132results about "Isotope delivery systems" patented technology

The present invention relates to assemblies and method for obtaining a container comprising 212Pb on the walls obtained from a 212Pb precursor isotope source. The invention provides an improved system and method for producing 212Pb in high purity without the need for processing, with high yields, and which safely and efficiently can be transported to the locations where it is to be used.

The present invention relates to assemblies and method for obtaining a container comprising 212Pb on the walls obtained from a 212Pb precursor isotope source. The invention provides an improved system and method for producing 212Pb in high purity without the need for processing, with high yields, and which safely and efficiently can be transported to the locations where it is to be used.

Systems and methods for generating radionuclides, such as radium-224, are disclosed herein. Systems herein may include a first cartridge having a first opening, a second opening, and a chamber therebetween having a first resin having affinity for thorium-228 and bismuth-212; a second cartridge having a first opening, a second opening, and a chamber therebetween having a second resin having affinity for thorium-228, a third cartridge having a first opening, a second opening, and a chamber therebetween comprising a third resin having affinity for thorium-228 and bismuth-212, and a fourth cartridge having a first opening, a second opening, and a chamber therebetween having a fourth resin having affinity for lead-212; wherein a continuous flow path is formed from a top of the first cartridge though the second cartridge, through the third cartridge, and to a bottom of the fourth cartridge during system use.

A radioisotope target station, including a target housing. The target housing includes a target material, and a target backing material. The radioisotope target station includes a loader mechanism comprising at least one jaw configured to secure the target housing, a loading position comprising a magazine, wherein the magazine is configured to hold two or more target housings, an irradiation position comprising a beam, where the beam is configured to irradiate the target housing orthogonally, a cooling fluid source fluidly coupled to the loader mechanism, where the cooling fluid source is configured to cool the target housing as the target housing is irradiated, and an ejection position comprising an ejector and an ejection chute, where the ejector is configured to detach the target housing from the loader mechanism and the ejection chute is configured to receive the target housing when detached.

A molybdenum / technetium 99-m generator contains a powder comprising a metal-molybdate salt and an alumina adsorbent. The preferred aluminum oxide adsorbent is gamma-phase aluminum oxide (gamma-Al2O3), chi-phase aluminum oxide (x-Al2O3), or a combination of the gamma-phase aluminum oxide and the chi-phase aluminum oxide.

To extract technetium-99m from low-specific-activity molybdenum-99 in a short time without being influenced by the volume of molybdenum solution.The method for recovering technetium-99m from low-specific-activity molybdenum-99 is a method in which the daughter nuclide technetium-99m produced through the decay of molybdenum-99 with a low specific activity contained in a high-concentration molybdenum solution containing the molybdenum-99 with a low specific activity is separated by using activated charcoal and recovered, and the method is characterized in that the activated charcoal is immersed into the molybdenum solution and selectively adsorbs a trace amount of technetium-99m in the solution, even when molybdenum-99 is present 1016 times or more abundantly in terms of the ratio of the number of atoms.

An adsorbent for a germanium [68Ge]-gallium [68Ga] generator, a preparation method therefor, and a germanium [68Ge]-gallium [68Ga] generator. The adsorbent is used for adsorbing 68Ge elements; the adsorbent comprises: a plurality of titanium dioxide particles, the specific surface area of the plurality of titanium dioxide particles being 30 m2 / g to 100m 2 / g; the titanium dioxide particles each consist of a plurality of nanoparticles, the average particle size of the plurality of nanoparticles being 10 nm to 100 nm; the nanoparticles each comprise mesopores, the diameter of the mesopores being 5 nm to 30 nm.

The present invention relates to assemblies and method for obtaining a container comprising 212Pb on the walls obtained from a 212Pb precursor isotope source. The invention provides an improved system and method for producing 212Pb in high purity without the need for processing, with high yields, and which safely and efficiently can be transported to the locations where it is to be used.

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 relates to an RI manufacturing apparatus including an accelerator, a target irradiated with a particle beam of an accelerated particle emitted from the accelerator, and an incident angle adjustment mechanism that adjusts an incident angle of the particle beam to the target. The apparatus further comprises a target attachment and detachment device attached to the accelerator.

Some aspects are generally related to gripper systems for manipulating holders and / or containers disposed therein for use with radionuclide generators. In some embodiments, the gripper system further facilitates the insertion and / or removal of a stopper from the container, which may maintain a sterility of an interior of the container before and / or after exposure of the container to radionuclides from the radionuclide generator.

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).

A remotely controllable sublimation apparatus (300) including a crucible block (316) adapted to hold a crucible (307) containing a solid mixture including one or more radionuclides, a first heating block (350) with one or more first heating elements (358) configured to selectively generate heat having a first temperature sufficient to at least partially sublimate the solid mixture, and a collection vessel (312) coupled to the first heating block. The crucible block is movable between an open position and a closed position relative to the first heating block. When the crucible block is in the closed position, the one or more first heating elements are configured to heat the crucible block to a first temperature, thereby heating the solid mixture and generating a vapor that is collected by the collection vessel, leaving a solid residue in the crucible consisting essentially of only one or more radionuclides.

The present invention extracts, at a use point such as a hospital: a radiopharmaceutical using radioactive molybdenum-99 having low specific activity as a raw material; and radioactive technetium-99m, which serves as a labeling compound raw material for the radiopharmaceutical.　Activated carbon or alumina is charged into a metal net-like cylindrical container which is not a column in which flow rate is limited. The metal net-like cylindrical container is immersed in a molybdenum solution brought to a low-pH acidic state and kept flowing by stirring, thereby preparing a molybdenum-99-adsorbed column in which the molybdenum-99 is adsorbed on the activated carbon or the alumina. The technetium-99m generated from the molybdenum-99 is eluted out from the molybdenum-99-adsorbed column and is then passed through a technetium-99m purification column filled with aluminum oxide, thereby capturing the technetium-99m. Physiological saline having a neutral pH is passed through the technetium-99m purification column, thereby separating and eluting out the technetium-99m, which is purified and recovered after impurities are removed therefrom.

A method for separating a lead radioisotope from a mixture comprising the lead radioisotope and a radioisotope of radium or thorium is provided, along with a system comprising a plurality of chromatographic columns. The system can include a first cartridge having a lead-complexing media that preferentially binds the lead radioisotope over radioisotopes of radium or thorium, and a second cartridge having a weak cationic exchange media, where a pH of a loading solution used to load the second cartridge is pH2L, and a pH of an eluent used to elute the lead radioisotope from the second cartridge is pH2E, and pH2L is greater than pH2E. The system can also comprise further third and fourth cartridges with chromatographic media to extract and purify the lead radioisotope, to provide a purified solution of lead radioisotope that can be used for medical and other purposes, such as in the labeling of radiopharmaceutical compounds.

An apparatus for producing Pb-212. The apparatus comprises an emanation box that comprises an emanation source comprising a porous non-reactive material. The emanation box receives at least one of Th-228 and Ra-224, wherein the at least one of Th-228 and Ra-224 decays to Rn-220 within the emanation box. The apparatus further includes a carrier gas feed coupled to the emanation box. The carrier gas feed directs an inert gas into the emanation box and the inert gas carries the Rn-220 out of the emanation box through a carrier gas exit port of the emanation box. The apparatus also includes one or more Rn-220 targets coupled to the carrier gas exit port. The carrier gas carries the Rn-220 from the emanation box to the one or more Rn-220 targets and the Rn-220 decays into Pb-212 within the one or more Rn-220 targets. The Pb-212 is directed into the Pb-212 collection container.

Various embodiments include a method of producing purified lutetium-177. The method may include irradiating a target material containing lutetium-176 in a nuclear reactor, separating lutetium-177 from the irradiated target material using electromagnetic isotope separation, dissolving the separated lutetium-177 in an acidic solution, purifying the dissolved lutetium-177 using a series of chromatographic columns and ion resins, and eluting the purified lutetium-177 in a final chemical form suitable for medical use. The chromatographic columns may include a first column containing a lanthanide resin and a second column containing a diglycolamide resin. The final chemical form may be lutetium-177 chloride.

The present invention relates to a method for producing actinium-225 from proton spallation of a thorium target via a radium generator. The method includes the steps of dissolving a thorium target in a thorium solution, evaporating the thorium solution to obtain a dried thorium salt, redissolving the dried thorium salt in sulfuric acid to form neutral thorium species, passing the neutral thorium species through a cation exchange chromatography column to remove bulk thorium, performing extraction chromatography on a mixed resin bed to elute the radium, evaporating the radium-containing eluate, reconstituting the dried radium, and performing extraction chromatography to elute a purified radium fraction, thereby constructing a radium generator.

The present invention relates to assemblies and method for obtaining a container comprising 212Pb on the walls obtained from a 212Pb precursor isotope source. The invention provides an improved system and method for producing 212Pb in high purity without the need for processing, with high yields, and which safely and efficiently can be transported to the locations where it is to be used.

The present invention relates to assemblies and method for obtaining a container comprising 212Pb on the walls obtained from a 212Pb precursor isotope source. The invention provides an improved system and method for producing 212Pb in high purity without the need for processing, with high yields, and which safely and efficiently can be transported to the locations where it is to be used.

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.

The invention relates to a transport container for a radioisotope elution system, said transport container comprising a hollow housing (20), which is disposed in a way to surround a radiation shield (2) that is made from radio-opaque material, especially from lead, and that encloses a radioactive isotope-carrying elution column (1); a seat (27), which is provided in an upper portion (22) of the housing (20) and which carries an elution slot (23) and a solution slot (25) that are adjacent to each other; a protective upper lid (10), which is arranged to cover the seat (27) in an entirely impermeable manner; and a base (30), which is mounted via a lower side (24) of the housing (20) and which has a cup-form bottom (36) where the radiation shield (2) is to fit.

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.

The invention relates to nuclear medical devices, in particular, to the manufacture of radionuclide generators. A strontium-82 / rubidium-82 generator includes a generator column with a sorbent based on hydrated tin (IV) oxide, to which the radioactive isotope 82Sr (half-life of 25.55 days) with the impurity 85Sr (half-life of 60 days) is applied. 82Sr decays to short-lived 82Rb (half-life of 76 seconds). The generator is intended for producing a radiopharmaceutical containing 82Rb chloride, which is washed off the sorbent and administered to a patient for diagnosing various diseases using positron emission tomography, while the strontium-82 and 85 isotopes should remain on the sorbent and should not pass into the eluate together with 82Rb. In this generator, the maximum volume of the obtained 82Rb-containing eluate with a content of 82Sr and 85Sr below the permissible level (0.01 and 0.1 kBq per 1 MBq of 82Rb, respectively) depends on the concentration of ions of stable isotopes of calcium (CCa) and strontium (CSr) on the sorbent arising during the preparation and use of the generator, and is limited by the value of 0.11 CCa + CSr. For example, the production of more than 17 liters of eluate with an acceptable content of 82Sr and 85Sr is achieved when this ratio is below 0.67 µmol per 1 g of dry sorbent. The production of more than 30 liters of eluate is achieved when this value is lower than 0.33 µmol per 1 g of dry sorbent (when the weight of specially prepared dry sorbent in the column is not less than 3.8 g). The limits of the amount of calcium and strontium arising on the sorbent during manufacture of the generator are proportional to the weight of the sorbent in the column. Thus, at a relatively low concentration of calcium and strontium ions and with a sorbent weight in the column of more than 3.8 g, a larger volume (31-60 liters) of a radiopharmaceutical in the form of a solution of 82Rb chloride with the necessary characteristics can be obtained using the generator. A larger volume of radiopharmaceutical allows increasing the number of patients examined with each generator. Also, observing the given limit for the strontium and calcium ion content in the sorbent allows preventing more reliably radioactive strontium isotopes from entering the patient.

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.