioisotope target in a vessel penetration of a fission reactor , comprising:an irradiated target removal system including a body defining a central bore, an elevator that is configured to be selectively received within the central bore, and a docking surface that is configured to selectively place the irradiated target removal system in fluid communication with the vessel penetration; anda target canister including a body defining a target bore that is configured to slidably receive the radioisotope target therein, and a cap configured to attach to the body of the target canister, thereby providing a water-tight seal for the target bore,wherein the elevator is configured to receive the target canister thereon, the elevator is lowered into the vessel penetration of the reactor when irradiating the radioisotope target, and the irradiated target removal system forms a portion of a pressure boundary of the reactor when in fluid communication with the vessel penetration.2. The target irradiation system of claim 1 , wherein the fission reactor is a heavy-water moderated fission reactor and the vessel penetration is an adjuster port.3. The target irradiation system of claim 1 , wherein the irradiated target removal system further comprises a winch and pulley assembly connected to the elevator by a cable.4 ...

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Номер записи: 42
23-01-2020 дата публикации

Compact Radioisotope Generator

Номер: US20200027619A1
Автор: Buchanan Charles Russell, Hamill James J., Siegel Stefan B.
Принадлежит:

Disclosed are a method and apparatus for making a radioisotope and a composition of matter including the radioisotope. The radioisotope is made by exposing a material to neutrons from a portable neutron source. 1. A composition of matter comprising a radioisotope , the radioisotope made according to a method comprising:obtaining a solution comprising a particular isotope dissolved in the solution;placing the solution into a container;exposing the solution to neutrons from a portable neutron source by completely surrounding the portable neutron source with at least the particular isotope, the particular isotope reacting with the neutrons and transforming into the radioisotope having a short half-life; andextracting the radioisotope from the solution.2. The composition of claim 1 , wherein the radioisotope is dispersed throughout a solid material.3. The composition of claim 2 , wherein the solid material has a geometrical shape.4. The composition of claim 1 , wherein the radioisotope that is made is Cu.5. The composition of claim 1 , wherein the container is located within a medical patient examination facility to expedite use after preparation. This is a divisional of U.S. patent application Ser. No. 12/887,933, filed Sep. 22, 2010, the contents of which are incorporated by reference.This application is directed toward production and use of radioactive isotopes, or radioisotopes.Radioactive isotopes have many beneficial uses. As one example, positron-emitting copper isotopes, such as copper-64 (Cu) and copper-60 (Cu) have a number of uses in clinical and pre-clinical nuclear medicine. These uses include, but are not limited to, the labeling of compounds and the creation of phantom objects suitable for localization and coregistration of multimodality imaging systems, such as those which combine magnetic resonance and positron-emission (MR-PET) imaging. In some instances these radioisotopes are used for oncology imaging and oncological therapy.The production of ...

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Номер записи: 43
23-01-2020 дата публикации

Compact Radioisotope Generator

Номер: US20200027620A1
Автор: Charles Russell Buchanan, James J. Hamill, Stefan B. Siegel
Принадлежит: Siemens Medical Solutions USA Inc

Disclosed are a method and apparatus for making a radioisotope and a composition of matter including the radioisotope. The radioisotope is made by exposing a material to neutrons from a portable neutron source.

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Номер записи: 44
23-01-2020 дата публикации

LOW DENSITY IRIDIUM

Номер: US20200027621A1
Автор: SHILTON Mark
Принадлежит:

The disclosure pertains to improvements in a gamma radiation source, typically containing low-density alloys or compounds or composites of iridium in mechanically deformable and compressible configurations, within a sealed encapsulation, and methods of manufacture thereof. 1. A radiation , radiological or radiographic source including a mechanically depressible , compressible non-solid configuration of:an alloy or mixture of iridium, manganese and an element chosen from a group consisting of aluminum, copper and mixtures thereof; oran alloy or mixture of iridium and yttrium.2. The radiation claim 1 , radiological or radiographic source of wherein the alloy or mixture comprises IrMnAl.3. The radiation claim 1 , radiological or radiographic source of wherein at least a portion of the iridium comprises Iridium-192.4. The radiation claim 1 , radiological or radiographic source of wherein the alloy or mixture further includes an element chosen from the group consisting of platinum claim 1 , osmium claim 1 , chromium or mixtures thereof.5. The radiation claim 1 , radiological or radiographic source of claim 1 , including at least a first element and a second element claim 1 , with a mechanically compressible portion between the first element and the second element claim 1 , whereby force on the radiation claim 1 , radiological or radiographic source causes the first element to move toward the second element.6. The radiation claim 1 , radiological or radiographic source of claim 1 , including at least a first element claim 1 , a second element and a third element claim 1 , with a first mechanically compressible portion between the first element and the second element and a second mechanically compressible portion between the second element and the third element.7. The radiation claim 6 , radiological or radiographic source of wherein the first claim 6 , second and third elements are respective first claim 6 , second and third rings or disks claim 6 , and wherein the second ...

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Номер записи: 45
28-01-2021 дата публикации

METHOD OF PRODUCING ACTINIUM BY LIQUEFIED RADIUM

Номер: US20210027906A1
Автор: KANG Joo Hyun, Lee Kyo Chul, Lim Sang Moo, OH Se Young
Принадлежит:

A method of producing actinium by using liquefied radium can minimize loss of Ra-226 according to the state change of Ac-225 by producing Ac-225 using Ra-226 of a liquefied state, moving the produced Ac-225 in a liquefied state after Ac-225 is produced, and separating and reusing Ac-225, thereby enabling a nuclear reaction process of Ac-225 to be performed. Further, a method of producing actinium by using liquefied radium according to the present disclosure has an effect of enabling safety to be improved by including a radon collection unit which is capable of discharging and isolating radon produced from Ra-226, thereby preventing radiation exposure due to radon. 1. A method of producing actinium by using liquefied radium , the method comprising step of;a step of moving the liquefied radium to load the liquefied radium into a reaction space inside a chamber;a step of producing actinium through a nuclear reaction process by irradiating a particle beam to the liquefied radium of the reaction space inside the chamber; andan unloading step of moving a product comprising the liquefied radium and actinium to the outside of the chamber.2. The method of claim 1 , further comprising step of separating actinium from the product.3. The method of claim 2 , further comprising a reloading step of transferring pure liquefied radium obtained by separating actinium from the product to the reaction space of the chamber.4. The method of claim 2 , further comprising a radon discharge step of discharging radon generated from radium while performing the loading step or the unloading step.5. The method of claim 4 , wherein the radon discharge step comprises condensing radon to discard radon.6. The method of claim 4 , wherein the radon discharge step comprises diluting radon with external air to discharge the diluted radon.7. The method of claim 2 , wherein the loading step comprises moving a preset amount of radium to the reaction space.8. The method of claim 7 , wherein the loading step ...

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Номер записи: 46
02-02-2017 дата публикации

TECHNIQUES FOR ON-DEMAND PRODUCTION OF MEDICAL ISOTOPES SUCH AS MO-99/TC-99M AND RADIOACTIVE IODINE ISOTOPES INCLUDING I-131

Номер: US20170032860A1
Автор: Tsang Francis Yu-Hei
Принадлежит:

A system 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. 120-. (canceled)21. A method for producing radioisotopes comprising:introducing non-enriched uranium (“NEU”) material into a an irradiation chamber, the irradiation chamber having one or more walls formed of neutron-reflecting material; at least some neutrons from the irradiating are reflected from at least one of the one or more walls, thereby increasing the path length over which those neutrons are in the NEU material, and', 'the increased path length increases the probability that those neutrons in the NEU material will cause fast fission reactions; and, 'irradiating the NEU material with neutrons having energies above 800 keV to cause fast fission reactions to occur in the NEU material and generate fission products, whereinextracting the fission products from the NEU material.22. The method of wherein one of the fission products extracted comprises at least one of molybdenum-99 (Mo-99) and technetium-99m (Tc-99m).23. The method of wherein one of the fission products extracted comprises at least one of iodine 131 (I-131) and iodine 132 (I-132).24. The method of wherein the NEU material in the irradiation chamber occupies a single spatially contiguous region.25. The method of wherein the NEU material in the irradiation chamber occupies multiple spatially disjoint regions.26. The method of wherein the one or more ...

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Номер записи: 47
02-02-2017 дата публикации

MASS PRODUCTION METHOD OF LOADING RADIOISOTOPES INTO RADIOVOLTAICS

Номер: US20170032862A1
Автор: Gahl John Michel, Kwon Jae Wan, Nullmeyer Bradley Ryan
Принадлежит:

A method of producing an integrated circuit-type active radioisotope battery, the method comprising exposing at least a portion of an electronically functional, unactivated integrated circuit-type battery to radiation to convert transmutable material in the unactivated battery to a radioisotope thereby producing an active cell and thus the integrated circuit-type active radioisotope battery. 1. A method of producing an integrated circuit-type active radioisotope battery , the method comprising exposing at least a portion of an electronically functional , unactivated integrated circuit-type battery that is either on a substrate or comprises the substrate , wherein the unactivated integrated circuit-type battery comprises an unactivated cell that comprises:a conversion device for converting energy from decay products of a radioisotope into electrical energy capable of performing work; anda non-radioactive, transmutable material associated with the conversion device; to radiation to transmute at least a portion of the transmutable material to a radioisotope thereby producing an active cell, wherein the energy from the decay products of the radioisotope material are converted by the conversion device into electrical energy capable of performing work, thereby producing the integrated circuit-type active radioisotope battery.2. (canceled)4. The method of claim 3 , wherein the transmutable material and the radiation are selected to yield a β-emitting or an α-emitting radioisotope.5. (canceled)6. (canceled)7. The method of claim 4 , wherein the substrate is a large band gap semiconductor material is selected from the group consisting of TiO claim 4 , Si claim 4 , SiC claim 4 , GaN claim 4 , GaAs claim 4 , ZnO claim 4 , WO claim 4 , SnO claim 4 , SrTiO claim 4 , FeO claim 4 , CdS claim 4 , ZnS claim 4 , CdSe claim 4 , GaP claim 4 , MoS claim 4 , ZnS claim 4 , ZrO claim 4 , and CeO claim 4 , and combinations thereof.8. (canceled)9. (canceled)10. (canceled)11. The method of ...

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Номер записи: 48
04-02-2016 дата публикации

Production of carbon-11 using a liquid target

Номер: US20160035448A1
Автор: Peter Andras Zavodszky, Tiberiu Mircea Siclovan
Принадлежит: General Electric Co

The present disclosure relates to the generation of radioisotopes, includes 11-carbon, from liquid targets. In certain embodiments, a liquid hydrazine target is employed which, when irradiated, such as with a charged particle beam, generates 11-carbon in a form that may be recovered and used in downstream processes, such as the generation of radiopharmaceuticals.

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Номер записи: 49
04-02-2016 дата публикации

CHARGED PARTICLE ACCELERATION DEVICE

Номер: US20160035449A1
Автор: Hird Jonathan, Naranjo Brian, Putterman Seth J.
Принадлежит:

A charged particle acceleration device according to some embodiments of the current invention includes a first triboelectric element, a second tribo-electric element arranged proximate the first tribo-electric element to be brought into contact with and separated from the first triboelectric element, an actuator assembly operatively connected to at least one of the first and second triboelectric elements to bring the first and second triboelectric elements into contact with each other and to separate the first and second triboelectric elements from each other, and a charged-particle source configured to provide charged particles in a gap between the first and second triboelectric elements. 1. A charged particle acceleration device , comprising:a first triboelectric element;a second triboelectric element arranged proximate said first triboelectric element to be brought into contact with and separated from said first triboelectric element;an actuator assembly operatively connected to at least one of said first and second triboelectric elements to bring said first and second triboelectric elements into contact with each other and to separate said first and second triboelectric elements from each other; anda charged-particle source configured to provide charged particles in a gap between said first and second triboelectric elements,wherein said first and second triboelectric elements comprise triboelectric materials that become charged with respect to each other by a triboelectric interaction such that an electric field is established between said first and second triboelectric elements when they are separated from each other by said actuator assembly, and wherein said charged-particle source is configured to provide said charged particles in said gap between said first and second triboelectric elements to be accelerated towards one of said first and second triboelectric elements by said electric field.2. A charged particle acceleration device according to claim 1 , ...

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Номер записи: 50
01-05-2014 дата публикации

NUCLIDE TRANSMUTATION DEVICE AND NUCLIDE TRANSMUTATION METHOD

Номер: US20140119488A1
Автор: Itoh Takehiko, Iwamura Yasuhiro, Sakano Mitsuru
Принадлежит: MITSUBISHI HEAVY INDUSTRIES, LTD.

The present invention produces nuclide transmutation using a relatively small-scale device. The device that produces nuclide transmutation comprises a structure body that is substantially plate shaped and made of palladium (Pd) or palladium alloy, or another metal that absorbs hydrogen (for example, Ti) or an alloy thereof, and a material that undergoes nuclide transmutation laminated on one surface A among the two surfaces of this structure body . The one surface A side of the structure body , for example, is made a region in which the pressure of the deuterium is high due to pressure or electrolysis and the like, and the other surface B side, for example, is a region in which the pressure of the deuterium is low due to vacuum exhausting and the like, arid thereby, a flow of deuterium in the structure body is produced, and nuclide transmutation is carried out by a reaction between the deuterium and the material that undergoes nuclide transmutation. 1. A nuclide transmutation device for achieving a nuclide transmutation , comprising:a multilayer structure body; that is made of palladium, or a palladium alloy, or a hydrogen absorbing metal other than palladium, or a hydrogen absorbing alloy other than a palladium alloy,an absorption part and a desorption part that are disposed so as to surround said multilayer structure body on the sides and form a closed space that can be sealed by said multilayer structure body;a high pressurization device that produces a relatively high pressure of deuterium at said absorption part on the side of the surface of said multilayer structure body; anda low pressurization device that produces a relatively low pressure of deuterium at said desorption part on the other side of the surface of said multilayer structure body,whereinsaid multilayer structure body includes:i) a base material including a hydrogen absorbing metal or a hydrogen absorbing alloy;ii) a mixed layer formed on said base material and comprising a hydrogen absorbing ...

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Номер записи: 51
11-02-2016 дата публикации

Production of copper-67 from an enriched zinc-68 target

Номер: US20160040267A1
Автор: Jon Stoner, Tim Gardner
Принадлежит: Idaho State University

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.

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Номер записи: 52
30-01-2020 дата публикации

HIGH EFFICIENCY NEUTRON CAPTURE PRODUCT PRODUCTION

Номер: US20200035373A1
Автор: Baldasaro Nicholas Guy
Принадлежит:

An apparatus for use with a neutron source for producing reaction-product nuclei from reactant nuclei includes a plurality of reactant nuclei and a plurality of moderating nuclei. The reactant nuclei and the moderating nuclei are configured to increase the probability of neutron capture by reactant nuclei to achieve enhanced ratios of neutron capture by reactant nuclei to neutron source neutron production. Moderating nuclei and neutron reflection are used to minimize neutron leakage. Temperature control, including cryogenic temperature control, may be used to enhance the rate or probability of reactant nuclei neutron capture. The reactant nuclei may include molybdenum-98 and reaction-product nuclei may include technetium-99m. 1. An apparatus for producing reaction-product nuclei from reactant nuclei , the apparatus comprising:a neutron source that is neither a nuclear reactor nor a subcritical assembly;a first plurality of reactant nuclei having a first average microscopic thermal neutron capture cross section;a collection of isotopes consisting of those isotopes whose nuclei capture at least 1% of all emitted neutrons from a neutron source and which are not reactant nuclei; anda second plurality of nuclei consisting of all nuclei from the collection of isotopes,wherein at least approximately 90% of the nuclei have microscopic thermal neutron capture cross-sections that are lower than the microscopic thermal neutron capture cross-section of any reactant nuclei, and wherein the total mass of moderating nuclei is greater than approximately 1 kilogram; andwherein the neutron source is in proximity to the reactant nuclei sufficient to produce reaction-product nuclei by neutron capture.2. The apparatus of claim 1 , wherein the rate of reactant nuclei neutron capture divided by the rate of the neutron source's neutron production is greater than approximately 1%.3. The apparatus of claim 1 , wherein the rate of reactant nuclei neutron capture divided by the rate of the ...

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Номер записи: 53
04-02-2021 дата публикации

FISSILE TARGET MATERIALS AND METHODS FOR PROCESSING FISSILE TARGET MATERIALS

Номер: US20210035699A1
Автор: Hall Gabriel B., Hubbard Lance R., McNamara Bruce K., Morrison Samuel S., Uhnak Nicolas
Принадлежит: BATTELLE MEMORIAL INSTITUTE

Methods for preparing fissile target materials are provided. The methods can include preparing a target substrate that includes a fissile atom, and layering at least one surface of the substrate with a capturing layer. Fissile target materials are provided. The fissile target materials can include a target substrate and a capturing layer operably interfacing with at least one surface of the target substrate. Methods for fissioning fissile target materials are also provided. The methods can include irradiating fissile target material to capture fission products of the irradiated fissile target material in a capturing layer of the target material. Fission fissile target materials are also provided that can include a target substrate comprising at least one fissile atom and a capturing layer operably interfacing with at least one surface of the target substrate. The capturing layer can include at least one fission product. Methods for separating fissioned product from fission fissile target materials are also provided. The methods can include separating at least a portion of the captured layer of the fissioned fissile target material from the fissile target material. 1. A method for preparing fissile target material , the method comprising:preparing a target substrate comprising a fissile atom; andlayering at least one surface of the substrate with a capturing layer.2. The method of wherein the target substrate is configured planarly.3. The method of further comprising providing the capturing layer along a flat surface of the planar target substrate.4. The method of wherein the target substrate is configured spherically.5. The method of further comprising providing the capturing layer along a curved surface of the spherical target substrate.6. The method of further comprising providing the capturing layer about the entirety of the exterior surface of the target substrate.7. The method of further comprising providing an intermediate layer between the substrate and the ...

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Номер записи: 54
11-02-2016 дата публикации

HIGH EFFICIENCY NEUTRON CAPTURE PRODUCT PRODUCTION

Номер: US20160042826A1
Автор: Baldasaro Nicholas Guy
Принадлежит: Research Triangle Institute

An apparatus for use with a neutron source for producing reaction-product nuclei from reactant nuclei includes a plurality of reactant nuclei and a plurality of moderating nuclei. The reactant nuclei and the moderating nuclei are configured to increase the probability of neutron capture by reactant nuclei to achieve enhanced ratios of neutron capture by reactant nuclei to neutron source neutron production. Moderating nuclei and neutron reflection are used to minimize neutron leakage. Temperature control, including cryogenic temperature control, may be used to enhance the rate or probability of reactant nuclei neutron capture. The reactant nuclei may include molybdenum-98 and reaction-product nuclei may include technetium-99m. 1. An apparatus for producing reaction-product nuclei from reactant nuclei , the apparatus comprising:a plurality of reactant nuclei and a plurality of moderating nuclei wherein the moderating nuclei comprise nuclei of atoms that are chosen from a group consisting of deuterium, tritium, helium-4, lithium-7, beryllium, boron-11, carbon, nitrogen-15, oxygen, fluorine, neon-20 and neon-22; anda neutron source that is neither a nuclear reactor nor a subcritical assembly, in proximity to the reactant nuclei sufficient to produce reaction-product nuclei by neutron capture;wherein the reactant nuclei comprise molybdenum-98;wherein the rate of molybdenum-98 nuclei neutron capture divided by the rate of the neutron source's neutron production is greater than approximately 1%;wherein the mass of molybdenum-98 is less than approximately 1000 kg; andwherein the mass of moderating nuclei is at least 1 kg.2. The apparatus of claim 1 , wherein the mass of molybdenum-98 is less than approximately 100 kg.3. The apparatus of claim 1 , wherein the mass of molybdenum-98 is less than approximately 25 kg.4. The apparatus of claim 2 , wherein the rate of reactant nuclei neutron capture divided by the rate of the neutron source's neutron production is greater than ...

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Номер записи: 55
09-02-2017 дата публикации

METHODS AND DEVICES FOR ISOLATING LEAD 203

Номер: US20170040074A1
Автор: Olewine Keith R.
Принадлежит: Lantheus Medical Imaging, Inc.

Methods for isolating Pb and/or Pb isotopes from various sources are provided. Compositions comprising Pb and/or Pb isotopes free of certain amounts of various contaminants are also provided. 1. A method , comprisingcontacting a chelating resin that comprises iminodiacetic acid with a solution comprising Pb, andeluting the Pb bound to the chelating resin with a heated sodium hydroxide solution, wherein the heated sodium hydroxide solution is at a temperature suitable for the selective elution of Pb.2. The method of claim 1 , wherein the temperature of the heated sodium hydroxide solution is about 85-95° C.3. A method claim 1 , comprisingcontacting a chelating resin that comprises iminodiacetic acid with a solution comprising Pb, andeluting the Pb bound to the chelating resin with heated sodium hydroxide solution, wherein the temperature of the sodium hydroxide is at about 90° C.4. A method claim 1 , comprisingeluting Pb from a chelating resin using a sodium hydroxide solution at a temperature of about 85-95° C.or of about 85° C. or higher.5. A composition claim 1 , comprising{'sup': '203', 'Pb and less than 0.1 μg/mCi Ni and/or'}less than 0.1 μg/mCi Cu and/orless than 0.5 μg/mCi Zn and/orless than 0.25 μg/mCi Fe and/orless than 0.05 μg/mCi Tl.6. The composition of claim 5 , further comprising sodium hydroxide. This application claims the benefit of U.S. Provisional Application No. 61/979,957 filed on Apr. 15, 2014, the entire contents of which are incorporated by reference herein.Radioactive isotopes of many metallic elements have potential uses in the diagnosis and treatment of disease. The lead-203 isotope (Pb), for example, which has a half-life of about 52 hours and decays by electron capture, has excellent promise in medical diagnostics. As a result, recent advances in radioimmunotherapy and peptide targeted radiotherapy have created a great demand for Pb.Pb is an important isotope in certain medical applications. For example, because of its relatively short ...

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Номер записи: 56
07-02-2019 дата публикации

Fuel channel isotope irradiation at full operating power

Номер: US20190043630A1
Автор: Benjamin D. Fisher, Thomas G. Onderwater
Принадлежит: BWXT Isotope Technology Group Inc

A method of a method of irradiating a target material in a heavy water reactor for the production of an isotope, including the steps of providing a target comprised of a material suitable for producing the isotope by way of a neutron capture event, placing the target in a primary fluid side of the heavy water reactor, and irradiating the target.

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Номер записи: 57
06-02-2020 дата публикации

SYSTEM FOR THE IRRADIATION OF A TARGET MATERIAL

Номер: US20200043621A1
Автор: COMOR Jozef, GEETS Jean-Michel, NACTERGAL Benoit
Принадлежит: Ion Beam Applications S.A.

A capsule for the transfer of a target material in a conveying system between a target irradiation station and a collecting station comprising: a beamline channel for the passage of an energetic beam irradiating the target material, a target holder holding the target material or a substrate backing the target material at a glancing angle with respect to the beamline channel axis, a degrader foil positioned across the beamline channel for degrading an energy of the energetic beam upstream of the target material, a target cooling inlet and a target cooling outlet for passage of a cooling fluid in a target cooling duct in a vicinity of the target holder such that the target material can be cooled during an irradiation, and a degrader foil cooling inlet and a degrader foil cooling outlet for passage of a cooling gas in a vicinity of the degrader foil. 115-. (canceled)16. A capsule for the transfer of a target material in a conveying system between a target irradiation station and a collecting station , comprising:a beamline channel extending along a beamline channel axis for passage of an energetic beam irradiating the target material,a target holder for holding the target material or a substrate backing the target material at a glancing angle with respect to the beamline channel axis,a housing for enclosing the target holder, the housing being openable such that the target material can be inserted in or removed from the target holder when the housing is opened,a degrader foil positioned across the beamline channel for degrading energy of the energetic beam upstream of the target material,a target cooling inlet and a target cooling outlet for passage of a cooling fluid in a target cooling duct in a vicinity of the target holder such that the target material can be cooled during the irradiation, anda degrader foil cooling inlet and a degrader foil cooling outlet for passage of a cooling gas in a vicinity of the degrader foil.17. The capsule according to claim 16 , ...

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Номер записи: 58
06-02-2020 дата публикации

Radioactive fine particle manufacturing system, and radioactive fine particle manufacturing method

Номер: US20200043622A1
Автор: Shinji TOKONAMI
Принадлежит: Hirosaki University NUC

A radioactive fine particle manufacturing system to manufacture physically stable radioactive fine particles without using large-scale equipment, which enable performance evaluation of a radioactivity measuring instrument employing a novel physical indicator, with which a method for controlling radioactivity concentration by means of the humidity of air is presented in a specific manner, and with which it is possible to implement performance evaluation of the overall radioactivity measuring instrument. The radioactive fine particle manufacturing system uses a configuration provided with a radioactive gas generating system, a specific particle-sized aerosol generating system and a mixing chamber, to manufacture radioactive fine particles employing natural radioactive nuclides. 220 Rn is employed to manufacture radioactive fine particles using physically stable progeny nuclides. In the mixing chamber, the progeny nuclides are caused to attach only to an aerosol having a specific particle size, to generate radioactive fine particles having a specific particle size.

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Номер записи: 59
15-02-2018 дата публикации

RADIOACTIVE WASTE PROCESSING METHOD

Номер: US20180047473A1
Автор: FUJITA Reiko, MATSUZAKI Teiichiro, MIZUGUCHI Koji, Nitta Koji, OIGAWA Hiroyuki, OTSU Hideaki, OZAWA Masaki, SAKURAI Hiroyoshi, SHIMOURA Susumu
Принадлежит:

Provided is a fission product processing method for selectively transmuting only a long-lived radionuclide from fission products. The method for processing radioactive waste includes the step of extracting, from the radioactive waste, the isotopes without isotope separation, the isotope elements including radionuclides of fission products and having a common atomic number, and the step of irradiating the isotopes with high-energy particles generated by an accelerator to produce nuclear transmutation of a long-lived radionuclide of the radionuclides into a short-lived radionuclide with a short half-life or a stable nuclide re-utilizable as a resource. 111.-. (canceled)12. A method for processing radioactive waste , comprising:a step of extracting, from the radioactive waste, an isotopes without isotope separation, the isotopes including a radionuclide of a fission product and having a common atomic number; anda step of irradiating the isotopes with a neutron (n) generated by an accelerator to produce nuclear transmutation of a first nuclide as a long-lived radionuclide of the radionuclide into a second nuclide as a stable nuclide,wherein a value of irradiation energy of the neutron (n) is set within such a range that a (n, 2n) reaction cross section of the first nuclide is equal to or larger than 10 times as large as a (n, 2n) reaction cross section of a third nuclide;wherein the nuclear transmutation of the third nuclide into the first nuclide is suppressed based on parity of neutron separation energy of the isotope element; and selenium (Se) isotops, Se-79, Se-78, and Se-80, respectively;', 'palladium (Pd) isotops, Pd-107, Pd-106, and Pd-108, respectively;', 'zirconium (Zr) isotops, Zr-93, Zr-92, and Zr-94, respectively;', 'krypton (Kr) isotops, Kr-85, Kr-84, and Kr-86, respectively; or', 'samarium (Sm) isotops, Sm-151, Sm-150, and Sm-152, respectively., 'wherein the isotops, the first nuclide, the second nuclide, and the third nuclide are defined as below13. A ...

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Номер записи: 60
15-05-2014 дата публикации

SYSTEMS AND METHODS FOR EFFICIENTLY PREPARING PLUTONIUM-238 WITH HIGH ISOTOPIC PURITY

Номер: US20140133616A1
Автор: BERTCH Timothy Creston, BROWN Lloyd Chauncey
Принадлежит: General Atomics

A method for preparing plutonium-238 (Pu-238) using reactor may include irradiating a liquid containing a neptunium-237 (Np-237) based compounds with neutrons to convert a portion of the Np-237 based compound to a Np-238 based compound; retaining the liquid containing the resulting mixture for a sufficient amount of time for the Np-238 based compound to at least partially convert to a plutonium-238 (Pu-238) based compound. The method further may include separating the Pu-238 based compound from the neptunium based compounds using distillation or chemical method. 1. A system for preparing plutonium-238 (Pu-238) using neutrons emitted by a nuclear reactor , the system comprising:an irradiation unit configured to receive a liquid comprising a neptunium-237 (Np-237) based compound and to receive the neutrons emitted by the nuclear reactor such that the neutrons convert a portion of the Np-237 based compound to a neptunium-238 (Np-238) based compound, resulting in a liquid mixture of the Np-237 based compound and the Np-238 based compound;a decay unit configured to retain the resulting liquid mixture from the irradiation unit for a sufficient amount of time for the Np-238 based compound to at least partially convert to a plutonium-238 (Pu-238) based compound, resulting in a liquid mixture of the Np-237 based compound, the Np-238 based compound, and the Pu-238 based compound; anda separation unit configured to separate the Pu-238 based compound in the resulting liquid mixture from the decay unit from the Np-237 based compound and the Np-238 based compound in that mixture.2. The system of claim 1 , in which the liquid mixture of the Np-237 based compound and the Np-238 based compound is recycled from the separation unit back to the irradiation unit.3. The system of claim 1 , wherein the irradiation unit comprises a plurality of panels each positioned adjacent the nuclear reactor and configured to receive the Np-237 based liquid.4. The system of claim 3 , further comprising ...

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Номер записи: 61
15-05-2014 дата публикации

METHOD AND SYSTEM FOR SIMULTANEOUS IRRADIATION AND ELUTION CAPSULE

Номер: US20140133617A1
Автор: BLOOMQUIST Bradley, Bowie Jennifer, II William Earl, Russell, Smith David Grey
Принадлежит: GE-HITACHI NUCLEAR ENERGY AMERICAS LLC

A capsule for holding, irradiating, and eluting a material is provided. Methods of fabricating and using the capsule are also provided. The capsule may include a multidiameter tube with a first end region, a second end region, and a middle region. Washers and filters are provided in the end regions and the end regions may be sealed using various methods and materials with the end caps press fit into the end regions. The middle region is designed to store a material to be irradiated by a neutron flux source. The capsule components may be made from materials having a low nuclear cross section so that the capsule may be handled safely after an irradiation step is performed. The capsule is also designed to have a symmetric configuration as an elution and irradiation column so that the same capsule may be used to elute the material within the middle region of the capsule after an irradiation step is performed. 1. An elution capsule , comprising:a tube with a first end portion having a first inside diameter, a second end portion having a second inside diameter;a singular first opening in the first end portion and a singular second opening in the second end portion, the first and second openings facing opposite directions and being about collinear with a longitudinal centerline of the tube;a middle portion between the first end portion and the second end portion and having an inside diameter smaller than the inside diameters of the first and second end portions, wherein an interface between the first end portion and the middle portion forms a first shoulder and an interface between the second end portion and the middle portion forms a second shoulder;a first washer inside the first end portion contacting the first shoulder;a first filter inside the first end portion contacting the first washer;a second filter inside the first end portion contacting the first filter, the first filter being located between the first washer and the second filter;a first end cap sealing the ...

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Номер записи: 62
20-02-2020 дата публикации

Alternating Flow Column Chromatography Apparatus and Method of Use

Номер: US20200054965A1
Автор: Le Minh Khoi, Le Van So
Принадлежит:

An alternating flow column chromatography apparatus comprising a ‘U’ shaped or T shaped separation column including at least one loading port for loading of components for separation, a first purification column in fluid communication with one end of the separation column and a second purification column in fluid communication with another end of the separation column, at least one eluent input port, an eluate output port and an alternating flow valve in fluid communication with the primary eluent input port, the eluate output port, the first purification column and the second purification column wherein, when operated, the alternating flow valve reverses the flow of eluent through the purification columns and the separation column. Also a method of using the apparatus. A benefit of the apparatus and method is more efficient operation compared to existing direct flow column chromatography apparatuses. 1. An alternating flow column chromatography apparatus for chromatographic separation and chromatographic purification of ionic radionuclide components and chemical components soluble in a solution comprising:a chromatographic separation column of ‘U’ shape or modified ‘I’ shape, including at least one loading port for loading of components for separation;a first purification column in fluid communication with one end of the separation column and a second purification column in fluid communication with another end of the separation column;at least one eluent input port;an eluate output port; andan alternating flow valve in fluid communication with the at least one eluent input port, the eluate output port, the first purification column and the second purification column wherein, when operated, the alternating flow valve reverses the flow of eluent through the purification columns and the separation column.2. The apparatus of wherein one of the at least one eluent input port is a primary eluent input port and there are one or more specific eluent input ports.3. The ...

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Номер записи: 63
05-03-2015 дата публикации

METHOD OF PREPARING RADIOISOTOPE HYBRID NANOCOMPOSITE PARTICLES USING SOL-GEL REACTION AND RADIOISOTOPE HYBRID NANOCOMPOSITE PARTICLES PREPARED USING THE SAME

Номер: US20150064108A1
Автор: Choi Seong Ho, CHOI Sun Ju, Jung Sung-Hee, Kim Jong Bum, MOON Jin Ho, Seo Sang Ei
Принадлежит:

A method of preparing radioisotope hybrid nanocomposite particles using a sol-gel reaction, and radioisotope hybrid nanocomposite particles prepared using the same are provided. The method includes preparing a complex precursor using a metal ion and an unshared electron pair reactive compound, growing hybrid nanocomposite particles based on the complex precursor by means of a sol-gel reaction, calcining the nanocomposite particles in the air to remove organic matters present in the nanocomposite particles, and irradiating the nanocomposite particles with neutrons to prepare radioisotope hybrid nanocomposite particles. The radioisotope nanocomposite particles prepared using the method can be used as diagnostic and therapeutic particles in the fields of oil refining, chemistry, cement, agriculture, water resources, environment, ocean, and medicine, and can also be used as a radioisotope tracer for evaluating the risk of nanomaterials. 1. A method of preparing radioisotope hybrid nanocomposite particles , comprising:(a) preparing a primary precursor by mixing a reactive compound with a metal ion and stirring the mixture;(b) preparing hybrid nanocomposite particles by subjecting the primary precursor to a sol-gel reaction;(c) calcining the hybrid nanocomposite particles at 300° C. to 700° C. for 5 to 10 hours; and(d) preparing radioisotope hybrid nanocomposite particles by irradiating the calcined particles with neutrons.2. The method of claim 1 , wherein operation (b) comprises:(b-1) adding the primary precursor to a mixed solvent;(b-2) adding tetraethoxysilane to the mixed solvent to which the primary precursor is added; and(b-3) preparing hybrid nanocomposite particles by stirring a solution to which the tetraethoxysilane is added in operation (b-2) for 6 to 9 hours.3. The method of claim 1 , wherein the reactive compound is a compound having an unshared electron pair.4. The method of claim 3 , wherein the reactive compound having an unshared electron pair is 3- ...

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Номер записи: 64
01-03-2018 дата публикации

PRODUCTION OF MOLYBDENUM-99 USING ELECTRON BEAMS

Номер: US20180061516A1
Автор: de JONG Mark, Diamond William, LIN Linda, NAGARKAL Vinay, REGIER Christopher, ULLRICH Douglas
Принадлежит: Canadian Light Source Inc.

An apparatus for producing Mo from a plurality of Mo targets through a photo-nuclear reaction on the Mo targets. The apparatus comprises: (i) an electron linear accelerator component; (ii) an energy converter component capable of receiving the electron beam and producing therefrom a shower of bremsstrahlung photons; (iii) a target irradiation component for receiving the shower of bremsstrahlung photons for irradiation of a target holder mounted and positioned therein. The target holder houses a plurality of Mo target discs. The apparatus additionally comprises (iv) a target holder transfer and recovery component for receiving, manipulating and conveying the target holder by remote control; (v) a first cooling system sealingly engaged with the energy converter component for circulation of a coolant fluid therethrough; and (vi) a second cooling system sealingly engaged with the target irradiation component for circulation of a coolant fluid therethrough. 1. An apparatus for producing molybdenum-99 (Mo) from a plurality of molybdenum-100 (Mo) targets through a photo-nuclear reaction on the Mo targets , the apparatus comprising:a linear accelerator component capable of producing an electron beam;a converter component capable of receiving the electron beam and producing therefrom a shower of bremsstrahlung photons;{'sup': '100', 'a target irradiation component for receiving the shower of bremsstrahlung photons, the target irradiation component having a chamber for receiving, demountingly engaging, and positioning therein a target holder housing a plurality of Mo target discs;'}a remote controlled grapple assembly transportable along and within the apparatus, the grapple assembly demountably engageable with an end of the target holder; anda cooling system sealingly engaged with the converter component for circulation of a coolant fluid therethrough.2. The apparatus according to claim 1 , wherein the linear accelerator component has at least 10 kW of power to about 100 kW ...

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Номер записи: 65
22-05-2014 дата публикации

Process

Номер: US20140140462A1
Автор: Barbosa Luis A.M.M.
Принадлежит:

A process for producing Tc-99m comprises the steps of contacting a solution of purified Mo-99 with an adsorbent material comprising i) a tin oxide, or ii) a zirconium oxide and a titanium oxide, such that the Tc-99m resulting from the decay of Mo-99 may thereafter be eluted. 1. A process for producing Tc-99m , the process comprising the steps of contacting a solution of purified Mo-99 with an adsorbent material comprising i) a tin oxide , or ii) a zirconium oxide and a titanium oxide , such that the Tc-99m resulting from the decay of Mo-99 may thereafter be eluted.2. A process according to claim 1 , wherein the adsorbent material comprises a tin oxide and a titanium oxide.3. A process according to claim 1 , wherein the adsorbent material comprises a zirconium oxide and a titanium oxide is Termoxid-5M.4. A process according to claim 2 , wherein the adsorbent material comprises a tin oxide and a titanium oxide is Termoxid-52.5. A process according to claim 1 , wherein the process further comprises the steps of allowing sufficient time for the Mo-99 to decay claim 1 , and eluting Tc-99m.6. A process according to claim 5 , wherein the process further comprises recycling the adsorbent material by removing residual molybdenum and optionally contacting a second solution of purified Mo-99 therewith.7. A process according to claim 1 , wherein the solution of purified Mo-99 is contacted with the adsorbent material in the presence of a molybdenum carrier.8. A process according to claim 1 , wherein the particle size of the adsorbent material ranges from 0.001 mm to 3 mm.9. A process according to claim 8 , wherein the particle size of the adsorbent material ranges from 0.2 mm to 1 mm.10. A process according to claim 9 , wherein the particle size of the adsorbent material ranges from 0.4 mm to 1 mm.11. An apparatus for carrying out the process of claim 1 , the apparatus comprising a column or vessel containing an adsorbent material comprising i) a tin oxide claim 1 , or ii) a ...

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Номер записи: 66
02-03-2017 дата публикации

SYSTEMS AND METHODS FOR GENERATING ISOTOPES IN NUCLEAR REACTOR STARTUP SOURCE HOLDERS

Номер: US20170062085A1
Автор: Caine Thomas A., Miranda Dana C., Stachowski Russell E.
Принадлежит:

Irradiation target holders are configured to fit in open locations inside of an operating commercial nuclear core. Holders can be placed with ends at vertical bottom and top of the core or any position therebetween to directly expose holders to nuclear fuel reactions. Holders have ends and overall shape that can join with existing reactor structures, while fitting closely with fuel and moderator and being easily removable from the same. Holders are fabricated of any reactor-compatible material that will retain irradiation targets and daughter products. Holders securely retain irradiation targets and daughter products of any shape or phase throughout reactor operation. Holders can be installed during reactor outages and irradiated during operation without risk of movement or interference with operation. After a desired period of operation and irradiation, holders can be harvested from the core independent of other core structures and fuel. 1. A method of creating desired isotopes in a commercial nuclear reactor generating heat for use in power production , the method comprising: the irradiation target holder is moveable independent of the fuel and impermeably contains an irradiation target having a thermal neutron absorption cross section exceeding 1 barn and an atomic number less than 90, and', 'the operating irradiates the irradiation target holder with neutron flux to produce a desired daughter product from the irradiation target., 'operating the nuclear reactor to generate heat for use in power production, wherein the reactor includes an irradiation target holder in a core of the nuclear reactor in a position directly exposed to fuel and moderator from all sides in the core and inaccessible from outside the reactor during the operating, wherein,'}2. The method of claim 1 , further comprising:removing a startup source holder from the position; andinstalling the irradiation target holder in the position, wherein the removing and installing are performed during a ...

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Номер записи: 67
08-03-2018 дата публикации

Automated purification and formulation device for radiopharmaceutical compounds

Номер: US20180065103A1
Автор: Alexander HSIAO, Brandon Maraglia, Eric Schopf, Melissa Moore, R. Michael Van Dam
Принадлежит: Sofie Biosciences Inc, UNIVERSITY OF CALIFORNIA

A device for purifying and formulating a radiopharmaceutical compound includes an automated purification subsystem that automates the loading of a sample into a sample loop for downstream purification via HPLC. A column selector valve is provided to select from one of a plurality of columns. Fractions can be collected as well as the desired product. The device includes an automated formulation subsystem that first sends the product to a dilution reservoir prior to being pneumatically pushed onto a solid phase extraction (SPE) cartridge. Automated rinse, elution, and reconstitution are also performed with the automated formulation subsystem. The device may be directly coupled to the output of an automated radiosynthesizer.

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Номер записи: 68
27-02-2020 дата публикации

RADIOISOTOPE TARGET STATION

Номер: US20200066418A1
Автор: Bailey James L., BROWN Michael Alexander, Chemerisov Sergey A., EHST David A., Grudzinski James J., Jr. Jerry A., Kmak Ronald T., Nolen, Rotsch David A., Smith Nicholas A.
Принадлежит: UCHICAGO ARGONNE, LLC

A system for producing and harvesting radioisotopes is provided, the system having a converter housing defining a first beam window; a converter carrier and cartridge in slidable communication with the converter housing; a target housing positioned downstream from the converter housing, the target housing defining a second beam window; and a target carrier in slidable communication with the target housing. 1. A system for producing radioisotopes , the system comprising:a) a converter housing having an upstream end and a downstream end, the upstream end defining a first window;b) a converter carrier in slidable communication with the converter housing;c) a target housing positioned downstream from the converter housing, the target housing defining a second window; andd) a target carrier removably received by the target housing, wherein the first window, the converter housing, the converter carrier, the target housing and the target carrier define a tunnel adapted to receive a particle beam.2. The system as recited in wherein the target carrier communicates with an upwardly facing surface of the target housing.3. The system as recited in wherein a coolant fluid is in thermal communication with the converter housing and the target housing.4. The system as recited in further comprising a target capsule adapted to be received by the target carrier.5. The system as recited in wherein the target capsule is adapted to receive target isotope having a weight of between 1 mg and 100 claim 4 ,000 mg.6. The system as recited in wherein the first window has a convex topography relative to the upstream end.7. The system as recited in wherein the first window has a flat topography relative to the upstream end.8. The system as recited in wherein the particle beam comprises an incident electron beam having an energy ranging from 0 MeV to 100 MeV.9. The system as recited in wherein the particle beam comprises an incident electron beam having a beam power ranging from 0 kW to 100 kW.10 ...

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Номер записи: 69
16-03-2017 дата публикации

RADIATION SHIELDS FOR LINAC HEAD AND SYSTEM

Номер: US20170072223A1
Автор: Constantin Magdalena, Hsu HsinLu, Scollay Stuart
Принадлежит:

In a method of constructing a head shield for a radiation machine, the angular distribution of radiation propagating from a source and the angular function of thickness of a material in attenuating the radiation to a certain level of its original value are determined. Based on the angular distribution of radiation from the source and the angular function of thickness of the material, the thicknesses of the material at a plurality of angular locations around the source and distances from the source can be calculated for attenuating the radiation to or less than a predetermined threshold value. A shield around the source is constructed based on the calculated thicknesses of the material through iterative steps to ensure a cost- saving, weight-efficient, optimal solution. A method of designing a local radiation shield for a point of interest in a radiation system is also described to improve the machine reliability, regardless of the motion component of the POI with respect to the main radiation source and the secondary radiation source created by the patient scatter. 1. A method of designing a radiation shield , comprising:determining an angular distribution of radiation propagating from a source;determining an angular function of thickness of a material in attenuating the radiation to a certain level of its original value; andcalculating thicknesses of the material at a plurality of angular locations around the source and distances with respect to the source for attenuating the radiation to or less than a predetermined threshold value based on the angular distribution of radiation from the source and the angular function of thickness of the material;designing a radiation shield around the source based on the calculated thicknesses of the material.2. The method of wherein the angular distribution of radiation propagating from the source comprises an angular distribution of radiation dose.3. The method of wherein the angular distribution of radiation propagating from ...

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Номер записи: 70
19-03-2015 дата публикации

HYBRID MOLTEN SALT REACTOR WITH ENERGETIC NEUTRON SOURCE

Номер: US20150078504A1
Автор: Woolley Robert Daniel
Принадлежит:

In an embodiment, a hybrid molten salt reactor includes a source of energetic neutrons, the energetic neutrons having a typical energy per neutron of 14 MeV or greater, a critical molten salt reactor, and a molten salt comprising a dissolved mixture of fissile actinides and fertile actinides. The molten salt circulates in a loop through the reactor vessel and around the source of energetic neutrons. The fissile actinides and fertile actinides sustain an exothermic nuclear reaction in which the actinides are irradiated by the energetic neutrons, the energetic neutrons inducing subcritical nuclear fission, and undergo critical nuclear fission when circulating through the critical molten salt reactor. A portion of the daughter neutrons generated by nuclear reactions are captured by the fertile actinides in the molten salt and induce transmutation of the fertile actinides into fissile actinides and sustain critical fission chain reactions in the molten salt reactor. 1. A hybrid molten salt reactor (HMSR) comprising:a source of energetic neutrons, the energetic neutrons having a typical energy per neutron of 14 MeV or greater;a critical molten salt reactor comprising a reactor vessel;a loop comprising a path in the reactor vessel and around the source of energetic neutrons; and the fissile and fertile actinides being irradiated by the energetic neutrons when exposed to the source of energetic neutrons, the energetic neutrons inducing subcritical nuclear fission and generating daughter neutrons;', 'the fissile actinides undergoing critical nuclear fission when circulating through the vessel of the critical molten salt reactor and generating daughter neutrons; and', 'a portion of the fertile actinides capturing a portion of the daughter neutrons, the captured daughter neutrons inducing transmutation of the portion of fertile actinides into fissile actinides., 'a molten salt comprising a dissolved mixture of salts of fissile actinides and fertile actinides, the molten salt ...

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Номер записи: 71
05-06-2014 дата публикации

Dry Phase Reactor for Generating Medical Isotopes

Номер: US20140153684A1
Автор: Heltemes Thad Alexander, Mackie Thomas Rockwell
Принадлежит: WISCONSIN ALUMNI RESEARCH FOUNDATION

An apparatus for generating medical isotopes provides for the irradiation of dry-phase, granular uranium compounds which are then dissolved in a solvent for separation of the medical isotope from the irradiated compound. Once the medical isotope is removed, the dissolved compound may be reconstituted in dry granular form for repeated irradiation. 1. A method of producing medical isotopes comprising the steps of:(a) exposing a dry granular uranium compound to radiation to produce the medical isotope by nuclear reaction;(b) dissolving the irradiated uranium compound in a solvent; and(c) separating the medical isotope from the solventized uranium compound to provide an isolated medical isotope.2. The method of wherein the uranium compound is selected from the group consisting of uranium oxides and uranium salts.3. The method of wherein the uranium salt is selected from the group consisting of uranyl nitrite or uranyl sulfate.4. The method of further including the step of (d) reconstituting the dry granular uranium compound by removing the solvent and repeating steps (a)-(c).5. The method of wherein the solvent is an acid selected from the group consisting of nitric acid and sulfuric acid.6. The method of further including the step of cooling the dry granular uranium compound by a flow of fluid in thermal physical contact with the granular uranium compound during step (a).7. The method of wherein the medical isotope is Mo.8. The method of wherein in step (a) the dry granular uranium compound is held in multiple containers and wherein step (b) dissolves the irradiated uranium compound in the solvent in the containers and then removes the solvent from the containers along with the dissolved uranium compound.9. The method of further including placement of one or more reflectors reflecting radiation near the dry granular uranium compound during irradiation.10. The method of including the step of moving neutron absorbing control elements in a region near the dry granular ...

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Номер записи: 72
17-03-2016 дата публикации

System And Method For Generating Molybdenum-99 And Metastable Technetium-99, And Other Isotopes

Номер: US20160078971A1
Автор: Clayton James E.
Принадлежит:

Accelerator based systems are disclosed for the generation of isotopes, such as molybdenum-98 (“99Mo”) and metastable technetium-99 (“99mTc”) from molybdenum-98 (“98Mo”). Multilayer targets are disclosed for use in the system and other systems to generate 99mTc and 98Mo, and other isotopes. In one example a multilayer target comprises a first, inner target of 98Mo surrounded, at least in part, by a separate, second outer layer of 98Mo. In another example, a first target layer of molybdenum-100 is surrounded, at least in part, by a second target layer of 98Mo. In another example, a first inner target comprises a Bremsstrahlung target material surrounded, at least in part, by a second target layer of molybdenum-100, surrounded, at least in part, by a third target layer of 98Mo. 1. A system for generating isotopes , comprising:an accelerator;a source of charged particles coupled to the accelerator to inject charged particles into the accelerator;a target comprising:a first, inner target material, comprising a first isotope of a first material; anda second, outer target material comprising a second isotope of a second material, the second outer target material at least partially surrounding the first, inner target material, the second, outer target material defining a passage for accelerated charged particles to the first, inner target material.2. The system of claim 1 , wherein the first material and the second material are the same and the first isotope and the second isotope are different isotopes of the first material.3. The system of claim 2 , wherein the first claim 2 , inner target material and the second claim 2 , outer target material are separated by a gap.4. The system of claim 1 , wherein the first isotope and the second isotope each comprise molybdenum-98.5. The system of claim 2 , wherein the first isotope comprises molybdenum-100 and the second isotope comprises molybdenum-98.6. The system of claim 1 , wherein the target further comprises a layer of ...

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Номер записи: 73
24-03-2022 дата публикации

COMPACT ASSEMBLY FOR PRODUCTION OF MEDICAL ISOTOPES VIA PHOTONUCLEAR REACTIONS

Номер: US20220093283A1
Автор: Brown Michael A., Chemerisov Sergey D., Henning Walter F., Jr. Jerry A., Nolen, Rotsch David A., Song Jeongseog
Принадлежит: UCHICAGO ARGONNE, LLC

The invention provides a method for generating medical isotopes, the method comprising contacting a primary radiation beam with a converter for a time sufficient to produce a secondary beam of gamma particles, and contacting the beam of gamma particles to a target, where the cross section dimension of the beam of gamma particles is similar to the cross section dimension of the target. Both the converter and target are small in diameter and very closely spaced. Also provided is a system for producing medical isotopes, the device comprising a housing having a first upstream end and a second downstream end, a radiotransparent channel (collimator) with a first upstream end and a downstream end, wherein the upstream end is adapted to receive a radiation beam, a target positioned downstream of the downstream end of the channel and coaxially aligned with the channel, wherein the target has a cross section that is similar to the cross section of the channel. 1. A system for producing medical isotopes , the system comprising:a) a housing having a first upstream end and a second downstream end;b) a radiotransparent channel with a first upstream end and a downstream end, wherein the upstream end is adapted to receive a radiation beam; andc) a target positioned downstream of the downstream end of the channel and coaxially aligned with the channel, wherein the target has a cross section that is similar to the cross section of the channel.211. The system as recited in claim further comprising a heat sink in thermal communication with the channel and target.311. The system as recited in claim further comprising a converter disposed between the channel and the target , wherein the converter and front face of the target are protected from degradation by air by being bathed in a vacuum or an inert fluid.412. The system as recited in claim wherein the heat sink is a fluid and the housing defines a first fluid conduit and a second fluid conduit.514. The system as recited in claim ...

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Номер записи: 74
05-03-2020 дата публикации

TARGET IRRADIATION SYSTEMS FOR THE PRODUCTION OF RADIOISOTOPES

Номер: US20200075180A1
Автор: Alboino Mark A., Fisher Benjamin D., Long Andrew F., Onderwater Thomas G.
Принадлежит:

A target irradiation system for irradiating a radioisotope target in a vessel penetration of a fission reactor, including a target delivery assembly including a body defining a central bore, a basket that is slidably receivable within the central bore of the body, and a winch that is connected to the basket by a cable, the target delivery assembly being affixed to the vessel penetration of the reactor, and a target passage that is in fluid communication with the target delivery assembly, wherein the basket is configured to receive the radioisotope target therein via the target passage and be lowered into the vessel penetration of the reactor when irradiating the radioisotope target, and the target delivery system forms a portion of the pressure boundary of the reactor when in fluid communication with the reactor. 1. A target irradiation system for irradiating a radioisotope target in a vessel penetration of a fission reactor , comprising:a target delivery assembly including a body defining a central bore, a basket that is slidably receivable within the central bore of the body, and a winch that is connected to the basket by a cable, the target delivery assembly being affixed to the vessel penetration of the reactor; anda target passage that is in fluid communication with the target delivery assembly,wherein the basket is configured to receive the radioisotope target therein via the target passage and be lowered into the vessel penetration of the reactor when irradiating the radioisotope target, and the target delivery system forms a portion of the pressure boundary of the reactor when in fluid communication with the reactor.2. The target irradiation system of claim 1 , wherein the fission reactor is a heavy-water moderated fission reactor and the vessel penetration is an adjuster port.3. The target irradiation system of claim 2 , wherein the radioisotope target is comprised of natural molybdenum.4. The target irradiation system of claim 1 , wherein the target ...

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Номер записи: 75
05-03-2020 дата публикации

SYSTEM AND PROCESS FOR PRODUCTION AND COLLECTION OF RADIOISOTOPES

Номер: US20200075187A1
Автор: Heibel Michael D.
Принадлежит: WESTINGHOUSE ELECTRIC COMPANY LLC

A means for installing material, through a fuel assembly instrument thimble insert, into the existing instrument thimbles in nuclear fuel assemblies for the purpose of allowing the material to be converted to commercially valuable quantities of desired radioisotopes during reactor power operations during a remainder of a fuel cycle and removing the radioisotopes from the core through the reactor flange opening once the fuel assemblies have been removed for refueling. The invention also describes methods that can be used to harvest the irradiated material so it can be packaged for transportation from the reactor to a location where the desired radioisotope(s) can be extracted from the fuel assembly instrument thimble insert. 18-. (canceled)9. A method of irradiating an isotope that requires an extended exposure within a nuclear reactor lasting at least one fuel cycle , to achieve an intended target product , comprising the steps of:enclosing the isotope within an elongated tubular housing having an axis along its elongated dimension, the elongated tubular housing being closed at a forward end and capped at a rearward end to form a target specimen chamber therebetween within an interior of the elongated tubular housing, the elongated tubular housing being sized to slide within an instrument thimble of a nuclear fuel assembly, with the rearward end structured to be driven by a drive cable of an existing moveable in-core detector system;positioning the isotope at a preselected axial position within the elongated tubular housing;attaching the rearward end to the drive cable;driving the isotope within the elongated tubular housing into and at least partially through an instrument thimble of a selected nuclear fuel assembly within a core of a nuclear reactor;leaving the isotope within the instrument thimble for the remainder of a fuel cycle of the core;withdrawing the elongated tubular housing from the core at the end of the fuel cycle;removing the selected fuel assembly ...

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Номер записи: 76
26-03-2015 дата публикации

RECOVERING AND RECYCLING URANIUM USED FOR PRODUCTION OF MOLYBDENUM-99

Номер: US20150085963A1
Автор: COPPING Roy, Dale Gregory Edward, MAY Iain, REILLY Sean Douglas
Принадлежит: Los Alamos National Security, LLC

A processes for recycling uranium that has been used for the production of molybdenum-99 involves irradiating a solution of uranium suitable for forming fission products including molybdenum-99, conditioning the irradiated solution to one suitable for inducing the formation of crystals of uranyl nitrate hydrates, then forming the crystals and a supernatant and then separating the crystals from the supernatant, thus using the crystals as a source of uranium for recycle. Molybdenum-99 is recovered from the supernatant using an adsorbent such as alumina. Another process involves irradiation of a solid target comprising uranium, forming an acidic solution from the irradiated target suitable for inducing the formation of crystals of uranyl nitrate hydrates, then forming the crystals and a supernatant and then separating the crystals from the supernatant, thus using the crystals as a source of uranium for recycle. Molybdenum-99 is recovered from the supernatant using an adsorbent such as alumina. 1. A process for recycling uranium that has been used for the production of molybdenum-99 (Mo-99) , comprising:providing an aqueous solution comprising uranyl nitrate and nitric acid, the nitric acid comprising a first concentration, the uranium concentration comprising a first concentration, said uranyl nitrate comprising uranium,irradiating the solution to produce soluble fission products that comprise Mo-99, and thereafter,adjusting the nitric acid concentration to a second concentration, adjusting the uranium concentration to a second concentration, the combined second concentrations being suitable for inducing the formation of crystals of uranyl nitrate hydrates, and a supernatant,inducing the formation of crystals of uranyl nitrate hydrates, and a supernatant, andseparating the crystals from the supernatant, thereby recycling uranium that has been used for the production of Mo-99.2. The process of claim 1 , wherein the uranium is low enriched uranium.3. The process of claim ...

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Номер записи: 77
26-03-2015 дата публикации

RECOVERY OF URANIUM FROM AN IRRADIATED SOLID TARGET AFTER REMOVAL OF MOLYBDENUM-99 PRODUCED FROM THE IRRADIATED TARGET

Номер: US20150085964A1
Автор: COPPING Roy, Dale Gregory Edward, MAY Iain, REILLY Sean Douglas
Принадлежит: Los Alamos National Security, LLC

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. 1. A process for recovering uranium from an irradiated solid target after recovering molybdenum-99 (Mo-99) produced from the irradiated target , comprising:irradiating a solid target comprising uranium to produce fission products comprising Mo-99, and thereafterdissolving the target to form a solution and conditioning the solution to provide an aqueous nitric acid solution comprising a first acid concentration and a first uranium concentration, and thereaftercontacting this solution with a solid sorbent, whereby uranium remains in the nitric acid while the Mo-99 is bound to the sorbent for subsequent retrieval,adjusting the concentration of nitric acid and the concentration of uranium in the solution to concentrations suitable for crystallization of uranyl nitrate hydrates, and thereafterinducing the crystallization of uranyl nitrate hydrates, andseparating the uranyl nitrate hydrates crystalline product from ...

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Номер записи: 78
23-03-2017 дата публикации

SLURRY DISPENSER FOR RADIOISOTOPE PRODUCTION

Номер: US20170080393A1
Автор: Mahoney Michael R., Worley Mark D.
Принадлежит:

A slurry dispensing system is disclosed. A peristaltic pump may direct a flow of slurry out of a horizontal mixer to a slurry dispenser. This slurry dispenser may be operated on a programmed manner by a controller to dispense slurry into a container. Both a bypass valve and a dispensing valve of the slurry dispenser may be opened/closed on a programmed basis by the controller to deliver slurry to a container, such as a glass column. Slurry may be intermittently directed into a metering chamber of the slurry dispenser, while the remainder of the slurry being directed into the slurry dispenser may be recirculated back to the horizontal mixer. 1. A slurry dispensing system comprising: 1) a slurry mixer comprising a mixer outlet and a mixer recirculation port; and 2) a slurry dispenser fluidly connectable with said slurry mixer and comprising:a housing assembly comprising a plurality of separate housings that are disposed in a stack;a slurry bypass channel fluidly connectable with each of said mixer outlet and said mixer recirculation port, wherein said slurry bypass channel extends completely through said housing assembly;a slurry flow channel that extends from said slurry bypass channel, that is disposed within said housing assembly, and that proceeds through said stack to a perimeter of said housing assembly, wherein said slurry flow channel comprises a metering chamber;a metering chamber inlet valve between said slurry bypass channel and said metering chamber; anda metering chamber outlet valve for said metering chamber.2. The slurry dispensing system of claim 1 , further comprising:at least one feed source fluidly connectable with said slurry mixer, wherein a fluid and a plurality of particles are directed into said slurry mixer by said at least one feed source, and wherein a discharge out of said mixer outlet comprises a slurry.3. The slurry dispensing system of claim 1 , wherein said slurry mixer comprises a horizontal mixer.4. The slurry dispensing system of ...

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Номер записи: 79
12-06-2014 дата публикации

68Ga Generator

Номер: US20140163211A1
Автор: Nikula Tuomo, Zhernosekov Konstantin
Принадлежит: ITM ISOTOPEN TECHNOLOGIEN MÜNCHEN AG

The present invention relates to a Ga generator, wherein the Ge parent nuclide thereof is attached specifically to a support through a triethoxyphenyl group and continuously disintegrates to Ga, the triethoxyphenyl group being covalently bound to a support material through a linker. 1. A generator for a Gallium (Ga) daughter nuclide , wherein the Germanium (Ge) parent nuclide thereof is attached specifically to a support through a trihydroxyphenyl group or a dihydroxyphenyl group and continuously disintegrates to Ga by electron capture at a half-life of 270.82d ,whereinthe trihydroxyphenyl group or dihydroxyphenyl group is covalently bound via a linker to a support material,{'sub': 2', '2', '2', '2', '3', '2', '2, 'the support material is selected from the group consisting of: inorganic inert oxide materials, in particular silica gel, SiO, TiO, SnO, AlO, ZnO, ZrO, HfO, organic inert polymers and copolymers, in particular styrene-divinylbenzene, polystyrene, styrene-acrylonitrile, styrene-acrylonitrile-methylmethacrylate, acrylonitrile-methylmethacrylate, polyacrylonitrile, polyacrylates, acrylic or methacrylic esters, acrylonitrile-unsaturated dicarboxylic acid-styrene, vinylidene chloride-acrylonitrile, and'}{'sub': 2', '20', '2', '20', '2', '20, 'the linker being selected from the group consisting of: Cto Cesters; Cto Calkyls, phenyl, thiourea, C-Camines, maleimide, melamine, trihydroxyphenyl alkoxsilanes, in particular 1,2,3-trihydroxyphenyltriethoxysilane, 1,2,3-trihydroxyphenyldiethoxysilane, 1,2,3-trihydroxyphenylethoxysilane, 1,2,3-trihydroxyphenyltripropoxysilane, 1,2,3-trihydroxyphenylchlorosilane, epichlorohydrin, isothiocyanates, thiols, wherein the trihydroxyphenyl group is 1,2,3-trihydroxybenzene (pyrogallol).'}2. The Ga generator of claim 1 , wherein silica gel is employed as a support material claim 1 , and 1 claim 1 ,2 claim 1 ,3-trihydroxyphenyltriethoxysilane is employed as a linker.3. The Ga generator of claim 2 , wherein the Ge-charged ...

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Номер записи: 80
14-03-2019 дата публикации

Shielding Device

Номер: US20190080808A1
Автор: Herbrink Maikel, Schreuder Nanno, Swiers Gerard
Принадлежит: GE HEALTHCARE LIMITED

The present invention relates to the field of radioactive substances and in particular to a method to facilitate handling of radioactive solutions. Provided by the present invention is a device that enables preparation of capsules filled with radioactivity. More particularly, the radioactivity is suitable for use in certain radiopharmaceutical procedures. The present invention provides improved accuracy and uniformity of patient doses. Furthermore, the potential for spills and needle stick injuries is reduced and the radiation burden is reduced. 1. A system comprising:(i) a capsule holder having a lower end and an upper end wherein said capsule holder comprises a solid base positioned at said lower end, a solid body extending upwardly from said solid base, and a well extending downwardly within said solid body wherein said well opens at the upper end of said capsule holder and ends prior to said solid base and is configured to receive a lower half of a capsule, wherein said capsule holder is formed from a radiation-shielding material; and(ii) a shielded needle positioner having a lower end and an upper end wherein said shielded needle positioner comprises a solid body defining a bore extending substantially linearly and centrally therethrough, said bore comprising a lower section opening onto said lower end and configured to be fitted over and contain the solid body of said capsule holder, and an upper section opening onto said upper end and configured to receive an upper half of a capsule, wherein said shielded needle positioner is formed from a radiation-shielding material.2. The system of claim 1 , wherein said shielded needle positioner further comprises a cap configured to fit over the upper end thereof wherein said cap comprises a bore therethrough having a similar width to the upper section of the bore of the shielded needle positioner claim 1 , wherein said cap is formed from a radiation-shielding material.3. The system of claim 1 , wherein the radiation- ...

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Номер записи: 81
21-03-2019 дата публикации

HIGH PURITY THERAPEUTIC BONE AGENTS

Номер: US20190083661A1
Автор: Frank R. Keith, Simon Jaime, WILSON David A.
Принадлежит: IsoTherapeutics Group, LLC

This invention relates to radioactive, bone-seeking, pharmaceutical methods, compositions and formulations that have a lower impurity profile, a longer shelf life, improved availability and are less expensive to prepare. The compositions of this invention can be conveniently prepared in a timely manner resulting in improved availability and delivery of the drugs to patients. 1. A method for the treatment of a Patient comprising administration to the Patient having bone pain , one or more calcific tumors , or in need of a bone marrow suppressing procedure , a pharmaceutically-acceptable , formulation of a chelate composition comprising a Clinically Relevant Dosage of the composition that is therapeutically effective , said composition either:i) has said formulation as a chelate composition consisting essentially of Sm-153 and DOTMP or a physiologically-acceptable salt thereof, orii) has said formulation comprising a kit containing as two separate components, the DOTMP chelant and the Sm-153 isotope, which components are mixed to form the chelate composition at the appropriate time prior to use,wherein the Sm-153 isotope possesses an extended Expiration Date of greater than or equal to about 5 days, and wherein the Sm-153 dosage is at least 35 mCi;with the proviso that the chelate composition is prepared by a process comprising the steps of:{'sup': '2', 'a) irradiating Sm-152 in a lower flux portion of the nuclear reactor having less than 8.5×1013 neutron/cm-sec to form low specific activity Sm-153, wherein the isotope composition after the irradiation contains mainly Sm-152 and Sm-153 with reduced trace impurity of Eu-154 less than 0.093 μCi Eu-154/mCi Sm-153 after 5 days of decay, thereby providing an extended Expiration Date greater than or equal to about 5 days;'}b) taking the prepared isotope mixture from step a) and either using it in step c) or allowing it to decay and then using it in step c) which decay further lowers the specific activity of the Sm-153 ...

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Номер записи: 82
02-04-2015 дата публикации

AQUEOUS ASSEMBLY AND CONTROL METHOD

Номер: US20150092900A1
Автор: Piefer Gregory, Van Abel Eric N.
Принадлежит:

An aqueous assembly has a negative coefficient of reactivity with a magnitude. The aqueous assembly includes a vessel and an aqueous solution, with a fissile solute, supported in the vessel. A reactivity stabilizer is disposed within the aqueous solution to reduce the magnitude of the negative coefficient of reactivity of the aqueous assembly during operation of the aqueous assembly. 1. An aqueous assembly having a negative coefficient of reactivity , the aqueous assembly comprising:a vessel;an aqueous solution, including a fissile solute, supported in the vessel; anda reactivity stabilizer disposed within the aqueous solution to reduce a magnitude of the negative coefficient of reactivity of the aqueous assembly during operation of the aqueous assembly.2. The aqueous assembly of claim 1 , wherein the coefficient of reactivity is a solution temperature coefficient of reactivity.3. The aqueous assembly of claim 1 , wherein the coefficient of reactivity is a solution void coefficient of reactivity.4. The aqueous assembly of claim 1 , wherein the fissile solute includes uranium.5. The aqueous assembly of claim 1 , wherein the fissile solute includes at least one of uranyl nitrate claim 1 , uranyl sulfate claim 1 , and uranyl fluoride.6. The aqueous assembly of claim 1 , wherein the reactivity stabilizer includes boron-10.7. The aqueous assembly of claim 1 , wherein the reactivity stabilizer includes boric acid.8. The aqueous assembly of claim 1 , wherein the reactivity stabilizer includes at least one of gadolinium-155 and gadolinium-157.9. The aqueous assembly of claim 1 , wherein the reactivity stabilizer is a solute of the aqueous solution.10. The aqueous assembly of claim 1 , wherein the aqueous assembly is subcritical claim 1 , the aqueous assembly further comprising a neutron source for maintaining a fission reaction within the vessel.11. The aqueous assembly of claim 1 , wherein the aqueous assembly is capable of critical operation.12. The aqueous assembly of ...

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Номер записи: 83
30-03-2017 дата публикации

PRODUCTION OF 43SC RADIONUCLIDE AND RADIOPHARMACEUTICALS THEREOF FOR USE IN POSITRON EMISSION TOMOGRAPHY

Номер: US20170087260A1
Автор: BUNKA MARUTA, TUERLER ANDREAS, VAN DER MEULEN NICHOLAS
Принадлежит:

The radionuclide Sc is produced at commercially significant yields and at specific activities and radionuclidic purities which are suitable for use in radiodiagnostic agents including imaging agents. In a method, a solid target having an isotopically enriched target layer prepared on an inert substrate is positioned in a specially configured target holder and irradiated with a charged-particle beam of protons or deuterons. The beam is generated using an accelerator such as a biomedical cyclotron at energies ranging from 3 to about 22 MeV. The method includes the use of three different nuclear reactions: a) irradiation of enriched Ca targets with protons to generate the radionuclide Scin the nuclear reaction Ca (p,n)Sc, b) irradiation of enriched Ca targets with deuterons to generate the radionuclide Sc in the nuclear reaction Ca(d,n)Sc, and c) irradiation of enriched Ti targets with protons to generate the radionuclide Sc in the nuclear reaction Ti (p,a)Sc. 17-. (canceled)8. A method for generating Sc , wherein one of the following method steps is applied:{'sup': 43', '43', '43, 'performing a nuclear reaction of Ca(p,n)Sc using enriched Ca at proton beam energies of 5 to 24 MeV;'}{'sup': 42', '43', '42, 'performing a nuclear reaction of Ca(d,n)Sc using enriched Ca and deuteron beam energies of 3 to 12 Mev; or'}{'sup': 46', '43', '46, 'performing a nuclear reaction of Ti(p,α)Sc using enriched Ti and proton beam energies of 10 to 24 MeV.'}9. The method according to claim 8 , which further comprises:{'sup': 43', '43', '43', '43, 'sub': 3', '3', '2', '2, 'irradiating the enriched Ca target in form of CaCO, Ca (NO), CaFor CaO powders of Ca metal having a Ca content of 50% or higher with the proton beam thereby turning the Ca content into the Sc;'}{'sup': 43', '43, 'dissolving an irradiated enriched Ca target in acidic solution and passing a resulting solution through a first column loaded with DGA resin in order to absorb Sc ions;'}{'sup': 43', '43, 'eluting absorbed Sc ...

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Номер записи: 84
21-03-2019 дата публикации

Method of Production of Radio Active Isotopes in Fast Neutron Nuclear Reactor

Номер: US20190088379A1
Автор: "ASMOLOV Vladimir Grigorevich", "BAKANOV Mikhail Vasilevich", "KLINOV Dmitriy Anatolevich", "KONDRATEV Nikolay Aleksandrovich", "VASILEV Boris Aleksandrovich", DUB Aleksey Vladimirovich, KOZMANOV Evgeniy Aleksandrovich, PERSHUKOV Vyacheslav Aleksandrovich, RISOVANYY Vladimir Dmitrievich, SILIN Boris Georgievich
Принадлежит:

A method of radioactive isotopes production in Fast Neutron Nuclear Reactor. The targets for radio nuclides production are being placed in the radiation assembly between the plumbs made of neutrons slowing materials, and the radiation assembly is being placed in the side screen of Fast Neutron Nuclear Reactor. The assemblies not containing nuclear fuel are placed around the radiation assembly. Fast neutrons are passed through the neutrons slowing material and then the slowed neutrons are passed through the radiated material (targets) in radiation assembly. The radio isotopes production is done simultaneously in radiation assembly and surrounding assemblies with content of steel less than 50%. The targets of radiation assembly have the absorption cross-section over 1 barn with neutrons energy less than 0.1 MeV. The targets of assemblies surrounding the radiation assembly have the neutrons absorption cross-section less than 1 barn with neutrons energy over 0.1 MeV. 1. The method production of radioactive isotopes in Fast Neutron Nuclear Reactor , includingplacing of radio nuclides production target in the radiation assembly containing neutrons slowing materials.placing of radiation assembly into the side screen of Fast Neutron Nuclear Reactor among assemblies not containing nuclear fuel.passing of fast neutrons through neutrons slowing materials in radiation assembly.passing of slowed neutrons through targets in radiation assemblycharacterised in thatproducing of radio nuclides is being done simultaneously in radiating and surrounding steel assembliesthe targets for production of radio nuclides in radiation assembly have the neutrons absorption cross-section over 1 barn with neutrons energy less than 0.1 MeV;the targets for production of radio nuclides in assemblies surrounding the radiation assembly have the neutrons absorption cross-section less than 1 barn with neutrons energy over 0.1 MeV, and the content of steel in assembly does not exceed 50%.2. The method ...

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Номер записи: 85
19-03-2020 дата публикации

METHOD FOR EVALUATING STRUCTURE USED FOR NUCLIDE TRANSMUTATION REACTION, EVALUATION DEVICE, STRUCTURE MANUFACTURING DEVICE PROVIDED WITH SAME, AND NUCLIDE TRANSMUTATION SYSTEM

Номер: US20200088629A1
Автор: Tsuruga Shigenori
Принадлежит: MITSUBISHI HEAVY INDUSTRIES, LTD.

A method for evaluating a structure is disclosed, the structure including a base material containing at least one kind of metal selected from the group consisting of hydrogen storage metals and hydrogen storage alloys, an intermediate layer provided on the base material and stacked alternately with a first layer containing low work function substances relatively lower in work function than the metal and a second layer containing the metal, and a surface layer provided on the intermediate layer and containing the metal, wherein the method includes measuring a change in polarization between incident light and reflected light by irradiating the surface layer with light, while holding the structure at a predetermined temperature, and comparing a measurement value of the change in polarization with a threshold of a change in polarization of a structure prepared in advance and evaluating a soundness of the structure based on comparison results. 110-. (canceled)11. A method for evaluating a structure to be used for nuclide transmutation reaction , the structure including a base material containing at least one kind of metal selected from the group consisting of hydrogen storage metals and hydrogen storage alloys , an intermediate layer provided on the base material and stacked alternately with a first layer containing low work function substances relatively lower in work function than the metal and a second layer containing the metal , and a surface layer provided on the intermediate layer and containing the metal , wherein the method comprises:measuring a change in polarization between incident light and reflected light by irradiating the surface layer with light, while holding the structure at a predetermined temperature;calculating an extinction coefficient based on the change in polarization of the structure,preliminarily setting a threshold of the extinction coefficient based on a relationship between an extinction coefficient of a structure prepared in advance and a ...

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Номер записи: 86
26-06-2014 дата публикации

Cabinet structure configurations for infusion systems

Номер: US20140175959A1
Автор: Charles R. Quirico, Daniel V. Clements, Ernest Balestracci, Jacob S. Childs, Janet L. Gelbach, Peter B. Madson
Принадлежит: Bracco Diagnostics Inc

A cabinet structure for an infusion system includes a platform, on which the system is mounted, and a shell surrounding an interior space, which contains at least a portion of the system. The shell preferably includes an opening that is sized and oriented to allow a lowering of a radioisotope generator, for the system, into the interior space, and a lifting of the generator out from the interior space. The shell may further include another opening, located at a higher elevation than the aforementioned opening, in order to provide access to a waste bottle of the infusion system.

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Номер записи: 87
12-05-2022 дата публикации

PURIFICATION OF ACTINIUM

Номер: US20220145423A1
Автор: CARDINAELS Thomas, MAERTENS Dominic, VAN HECKE Karen
Принадлежит:

A method for purifying Ac from a mixture includes Ac and at least one element selected from Ra, Pb, Po, Bi and La. The method includes the steps of: (a) performing a first separation using a first extraction chromatographic column based on a first resin (either a diglycolamide resin or a dialkylphosphoric acid resin) and a first matrix solution; and (b) performing a second separation using a second extraction chromatographic column based on a second resin (respectively either a dialkylphosphoric acid resin or a diglycolamide resin). 116.-. (canceled)17. A method for purifying Ac from a mixture comprising Ac and at least one element selected from Ra , Pb , Po , Bi and La , the method comprising: a1. loading the mixture on a first extraction chromatographic column based on a first resin and a first matrix solution,', 'a2. washing the mixture loaded on the first extraction chromatographic column with a first washing solution, and', 'a3. eluting the mixture loaded on the first extraction chromatographic column with a first eluent to obtain a first eluate; and, 'a. performing a first separation, comprising'} b1. loading the first eluate on a second extraction chromatographic column based on a second resin and a second matrix solution,', 'b2. washing the first eluate loaded on the second extraction chromatographic column with a second washing solution, and', 'b3. eluting the first eluate loaded on the second extraction chromatographic column with a second eluent to obtain a second eluate containing the purified Ac;, 'b. performing a second separation, comprising'}wherein eitherthe first resin is a diglycolamide resin, the first matrix solution has a pH between −0.8 and 0, the first washing solution has a pH between −0.8 and 0 and the first eluent has a pH between 1 and 4, andthe second resin is a dialkyl phosphoric acid resin, the second matrix solution has a pH between 1 and 4, the second washing solution has a pH between 1 and 4 and the second eluent has a pH between −0 ...

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Номер записи: 88
19-03-2020 дата публикации

Method for Enhanced Nuclear Reactions

Номер: US20200090822A1
Автор: Lo Shui Yin
Принадлежит:

A method for enhanced nuclear reactions includes the steps of providing a first target which is a thin film with solid deuterium; providing a deuteron beam having an extreme ultraviolet laser and a first infrared laser to apply on the first target to ionize the deuterium to form positive charged deuterons and electrons; providing a second infrared laser to the first target to accelerate the electrons and the positively charged deuterons; separating the accelerated electrons and the accelerated positively charged deuterons under a magnetic field; providing the accelerated electrons to move in a circular motion and the accelerated positive charger deuterons to move to form a cluster of accelerated positively charged deuterons, and breaking the cluster of accelerated positive charged deuterons into small pieces of positively charged deuterons. 1. A method for enhanced nuclear reactions , comprising the steps of:providing a first target which is a thin film with solid deuterium;providing an extreme ultraviolet laser and first infrared lasers to apply on the first target to ionize the deuterium to form positive charged deuterons and electrons;providing a second infrared laser to the first target to accelerate the electrons and the positively charged deuterons;separating the accelerated electrons and the accelerated positively charged deuterons under a magnetic field;providing the accelerated electrons to move in a circular motion and the accelerated positive charger deuterons to move to form a cluster of accelerated positively charged deuterons; andbreaking the cluster of accelerated positive charged deuterons into small pieces of positively charged deuterons.2. The method for enhanced nuclear reactions claim 1 , as recited in claim 1 , wherein the first target is selected from a group consisting of lithium 7 and boron 11.3. The method for enhanced nuclear reactions claim 1 , as recited in claim 1 , wherein the nuclear reaction is a deuteron-deuterons reaction.4. The ...

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Номер записи: 89
19-03-2020 дата публикации

PNEUMATICALLY OPERATED TARGET IRRADIATION SYSTEMS FOR THE PRODUCTION OF RADIOISOTOPES

Номер: US20200090824A1
Автор: Alboino Mark A., Fisher Benjamin D., Long Andrew F., Onderwater Thomas G.
Принадлежит:

A target irradiation system for irradiating a radioisotope target in a vessel penetration of a fission reactor, including a target elevator assembly including a body portion defining a central bore and an open bottom end, a center tube that is disposed within the central bore of the body portion, a target basket that is slidably receivable within the center tube, and a winch that is connected to the target basket by a cable, wherein the target basket is configured to receive the radioisotope target therein and be lowered into the vessel penetration of the reactor when irradiating the radioisotope target. 1. A target irradiation system for irradiating a radioisotope target in a vessel penetration of a fission reactor , comprising:a target elevator assembly including a body portion defining a central bore and an open bottom end, a center tube that is disposed within the central bore of the body portion, a target basket that is slidably receivable within the center tube, and a winch that is connected to the target basket by a cable, the target elevator assembly being affixed to the vessel penetration of the reactor; anda target passage that is in fluid communication with the target elevator assembly,wherein the target basket is configured to receive the radioisotope target therein via the target passage and be lowered into the vessel penetration of the reactor when irradiating the radioisotope target, and the target elevator assembly forms a portion of the pressure boundary of the reactor when in fluid communication with the reactor.2. The target irradiation system of claim 1 , wherein the fission reactor is a heavy-water moderated fission reactor and the vessel penetration is an adjuster assembly port.3. The target irradiation system of claim 2 , wherein the radioisotope target is comprised of natural molybdenum.4. The target irradiation system of claim 1 , wherein the target elevator assembly is affixed to the vessel penetration so that a portion of the body portion ...

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Номер записи: 90
12-05-2022 дата публикации

Methods of producing enriched scandium-47, and related systems and apparatuses

Номер: US20220148752A1
Автор: Mathew S. Snow, Mathew T. Kinlaw
Принадлежит: Battelle Energy Alliance Llc

A method of producing enriched 47 Sc comprises irradiating a V structure comprising 51 V with at least one incident photon beam having an endpoint energy within a range of from about 14 MeV to about 44 MeV to convert at least some of the 51 V to 47 Sc and form a 47 Sc-containing structure. The 47 Sc of the 47 Sc-containing structure is separated from additional components of the 47 Sc-containing structure using a chromatography process. Systems and apparatuses for producing enriched 47 Sc are also described.

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Номер записи: 91
12-05-2022 дата публикации

ACCELERATOR-DRIVEN NEUTRON ACTIVATOR FOR BRACHYTHERAPY

Номер: US20220148753A1
Автор: BUONO Stefano, MACIOCCO Luca
Принадлежит:

A neutron activator for neutron activation of a material, the neutron activator being configured to produce neutrons from an interaction with a proton beam (), the neutron activator comprising: 1. A neutron activator for neutron activation of a material , the neutron activator being configured to produce neutrons from an interaction with a proton beam emitted along a beam axis , the proton beam having an energy comprised between 16 MeV and 100 MeVr and a beam intensity up to 1 mA , the neutron activator comprising:a neutron source comprising a metallic target presenting a longitudinal axis intended to be arranged parallel to the beam axis, wherein the metallic target has a hollow conical shape, the longitudinal axis of said conical shape being aligned with the proton beam, anda Beryllium first reflector-moderator peripheral to the neutron source and comprising a neutron activation area configured to accommodate the neutron source and the material to be activated, the neutron activation area of the first reflector-moderator comprising a bore extending along a bore axis and configured to accommodate the neutron source so that the bore axis and the longitudinal axis are coaxial.2. The neutron activator according to claim 1 , wherein the neutron activation area of the first reflector-moderator further includes at least one activation channel extending along a channel axis parallel to the bore axis at the vicinity of the bore claim 1 , the activation channel being configured to load the material to be activated.3. The neutron activator according to claim 2 , wherein the neutron activation area comprises a plurality of activation channels distributed claim 2 , around the bore.411. The neutron activator of claim 1 , further comprising a cooling area in direct contact with an outer surface of the target () for receiving a flow of fluid for cooling the target () during neutron generation.5. The neutron activator according to claim 1 , wherein the aperture of the hollow ...

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Номер записи: 92
13-04-2017 дата публикации

INTEGRATED STRONTIUM-RUBIDIUM RADIOISOTOPE INFUSION SYSTEMS

Номер: US20170100535A1
Автор: Fontaine Aaron M., Gelbach Janet L., Hidem Stephen E., Hunter Kathryn M., McDonald Patrick M., Swenson Rolf E., ZODDA Julius P.
Принадлежит:

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. 1. A strontium-rubidium radioisotope infusion system comprising: a platform having a topside and an underside;', 'an exterior shell that extends upwardly from the platform and has a front side, a rear side, two sidewalls connecting the front side to the rear side, and a top surface, wherein the platform and the exterior shell collectively define an interior space of the cabinet structure;', 'four wheels mounted to the underside of the platform;', 'an opening through the front side of the exterior shell configured to provide access to a strontium-rubidium radioisotope generator within the interior space of the cabinet structure;', 'an opening through the top surface of the exterior shell configured to provide access to a waste bottle within the interior space of the cabinet structure; and', 'a handle facing rearwardly and being configured for a person to grasp in order to move the strontium-rubidium radioisotope infusion system;, 'a cabinet structure that comprisesa touch screen display mounted to a pole extending upwardly from the cabinet structure, thereby positioning the touch screen display at an elevation above the top surface of the cabinet structure, wherein the touch screen display is configured to receive input from a user for controlling operation of the strontium-rubidium radioisotope infusion system;a computer configured to control operation of the ...

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Номер записи: 93
04-04-2019 дата публикации

COMPACT ASSEMBLY FOR PRODUCTION OF MEDICAL ISOTOPES VIA PHOTONUCLEAR REACTIONS

Номер: US20190103198A1
Автор: BROWN Michael Alexander, Chemerisov Sergey D., Henning Walter F., Jr. Jerry A., Nolen, Rotsch David A., Song Jeongseong
Принадлежит: UCHICAGO ARGONNE, LLC

The invention provides a method for generating medical isotopes, the method comprising contacting a primary radiation beam with a converter for a time sufficient to produce a secondary beam of gamma particles, and contacting the beam of gamma particles to a target, where the cross section dimension of the beam of gamma particles is similar to the cross section dimension of the target. Both the converter and target are small in diameter and very closely spaced. Also provided is a system for producing medical isotopes, the device comprising a housing having a first upstream end and a second downstream end, a radiotransparent channel (collimator) with a first upstream end and a downstream end, wherein the upstream end is adapted to receive a radiation beam, a target positioned downstream of the downstream end of the channel and coaxially aligned with the channel, wherein the target has a cross section that is similar to the cross section of the channel. 1. A method for generating medical isotopes , the method comprising:a) supplying a target enriched in a specific isotope; andb) impinging a radiation beam onto the target for a time sufficient to produce medical isotopes, wherein a cross section of the beam is approximately same as a cross section of the target.2. The method as recited in further comprising a converter positioned between the beam and the target.3. The method as recited in wherein the beam traverses a collimator which limits the beam diameter to be slightly smaller than the diameter of the converter.4. The method as recited in wherein a coolant is in thermal communication with the collimator claim 3 , the converter claim 3 , and the target.5. The method as recited in wherein the radiation beam is comprised of electrons with an energy between 30 MeV and 45 MeV with beam total beam power approximately 10 to 20 kW.6. The method as recited in wherein the target is 226Ra and 225Ac is the medical isotope produced.7. The method as recited in wherein only about ...

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Номер записи: 94
21-04-2016 дата публикации

PRODUCTION OF ISOTOPES USING HIGH POWER PROTON BEAMS

Номер: US20160111176A1
Автор: Gomes Itacil C., Jr. Jerry A., Nolen
Принадлежит: UCHICAGO ARGONNE, LLC

The invention provides for a method for producing isotopes using a beam of particles from an accelerator, whereby the beam is maintained at between about 70 to 2000 MeV; and contacting a thorium-containing target with the particles. The medically important isotope Ac is produced via the nuclear reaction (p,2p6n),whereby an energetic proton causes the ejection of 2 protons and 6 neutrons from a Th target nucleus. Another medically important isotope Bi is then available as a decay product. The production of highly purified At is also provided. 1. A method for producing astatine isotope , the method comprising:a. irradiating a thorium target for a time and at an energy sufficient to produce radon isotopes;b. extracting the radon isotopes from the target;c. condensing and purifying the extracted radon isotopes; andd. generating At from the purified radon isotopes.2. The method as recited in wherein the target is irradiated with protons maintained at an energy of about 100 to 400 MeV.3. The method as recited in wherein At is generated from the decay of Rn and chemically separated from radon gas.4. The method as recited in wherein the step of extracting the radon isotopes from the target comprises heating the irradiated target.5. The method as recited in wherein the radon is extracted along with co-extractants as a gas mixture and the step of purifying the radon comprises subjecting the gas mixture to a cold trap to separate the co-extractants from radon.6. The method as recited in wherein the radon remains in vapor phase.7. The method as recited in wherein the radon is continuously extracted from the target. This Utility Patent Application claims priority benefit as a Divisional of U.S. Non-Provisional Application No. 13/025,079, filed on Feb. 10, 2011, presently pending, which in turn claims priority benefit as a Non-Provisional Application of U.S. Provisional Application No. 61/303,023 filed on Feb. 10, 2010, presently expired, the entirety of both Applications ...

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Номер записи: 95
19-04-2018 дата публикации

RADIONUCLIDE GENERATION SYSTEM AND METHOD OF PRODUCING RADIONUCLIDES

Номер: US20180108445A1
Автор: RICHTER Thomas Fabian, Sykora Alexander, WISTUBA Lothar
Принадлежит:

A method of producing radionuclides from irradiation targets in a nuclear reactor uses at least one instrumentation tube system of a commercial nuclear reactor. Irradiation targets and dummy targets are inserted into an instrumentation finger and the irradiation targets are activated by exposing them to neutron flux in the nuclear reactor core to form a radionuclide. The dummy targets hold the irradiation targets at a predetermined axial position in the reactor core corresponding to a pre-calculated neutron flux density sufficient for converting the irradiation targets to the radionuclide. Separating the dummy targets from the activated irradiation targets includes exposure to a magnetic field to retain either the dummy targets or the activated irradiation targets in the instrumentation tube system and release the other one of the activated irradiation target or the dummy target from the instrumentation tube system. An apparatus adapted to the above method is also provided. 128.-. (canceled)29. A method of producing radionuclides from irradiation targets in a nuclear reactor comprising the steps of:providing at least one instrumentation tube system including an instrumentation finger passing through a core of the nuclear reactor;inserting at least one irradiation target and at least one dummy target into the instrumentation finger and activating the irradiation target to form an activated irradiation target by exposing the irradiation target to neutron flux in the nuclear reactor core to form a radionuclide;retrieving the dummy target and the activated irradiation target from the instrumentation finger and separating the dummy target from the activated irradiation target;wherein the dummy target and the irradiation target are arranged in the instrumentation finger in a linear order such that the dummy target holds the irradiation target at a predetermined axial position in the reactor core, said axial position corresponding to a pre-calculated neutron flux density ...

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Номер записи: 96
20-04-2017 дата публикации

Method to produce a high-purity Zr-89 through physical irradiation and measurement thereof

Номер: US20170110211A1
Автор: CHU Han-Hsiang, Duh Ting-Shien, LI MING-HSIN, Lin Wuu-Jyh
Принадлежит:

A method to produce a high-purity Zr-89 on a solid target through physical irradiation and measurement by selecting a target Barn value of the cross-sectional area of nuclear reaction, drawing a horizontal line to intersect at two points on the function diagram curve and drawing a vertical line downward from each of the two points intersecting at X-axis to obtain incident energy values at the two intersecting points on the X-axis, and followed by plotting an attenuation function diagram curve of penetration depth versus incident energy of Y-89(p,n)Zr-89, selecting an attenuation function diagram curve and a minimum attenuation position of the selected attenuation function diagram curve in correspondence to the incident energy in the interval of incident energy absorption range to obtain an optimal plating thickness value on the solid target. 1. A method of physical irradiation and measurement for producing a high purity Zr-89 on a solid target , comprising steps:{'b': '11', 'Step S, plotting a function diagram curve of nuclear incident energy versus reaction cross-sectional area for each of Y-89(p, n) Zr-89 and relevant radionuclide zirconium (Zr)-88, zirconium (Zr)-87, and the kinds in accordance with each of their atomic physical characteristics, and providing an equation for the function diagram curve;'}{'b': 12', '1', '2, 'Step S, selecting a target Barn value of the cross-sectional area of nuclear reaction and drawing a horizontal line to intersect at two points on the function diagram curve of nuclear incident energy versus reaction cross-sectional area, followed by drawing a vertical line downward from each of the two points on the function diagram curve and intersecting at X-axis to obtain incident energy values (E, E) at the two intersecting points on the X-axis;'}{'b': 13', '1', '2', '1', '2, 'Step S, substituting the two incident energy values (E, E) into the equation of each of the function diagram curve of nuclear incident energy versus reaction cross- ...

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Номер записи: 97
10-07-2014 дата публикации

MOLYBDENUM-CONVERTER BASED ELECTRON LINEAR ACCELERATOR AND METHOD FOR PRODUCING RADIOISOTOPES

Номер: US20140192942A1
Автор: Tsechanski Alexander
Принадлежит: BEN-GURION UNIVERSITY OF THE NEGEV, RESEARCH AND DEVELOPMENT AUTHORITY

The present invention provides a method for producing molybdenum-99 comprising: i) providing an electron accelerator; ii) providing a molybdenum converter/target unit (Mo-CTU) comprising one or more metallic components, wherein each one of said metallic components is made of a material selected from the group consisting of natural molybdenum, molybdenum-100, molybdenum-98, and mixtures thereof; iii) directing an electron beam generated via said electron accelerator onto said Mo-CTU to produce a braking radiation (bremsstrahlung); iv) employing said bremsstrahlung onto said Mo-CTU to produce molybdenum-99 and neutrons via a photo-neutron reaction; v) slowing down the neutrons produced in step iv) with a low atomic liquid, e.g. distilled water; and optionally vi) employing the neutrons produced in step iv) to produce a complementary amount of molybdenum-99 via a neutron capture reaction on said Mo-CTU. The invention further provides an apparatus for producing molybdenum-99. 1. A method for producing molybdenum-99 comprising:i) providing an electron accelerator;ii) providing a molybdenum converter/target unit (Mo-CTU) comprising one or more metallic components, wherein each one of said metallic components is made of a material selected from the group consisting of natural molybdenum, molybdenum-100, molybdenum-98, and mixtures thereof;iii) directing an electron beam generated via said electron accelerator onto said Mo-CTU to produce a braking radiation (bremsstrahlung);iv) employing said bremsstrahlung onto said Mo-CTU to produce molybdenum-99 and neutrons via a photo-neutron reaction;v) slowing down the neutrons produced in step iv) with a low atomic liquid, e.g. distilled water; and optionallyvi) employing the neutrons produced in step iv) to produce a complementary amount of molybdenum-99 via a neutron capture reaction on said Mo-CTU.2. The method of claim 1 , wherein production and accumulation of the isotope Mo-99 is carried out in the Mo-CTU itself which is ...

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Номер записи: 98
11-04-2019 дата публикации

Method and Apparatus for Planting and Harvesting Radioisotopes on a Mass Production Basis

Номер: US20190108921A1
Автор: Carvajal Jorge V., Czerniak Luke D., Heagy Melissa M., Heibel Michael D., McArdle Matthew D., Taylor Jeffrey J., Yankel James L.
Принадлежит: WESTINGHOUSE ELECTRIC COMPANY LLC

A method and apparatus for modifying an existing nuclear reactor moveable in-core detector system to insert and withdraw target specimens from a reactor core during reactor operation without practically impeding the moveable in-core detector system's ability to obtain flux maps of the core throughout the reactor's operation. The apparatus provides a separate drive unit and delivery cable that is independent of the detector drive system, but uses most of the same core delivery conduits to access the core. A specimen holder is remotely detachable from the delivery cable when appropriately positioned and can be remotely reattached for withdrawal after a scheduled period of radiation. 1. An irradiation target handling system having an isotope production cable assembly comprising:a target holder drive cable constructed to be compatible with conduits of an existing nuclear reactor moveable in-core detector system that convey in-core detectors from a detector drive unit to and through instrument thimbles within a reactor core, the target holder drive cable having a remotely controlled one of a male or female coupling on a leading end of the drive cable;a target holder drive cable drive motor unit separate from and independent of the detector drive unit on the existing nuclear reactor moveable in-core detector system and configured to drive the target holder drive cable into and out of the core, wherein the target holder drive cable drive motor unit is structured to drive the target holder drive cable into and through the conduits, a first multipath selector and a second multipath selector on the existing nuclear reactor moveable in-core detector system;a specimen target holder having another of the male or female coupling on a trailing end of the specimen target holder with the another of the male or female coupling configured to mate with the one of the male or female coupling on the leading end of the target holder drive cable; anda third multipath selector structured to ...

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Номер записи: 99
13-05-2021 дата публикации

AUTOMATIC PROCESS PLATFORM FOR THE PRODUCTION OF ASTATINE-211 [ AT 211] RADIOPHARMACEUTICALS

Номер: US20210139389A1
Автор: Aneheim Emma, Lindegren Sture
Принадлежит:

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. 1. A process for automatic synthesis from isolation of At-211 nuclide from irradiated Bi-209 target material to the full synthesis product of At-211-labeled molecules comprising{'b': 100', '101, 'dry-distilling At-211 in a furnace system (, ) and'}{'b': '109', 'introducing At-211 into a reaction vial () comprising of a precursor molecule adapted to bind At-211, characterized in that the process comprises the steps of'}{'b': '106', 'A) condensing the dry-distilled At-211 by cooling in a cooling unit () to obtain At-211 as a dry residue,'}B) eluting the At-211 with a transfer liquid that solvate the dry residue of At-211,C) introducing At-211 for further chemical processing into said reaction vial,D) activating At-211 for further chemical processing,E) reacting activated At-211 with a precursor molecule,2125. The process of claim 1 , wherein the At-211 is obtained by scraping an irradiated bismuth target to At-211 powder () target material.3120. The process of claim 2 , wherein in the scraping of the irradiated bismuth target is performed using a scraping unit ().4. The process of claim 1 , wherein in step B) the transfer liquid is an organic solvent.5. The process of claim 1 , wherein in step C) the organic solvent is evaporated leaving a dry residue of At-211.6. The process of claim 1 , wherein in step B) the transfer liquid is an adaptive solvent oxidizing At-211.7. The process of claim 1 , wherein in step B) the transfer liquid is an adaptive solvent reducing At-211.8. The process of claim 1 ...

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Номер записи: 100