48results about "Isotope delivery systems" patented technology

A method and system (300) for separating thorium from uranium and its decay products is provided. The method includes combining a nuclear fuel feedstock (102) containing thorium and uranium with a first acid (104, 204) to form a first solution. The first solution is contacted with an ion exchange resin (308) that is selective for thorium or uranium. The thorium or uranium is at least partially removed from the first solution by binding the thorium or uranium to the ion exchange resin (308), thereby forming a second solution (106, 206). The second solution (106, 206) is combined with oxalic acid to precipitate the uranium or thorium from the second solution, forming a precipitate (110, 210). The precipitate (110, 210) is separated from the second solution (106, 206).

The invention relates to wet preparation of a radiation therapy source and a method for accumulating radium radionuclides. The method comprises providing a first solution comprising a thorium radionuclide and a thorium binding extractant, wherein the first solution does not bind to radium; allowing a portion of the thorium radionuclides in the first solution to decay to radium atoms; and collecting radium atoms resulting from the decay. The collected radium atoms may be contained in a solution into which a brachytherapy source is immersed in a manner that collects radium atoms onto the brachytherapy source.

The invention relates to an arrangement for integrated production of a plurality of unit dosages of an anhydrous radiopharmaceutical composition, to anhydrous and aqueous radiopharmaceutical compositions and to methods for the preparation thereof.

A method of generating a radionuclide includes receiving a container in a container receptacle of a radionuclide generator, and moving the container in the container receptacle from a first pose to a second pose. The method also includes exposing an interior surface of the container to a precursor radionuclide source while the container is in the second pose, and allowing sufficient time for the precursor radionuclide source to decay into one or more progeny radionuclides and to emanate the one or more progeny radionuclides into the container. The method further includes isolating the precursor radionuclide source from the container while the container is in the first pose.

A radioisotope generator is disclosed, the radioisotope generator comprising: a housing; a radioactive source region located in the housing and configured to receive a radioactive source emitting a radioisotope; and a container movement mechanism located in the housing. The container movement mechanism is configured to cause movement of a first container between: (i) a source exposure position, wherein the first container is positioned in the housing adjacent to the radioactive source, and wherein an internal surface of the first container is configured to be exposed to the radioactive source to receive the radioisotope; and (ii) a collection position, wherein the first container is positioned in the housing for elution of the received radioisotope.

An enclosure for producing radioisotopes from material to be irradiated within a thimble guide tube of a nuclear reactor core is provided. The enclosure is constructed of enriched material and defines a cavity therein. The cavity of the enclosure is configured to contain the material to be irradiated. A target assembly for producing synthetic radioisotopes and a method for producing pharmaceutical radioisotopes using the target assembly are also provided.

The invention relates to the technical field of radioactive source preparation, in particular to a preparation process of a 137Cs source for a blood irradiator. The process comprises the following steps: step 1, preparing raw materials: using 137Cs product liquid extracted from high-level liquid waste, wherein the radioactive activity of the 137Cs product liquid meets the basic requirements of a cesium source for a blood irradiator; step 2, cesium source pellet pressing: loading a 137Cs raw material into a mold, pressing a pellet in a hydraulic machine, and then drying and sintering at high temperature to obtain the cesium source pellet; and step 3, welding and sealing: the cesium source core block is arranged in a stainless steel source box, and the source box and the sleeve are sealed through an argon arc welding technology. The invention provides a process for purifying and transforming 137Cs product liquid extracted based on high-level liquid waste. A prepared radioactive source has the characteristics of high uniformity, high radioactive activity, small size, high difficulty, high sealing performance and the like; meanwhile, the 137Cs product liquid is successfully converted into the radioactive source meeting the standard of the blood irradiator, and autonomous preparation of the 137Cs source for the domestic blood irradiator is achieved.

A method of generating radionuclides includes receiving a container in a container receptacle of a radionuclide generator, and moving the container in the container receptacle from a first attitude to a second attitude. The method further includes exposing an inner surface of the container to the precursor radionuclide source when the container is in the second attitude; and giving sufficient time to decay the precursor radionuclide source into the one or more seed radionuclides and to diffuse the one or more seed radionuclides into the container. The method further includes isolating the precursor radionuclide source from the container when the container is in the first attitude.

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.

A system and method are provided for obtaining radium radionuclides by separating radium from thorium and other nuclides. The system and method in one embodiment can comprise a multi-column configuration in which the first column is a strong cation exchange column onto which radium is adsorbed, the next columns comprise TEVA and TRU resins that adsorb and removes nuclides from radium, and subsequent columns can include Pb resin, mono- or di-phosphonic acid based resins, and / or prefilter resin, that further remove nuclides from radium.

To extract, at hospitals or other use points, a radiopharmaceutical made from low-specific-activity radioactive molybdenum-99 and of radioactive technetium-99m as a raw material for a labeling compound for the radiopharmaceutical. Pack activated charcoal or alumina into a cylindrical metal mesh rather than a column, with which the flow rate is limited, in advance, adjust the molybdenum solution to a low-pH, acidic state, and then immerse the cylindrical metal mesh into the molybdenum solution while the molybdenum solution is flowing as a result of being stirred, to prepare a molybdenum-99-adsorbing column in which the molybdenum-99 has been adsorbed onto the activated charcoal or alumina, then elute the technetium-99m produced from the molybdenum-99 from the molybdenum-99-adsorbing column, and pass the eluate through a technetium-99m-purifying column packed with aluminum oxide to trap the technetium-99m, and then pass neutral-pH physiological saline through the technetium-99m-purifying column to separate and elute the technetium-99m, thereby purifying and recovering the technetium-99m while removing impurities.

A pierceable plug for closing off a piercing end of a needle is described herein. The plug has an end that is configured to be pierced by the needle to close off the piercing end of the needle. The plug may be radiation sterilizable and may be made of a material that includes an antimicrobial agent. The plug may be used to close off a needle end that is in fluid communication with a radioactive substance.

The present invention provides a method and apparatus for producing Pb-212. [Solution] The apparatus comprises a release box equipped with an release source containing a porous, non-reactive material. The release box receives at least one of Th-228 and Ra-224, and at least one of Th-228 and Ra-224 decays into Rn-220 within the release box. The apparatus further includes a carrier gas supply unit coupled to the release box. The carrier gas supply unit introduces an inert gas into the release box, and the inert gas transports Rn-220 out of the release box through the carrier gas outlet port of the release box. The apparatus also includes one or more Rn-220 targets coupled to the carrier gas outlet port. The carrier gas transports Rn-220 from the release box to one or more Rn-220 targets, where Rn-220 decays into Pb-212 within one or more Rn-220 targets. The Pb-212 is introduced into a Pb-212 collection container.

This invention provides a method for separating lead radioisotopes from a mixture comprising lead radioisotopes and radioisotopes of radium or thorium, and a system comprising multiple chromatographic columns. The system may include a first ferrule column having a lead complexing medium that preferentially binds lead radioisotopes compared to radium or thorium radioisotopes; and a second ferrule column having a weak cation exchange medium, wherein the pH of the loading solution for loading the second ferrule column is pH [pH value missing]. 2L The pH of the eluent used to elute lead radioisotopes from the second cassette column is pH. 2E And pH 2L greater than pH 2E The system may also include a third and a fourth cassette column with chromatographic media for the extraction and purification of lead radioisotopes, thereby providing a purified solution of lead radioisotopes that can be used for medical and other purposes, such as for labeling radiopharmaceutical compounds.

The elution generator has an elution column having a vessel and a septum defining an interior volume, and a radiation shield. The radiation shield includes an upper shield portion and a lower shield portion, the upper shield portion defining a central recess and a coaxial flow needle extending downwardly into the central recess, and the lower shield portion having a body portion defining the central recess. The elution column is disposed within the central recess of the lower shield portion, the body portion of the lower shield portion is disposed within the central recess of the upper shield portion, and the coaxial flow needle extends downwardly through the septum into the interior volume of the elution column.

The application relates to a method for producing medical grade lead-212, including the steps of:a) producing lead-212 by radioactive decay of radium-224 in at least one first chromatography column containing a first stationary phase to which radium-224 is attached;b) eluting thus produced lead-212 from the first stationary phase;c) loading the eluate thus obtained into a second chromatography column containing a second stationary phase to attach the lead-212 to the second stationary phase;d) performing wash(es) of the second stationary phase; and thene) eluting lead-212 from the second stationary phase;and wherein:step b) includes circulating in said at least one first chromatography column an aqueous solution A1 including from 0.8 mol / L to 1.6 mol / L chloride, optionally with at most 200 mmol / L HCl; andstep d) includes circulating in the second chromatography column an aqueous solution A2 including from 0.01 mol / L to 1 mol / L chloride.

The present invention relates to assemblies and methods of obtaining a container comprising containing 212Pb on a wall wherein 212Pb is obtained from a 212Pb precursor isotope source. The present invention provides an improved system and method for producing high purity 212Pb that does not require processing, is high in yield, and can safely and efficiently transport the high purity 212Pb to its location of use.

To generate diffusing alpha-emitter radiation therapy (DART) sources loaded with radium-223 or radium-224 atoms.SOLUTION: A method of accumulating radium radionuclides comprises: providing a first solution including thorium radionuclides and a thorium-binding extractant, where the first solution does not bind to radium; allowing a portion of the thorium radionuclides in the first solution to decay into radium atoms; and collecting radium atoms resulting from the decay. The collected radium atoms may be included in a solution in which a brachytherapy source is dipped, in a manner of collecting the radium atoms on the brachytherapy source.SELECTED DRAWING: Figure 5

An elution generator including an elution column having a container defining an interior volume and a septum, a radiation shield having an upper shield portion defining a central recess and a coaxial flow needle extending downwardly into the central recess, and a lower shield portion having body portion defining a central recess, wherein the elution column is disposed in the central recess of the lower shield portion, the body portion of the lower shield portion is disposed in the central recess of the upper shield portion, and the coaxial flow needle extends downwardly through the septum into the internal volume of the elution column.

Embodiments of the present invention provide for assessing the state of an 82Rb elution system. In certain embodiments, a system begins an assessment that comprises an elution, and a metric may be measured. This metric may be a concentration of 82Rb, 82Sr, or 85Sr in a fluid that is eluted from the generator, the volume of the fluid that is eluted from the generator, or the pressure of the fluid flowing through at least one portion of the system. If the assessment is completed, an output may be generated on a user interface that recommends a course of action, or no course of action, based on a result of the assessment. Should the assessment not complete successfully because it is interrupted, a 82Sr / 82Rb generator of the system may be halted so as to prevent a user from performing an end-run around these quality control mechanisms of the 82Rb elution system.

The present invention provides a radioisotope generator system with enhanced safety features and implements such system. In particular, the present invention provides a radioisotope generator system comprising a surface that comprises three ports: an evacuation port, a loading port, and a saline flush port. The saline flush port is permanently connected with the loading port so that the rinsing solution can be placed on the saline port and pass it through the Mo-99 vial to minimize the wastage of the Mo-99. The present invention provides a robust design of the three-port radioisotope generator, which is cost-effective and ensures improved safety from needle contamination.

This invention provides a method for preparing a proximity irradiation therapy source. [Solution] A method for accumulating radium radionuclides, comprising the steps of: providing a first solution containing a thorium radionuclide and a thorium-binding extractant, wherein the first solution is not bound to radium; decaying a portion of the thorium radionuclide in the first solution into radium atoms; and collecting the radium atoms resulting from the decay. The collected radium atoms may be included in a solution into which a proximal irradiation source is immersed, in a manner that collects the radium atoms into the proximal irradiation source.

A method for generating radionuclides comprises receiving a container in a container receiving section of a radionuclide generator, and moving the container in the container receiving section from a first position to a second position. This method also comprises exposing the inner surface of the container to a precursor radionuclide source while the container is in the second position, and allowing sufficient time for the precursor radionuclide source to decay into one or more progressive radionuclides and release one or more progressive radionuclides into the container. This method further comprises isolating the precursor radionuclide source from the container while the container is in the first position.

In the medical and pharmaceutical fields, radioisotopes may be valuable in imaging and therapeutic aspects. Various irradiation systems are known for use within a nuclear reactor facility to produce radioisotopes. However, current systems face numerous challenges, such as impeded field of view in a viewport, and inability to accurately locate a target in the system. In some embodiments, an isotope irradiation system for use in a nuclear reactor facility is provided. The isotope irradiation system may include a removable support structure, an interface system, a cartridge loading and retrieval system, and an isotope target transport system. The disclosed isotope irradiation system can address challenges associated with conventional systems.

1. A layered radioisotope source for producing a medically useful dose of a daughter radioisotope through a chain of spontaneous decays from a parent radioisotope via a gaseous intermediate radioisotope, the layered radioisotope source comprising: an inert ceramic substrate layer; a metal oxide surface layer bonded onto the inert ceramic substrate layer; and a parent radioisotope immobilized on or within the metal oxide surface layer so as to enable effective release of the gaseous intermediate radioisotope away from the layered radioisotope source.

The invention relates to a process for producing medical-grade lead-212, comprising the steps of: a) production of lead-212 by radioactive decay of radium-224 in at least one first chromatography column containing a first stationary phase on which radium-224 is fixed; b) elution of the lead-212 thus produced from the first stationary phase; c) loading of the eluate thus obtained into a second chromatography column containing a second stationary phase to fix the lead-212 on the second stationary phase; d) washing of the second stationary phase; d) elution of the lead-212 from the second stationary phase; and characterized in that: - step b) comprises circulating in said at least one first chromatography column an ​​aqueous solution A1 comprising from 0.8 mol / L to 1.6 mol / L of a chloride, optionally with at most 200 mmol / L of HCl;and- step d) includes circulating an aqueous solution A2 comprising 0.01 mol / L to 1 mol / L of chloride through the second chromatography column. Applications: manufacture of lead-212 based radiopharmaceuticals, useful in nuclear medicine.

In one aspect, the technology relates to a method of producing Ac, the method including preparing a phosphate-modified titania material to produce an ion-exchange material, contacting a solution including 229Th with the ion-exchange material to produce a Th-loaded titania material, eluting the Th-loaded titania material with a wash solution to produce an eluted solution containing eluted compounds including 225Ac, concentrating the eluted solution to generate eluted compounds including the 225Ac, and separating the 225Ac from the eluted compounds.

A method for enhancing the activity of radionuclides in a daughter radionuclide-containing eluate obtained from a mixture of mother / daughter radionuclides is disclosed. The method comprises the steps of: i) contacting separated particles with an aqueous solution containing a mixture of mother and daughter radionuclides, wherein the daughter radionuclides are bound to the separated particles and the mother radionuclides are not bound; ii) maintaining the contact for a period of time for unbound daughter radionuclides to bind to the separated particles; iii) separating the unbound mother radionuclides from the separated particles with bound daughter radionuclides using a wash solution; iv) repeating steps i) and ii) at least once; and v) stripping the bound daughter radionuclides from the separated particles using a stripping solution in each of the at least two separations described, using a quantity of stripping solution less than the quantity of stripping solution used if only steps i), ii), iii), and v) were used, thereby forming an aqueous eluate with enhanced daughter radionuclide activity.