176results about "Radioactive sources" patented technology

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.

The invention discloses a method for efficiently generating high-brightness gamma radiation, and belongs to the technical field of radiation. A relativistic electron beam is injected into the porous microstructure foam target material, and high-brightness gamma ray radiation is generated. According to the method, the used device is simple, only the single relativistic electron beam and the porous microstructure foam target material are needed to interact, compared with a traditional uniform-density solid material, the energy conversion efficiency in the interaction process of the electron beam and a substance can be remarkably improved, and the energy conversion efficiency can be remarkably improved through the effective constraint effect of a high-intensity magnetic field. And the problems of low energy conversion rate, low light source brightness, poor radiation directivity, complex device or difficulty in experiment implementation and the like of the existing high-energy gamma ray radiation source are solved.

The present disclosure generally relates to materials, processes, generators, and / or systems, for generating radioisotope. The present disclosure also generally relates to ceramic materials comprising radioisotope suitable for use in a radioisotope generator. The present disclosure also generally relates to processes, generators and / or systems, for producing and capturing radioisotope. The present disclosure also generally relates to the preparation of radioisotope solutions for use in radiopharmacy and / or other clinical applications.

Aspects of the present disclosure relate generally to systems and methods for use in the implementation and / or operation of quantum information processing (QIP) systems, and more particularly, to a technique for the fabrication of laser-ablation targets used in atomic sources for QIP systems that are based on atomic-based qubits.

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.

A sterilization system for a radiopharmaceutical product comprising a hot cell disposed within a clean room environment. A sterilization shaft extends between a first end and a second end and defines an interior. The first end of the shaft is disposed within the hot cell and the second end of the shaft is disposed externally to the clean room. An electron beam accelerator assembly is disposed within the interior of the sterilization shaft so that an emission end of the electron beam accelerator is adjacent the first end of the sterilization shaft.

A method for producing a titanium molybdate material.SOLUTION: The method includes reacting a metallic molybdenum-99 (Mo-99) material in a liquid medium with a first acid to obtain a Mo composition, combining the Mo composition with a titanium source to obtain a Ti-Mo composition, and pH adjusting the Ti-Mo composition with a base to precipitate a plurality of Ti-Mo particulates.SELECTED DRAWING: Figure 1

To provide an electron-generating material and electron-generating member, which can reduce a friction coefficient.SOLUTION: An electron-generating material capable of reducing a friction coefficient is provided, the material comprising powder of a natural mineral containing a radioactive substance and powder of an electron-generating material that generates electrons when subjected to alpha rays emitted from the natural mineral, where the powder of the electron-generating material comprises titanium dioxide powder, lanthanum hexaboride, and silicon metal.SELECTED DRAWING: None

The present invention relates to a radioactive microsphere with a core-shell structure having a diameter in the range of from 10-200 μm, wherein the radioactive microsphere comprises a core, a metal shell coated on the surface of the core, and non-metallic radionuclides bound to the metal shell by the interaction therebetween to form the radioactive microsphere. The present invention provide a method for the production thereof and a use of the radioactive microsphere in radiotherapy or imaging thereof. Moreover, the present invention provides the separate administration of the non-metallic radionuclides and the microsphere. The present application also provides a new method of treating a cancer with the microsphere comprising inserting a catheter to a target tissue site in the patient in a DSA suite, following by transferring the patient from the DSA suite to nuclear medicine department with certification for radionuclides handling, and then treating the patient by administrating radionuclides and / or radioactive microspheres through the catheter in the nuclear medicine department.

Cobalt intermetallic compounds that include cobalt and a second element are provided. The isotopes of the second element in the compounds are present in their natural isotopic abundance or in an enriched isotopic abundance. Methods of making the compounds and methods of using the compounds as targets in the production of radionuclides are further provided.

This invention relates to the field of nuclear medicine PET technology, and more particularly to a method for preparing a radionuclide beam source. The method includes: mixing addition-type liquid silicone rubber with a radionuclide to obtain a liquid mixture; placing the liquid mixture in a syringe and removing air bubbles; connecting the tip of the syringe needle to a hollow casing; filling the casing with the liquid mixture and sealing it; then curing and sealing by welding; the radionuclide includes one or more of Ge-68, Cs-137, Co-60, P-32, Sr-90, Y-90, Na-22, Na-24, Sr-89, Lu-177, and Rh-106. This invention provides a method for preparing a radionuclide beam source for nuclear medicine PET. 68 The manufacturing method of the Ge wire source features room temperature curing with no byproducts, uniformity without bubbles, and long-term use at temperatures ranging from -50 to 200 degrees Celsius, meeting [the requirements]. 68 Safety performance level requirements for Ge line sources.

The present disclosure relates to an automated device and methods to produce a highly purified alpha-emitting radioisotope Pb-212 from a pre-filled column of a parent isotope Ra-224 for use in targeted alpha-particle therapy.

The application discloses a column tube system and a generator, the column tube system comprising a chromatographic column, elastic plugs and a support, the chromatographic column being provided with two openings at two axial ends thereof; the two elastic plugs are connected with the two ends of the chromatographic column respectively and used for sealing the openings of the chromatographic column; the support comprises a first support leg, two limiting plates being arranged on the first support leg and spaced apart along a first direction, the chromatographic column and the two elastic plugs being located between the two limiting plates, and the two elastic plugs abutting against the two limiting plates respectively. The column tube system disclosed by the application is provided with the support, the support being provided with the two limiting plates which are spaced apart, the chromatographic column is clamped between the two limiting plates when the chromatographic column is installed, the elastic plugs at the two ends of the chromatographic column abut against the two limiting plates respectively, the chromatographic column is extruded and limited by the two limiting plates, the installation stability of the chromatographic column in the production process is improved, and the liquid leakage probability is reduced.

A method for isolating astatine, comprising the steps of: (a) contacting a composition comprising astatine and bismuth with nitric acid to form a first solution comprising astatine, bismuth, and nitric acid, (b) contacting a resin with the first solution to separate the astatine from the first solution and partition it onto the resin, and (c) eluting the astatine from the resin. The astatine-containing composition is a compound of formula AtO + X ‐ (X ‐ is a counter ion).

In an embodiment of the present disclosure provided is a method of producing radionuclides that includes the installation, irradiation, transport, and trapping steps. In the installation step, a target material containing a target nuclide is placed inside a target chamber. In the irradiation step, at least a portion of the target material is irradiated with a quantum beam. In the transport stage, a carrier gas is supplied to the inside of the target chamber and an ambient gas around the target material is sent to the outside of the target chamber through an exhaust pipe. In the trapping step, a trap device connected to the exhaust pipe is configured to trap the radionuclides produced from the target nuclide from the ambient gas. In the present embodiment of the present disclosure, the target nuclide is bismuth 209 and the produced radionuclide is astatine 211. In an embodiment of the present disclosure, a target holding device 100 for quantum beam irradiation comprising a target material container 3 and a rotational drive mechanism 5 is also provided, as well as a quantum beam irradiation system 1000. An example target material container is rotatable.

To extract technetium 99m from low specific activity Mo 99 in a short time, without being influenced by an amount of a molybdenum solution.SOLUTION: A method for recovering technetium-99m from low specific radioactivity molybdenum-99 involves separating and collecting the daughter nuclide technetium-99m, which is produced by the decay of molybdenum-99 contained in a high-concentration molybdenum solution with low specific activity, using activated carbon. The activated carbon is characterized by being immersed in the molybdenum solution and selectively adsorbing trace amounts of technetium-99m present, even when the molybdenum-99 to atom ratio is 1016 or higher.SELECTED DRAWING: Figure 1

Aspects of the present disclosure relate generally to systems and methods for use in the implementation and / or operation of quantum information processing (QIP) systems, and more particularly, to a technique for the fabrication of laser-ablation targets used in atomic sources for QIP systems that are based on atomic-based qubits.

Disclosed herein are charge or electricity generating devices and methods of making and use thereof.

An automatic scraper (1) for scraping a radioactive target (101) used in radiopharmaceuticals, comprising: a target holder (2) for holding the radioactive target; a scraping unit (3) having a scraping member for scraping the radioactive target disposed in the target holder; a container (5) for receiving the material scraped from the radioactive target; a motor (6) for moving the scraping unit and the target holder relative to each other; and a control unit for controlling the motor. The surface (102) of the radioactive target to be scraped is oriented at an angle between 45 and 315 degrees, with an angle of 0 degrees corresponding to a radioactive target oriented such that the surface to be scraped is perpendicular to the vertical direction and faces upward, and the angle of the target corresponds to a clockwise rotation of the target from 0 degrees.

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.

An irradiation target is formed into a sphere. The spherical irradiation target can be iridium metal (10) containing natural or enriched iridium 191. The radiation source of the present invention can be manufactured by manufacturing a spherical irradiation target, accommodating the spherical irradiation target in a rotating capsule (20), and rotating an axial flow impeller (32) by a downward flow of a reactor primary coolant, whereby the rotating capsule (20) is rotated. This radiation source provides an improved nondestructive inspection image having a high geometric resolution, and has no radiation source anisotropy and also has high target recyclability.

A brachytherapy seed applicator, comprising a hollow needle; a non-metallic elongated tube configured for insertion into tissue, within the hollow needle; a hub at a proximal end of the non-metallic elongated tube; one or more brachytherapy seeds carrying radioactive particles, within the non-metallic elongated tube; and a stylet configured to be inserted into the non-metallic elongated tube and to push the one or more brachytherapy seeds to a distal end of the non-metallic elongated tube, when the non-metallic elongated tube is in the tissue.

A radiation therapy source (20, 30, 40) for treating a tumor includes a flexible core (22) impermeable to radon and a polymeric coating (28, 48) on the flexible core. The polymer coating is impermeable to radium and allows radon to diffuse through the polymer coating. The radiation therapy source further includes an alpha-emitting radium radionuclide (26) in the polymer coating or between the flexible core and the polymer coating.

According to various aspects of the present disclosure, the present disclosure relates to an automated process for the radiosynthesis of [18F]FSPG, a positron emission tracer. The automated optimization process of the present invention enables the centralized and large-scale production of [18F]FSPG for commercial use.

To provide an electron-generating member capable of reducing a friction coefficient.SOLUTION: An electron-generating member capable of reducing a friction coefficient is provided, the member comprising: an electron-generating portion made of an electron-generating material comprising powder of a natural mineral containing a radioactive substance and powder of an electron-generating substance that generates electrons when subjected to alpha rays emitted from the natural mineral; and a magnet laminated on the electron-generating portion.SELECTED DRAWING: Figure 1

Compositions comprising high levels of high specific activity copper-64, and process for preparing said compositions. The compositions comprise from about 2 Ci to about 15 Ci of copper-64 and have specific activities up to about 3800 mCi copper-64 per microgram of copper. The processes for preparing said compositions comprise bombarding a nickel-64 target with a low energy, high current proton beam, and purifying the copper-64 from other metals by a process comprising ion exchange chromatography or a process comprising a combination of extraction chromatography and ion exchange chromatography.