31results about "Radioactive sources" patented technology

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.

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.

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.

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 a radioactive nuclide production system and a radioactive nuclide production method which improve cooling performance of a target material including a material nuclide, suppress contamination of impurities to the target material, and are capable of efficiently producing a radioactive nuclide.SOLUTION: A radioactive nuclide production system 1 comprises: a particle beam irradiation device 10 which generates a particle beam 11; and a target 20 which generates radioactive nuclide by irradiation of the particle beam 11. In the target 20, a target material 21 including a material nuclide generating the radioactive nuclide is mounted on a target cooling plate 22 cooling the target material 21. In a radioactive nuclide production method, the target material 21 including the material nuclide forms the target 20 mounted on the target cooling plate 22 cooling the target material 21, and the target 20 is irradiated with the particle beam 11 or bremsstrahlung while cooling the target material 21 by the target cooling plate 22 to produce radioactive nuclide.SELECTED DRAWING: Figure 1

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.

A target for heavy ion or electron bombardment is intended, and a method for preparing it is also intended. In this method, a) a liquid target aqueous solution of a target metal salt dissolved in water is deposited at the bottom of a metal target capsule having an opening at the top, and b) the capsule is heated to form a crystalline material. Steps a) and b) are repeated until the crystalline material contains a target amount of the target salt. The target capsule is then heated until the mass of the target capsule remains constant. To mitigate the formation of salt creep during preparation, the liquid target aqueous solution may contain about 2 to about 20 percent v / v of C2-C4 polyol, or the inner surface of the target capsule may be coated with a hydrophobic film that gives a water contact angle of about 70 to about 130° prior to liquid deposition.

This provides a rapid and more effective method for recovering At. [Solution] A method for isolating astatine, comprising the steps of (a) contacting a composition containing astatine and bismuth with nitric acid to form a first solution containing astatine, bismuth, and nitric acid; (b) contacting a resin with the first solution to separate the astatine from the first solution and distribute it to the resin; and (c) eluting the astatine from the resin. The composition containing astatine may have the formula AtO+X- (where X- is a counterion).

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.

This invention relates to a method for preparing an ultrathin 4π fission source based on a graphene substrate, belonging to the field of fission source preparation. The method involves preparing a graphene-toughened carbon film, growing graphene of a predetermined thickness on the film, and transferring the resulting substrate material. Fissionable material is then transferred onto the graphene substrate using a combination of solution drying and vacuum self-transfer technology, resulting in an ultrathin fission source capable of emitting fission fragments in the 4π direction. By transferring fission nuclides to a nanometer-thick graphene substrate, the fission products released from the fission source are emitted in the 4π direction, and the average energy loss of the fission fragments penetrating the substrate is far less than their own kinetic energy. This yields a high-quality fission source with low energy loss and minimal self-absorption, achieving efficient and stable preparation of an ultrathin 4π fission source, providing a relatively "perfect" fission source for fission physics experiments or related detector calibration.

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.

A generator column assembly for the elution of a radioisotope, having a generator column container having a bottom wall defining a flow outlet aperture, an open top end, and a sidewall extending from the open top end to the bottom wall that defines an interior volume having a substantially cylindrical upper volume portion and a substantially cylindrical lower volume portion, the upper volume portion having a diameter that is greater than a diameter of the lower volume portion, and a closure cap assembly including a container cap defining a flow inlet aperture.

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.

Provided are a radionuclide production system and a radionuclide production method which make it possible to produce radionuclides with a compact, lightweight device with high safety and good efficiency. A radionuclide production system (S) according to the present invention comprises: an electron beam accelerator (1) that emits an electron beam (20); a bremsstrahlung radiation generation target (10) that generates bremsstrahlung radiation (30) with the emitted electron beam (20); and a radionuclide production target (40) that includes a raw material which produces a radionuclide upon irradiation with the generated bremsstrahlung radiation (30). The thickness of the bremsstrahlung radiation generation target (10) is set in the range in which the production rate of the radionuclide reaches a peak and with the condition that the amount of electron beam (20) irradiation on the radionuclide production target (40) is smallest within said range.

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.

The present invention provides a radioactive isotope production system and a radioactive isotope production method that can be miniaturized. [Solution] According to this radioactive isotope production system 100, the target 10 after irradiation with charged particle beam B is made smaller than it was during irradiation, and the radioactive isotope is recovered. Figure 6(b) shows what happens when the target 10 after irradiation with charged particle beam B is placed in the purification apparatus 103 at its original size. As shown in Figure 6(b), because the size of the target 10 is large, the internal space 31 needs to be enlarged, and as a result, the entire purification apparatus 103 must be enlarged. In contrast, by making the target 10 smaller after irradiation, a smaller purification apparatus 103 can be used, as shown in Figure 6(a). Thus, the system can be miniaturized.

The present application belongs to the technical field of isotope battery, and specifically provides a radioactive source for an isotope battery, a preparation method thereof and the isotope battery. The present application aims to solve the problems that the existing radioactive source is not easy to prepare a substrate-free radioactive source film during preparation, and the existing radioactive source film is easy to damage the radioactive source when connected with a semiconductor transducer element. To this end, the radioactive source comprises a substrate layer, a radioactive source layer and a connecting layer connected in sequence, the substrate layer is connected to one side of the radioactive source layer and can be separated from the radioactive source layer, and the connecting layer is provided with adhesion and can transmit the energy radiated by the radioactive source layer. The radioactive source of the present application is convenient to prepare and has adhesion itself, and can be directly adhered to the semiconductor transducer element when used, without damaging the radioactive source.

The present disclosure relates to a system and method for recovering radium-226. In one embodiment, uranium tailings are processed to obtain an aqueous solution containing radium-226. A macrocyclic material is used to sorb radium-226 from the aqueous solution. The macrocyclic material is then exposed to a recovery solution such as EDTA to recover the radium-226.

A method for purifying a target substance for reuse in the production of radioisotopes is disclosed. The method includes obtaining a solution of an irradiated target substance that includes Ra-226 and optionally Ra-225 and Ac-225, and then adding an acid, which is HNO3, in a predetermined amount to provide conditions for quantitatively dissolving the target substance and optionally avoiding coprecipitation of radioisotopes that are present. The method also includes selectively removing H2O from the solution by distillation, leaving mainly the acid in the solution, thereby enabling the target substance to precipitate while the acid concentration in the solution increases, thereby reducing or avoiding coprecipitation of optionally present radioisotopes and impurities. After removing the excess H2O, the method includes lowering the temperature of the solution to maximize precipitation of the target substance and reduce the solubility of the target substance in the residual liquid, separating the liquid containing the optionally present radioisotope from the precipitated target substance, and preparing the precipitated target substance for reuse in the production of radioisotopes by re-irradiation for the production of radioisotopes.

A device is provided having a support having an outer surface and configured for insertion into a subject's body. The present invention relates to a device (20) having a support (22) configured for insertion into a subject's body, the support (22) having an outer surface (24). The device further has a plurality of atoms (26) of a radionuclide bound to the outer surface that radioactively decay to produce daughter radionuclides, and a layer (28) of polymer that is permeable to the daughter radionuclides and covers the atoms.

The present invention relates to a nuclear target (1), a method for inducing a nuclear reaction and a device capable of inducing nuclear reactions. According to the present invention, the nuclear target (1) is equipped with a hollow (12) into which projectile particles (3) are deposited. In the hollow (12), the projectile particles (3) interact with precursors (21 and / or 22 and / or 23), or projectile particles (3) are elastically scattered on isotopes (4). The nuclear target (1), method, or the device thus provides a more efficient induction of nuclear reactions and provides a higher yield of radioisotope production. In another embodiment, the nuclear target (1) can be used as a means used to nuclear waste transmutation, or as a means of sustainable exothermic nuclear reactions.

To provide a method for generating medical-grade lead-212. 【Solution means】The present invention a) generating 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 the thus-generated lead-212 from the first stationary phase; c) loading the thus-obtained eluate onto a second chromatography column containing a second stationary phase to attach lead-212 to the second stationary phase; d) performing a washing of the second stationary phase, and e) eluting lead-212 from the second stationary phase In a method for generating medical-grade lead-212, comprising Step b) includes circulating an aqueous solution A1 containing 0.8 mol / L to 1.6 mol / L of chloride, optionally together with up to 200 mmol / L of HCl, through the at least one first chromatography column; Step d) includes circulating an aqueous solution A2 containing 0.01 mol / L to 1 mol / L of chloride through the second chromatography column A method characterized by the above. Use: Manufacture of radiopharmaceuticals based on lead-212 useful in nuclear medicine.

The present invention provides a target irradiation system that allows the target to be removed from the irradiation device and the radioactive isotope to be quickly dissolved in a dissolution device, and a method for recovering radioactive isotopes from a solid target. [Solution] The transport device 22 transports the solid target 10 from the target irradiation device 20, where the charged particle beam B is irradiated onto the solid target 10, to the dissolution device 21, which recovers the radioactive isotopes. Here, the target irradiation device 20 and the dissolution device 21 are located in a cyclotron chamber 152 provided in the building 150. Therefore, both the process of irradiating the solid target 10 with a charged particle beam and the process of recovering the radioactive isotopes by dissolution are performed in the cyclotron chamber 152. Thus, the solid target 10 can be removed from the target irradiation device 20 and the radioactive isotopes can be quickly dissolved in the dissolution device 21.

The utility model discloses a kind of high-precision transmission plug structure of radioactive source, it is related to mechanical design manufacturing technical field, the utility model includes mainboard, the top outer wall of mainboard is fixedly connected with slide rail, the outer wall of mainboard is provided with plug-in mechanism;The plug-in mechanism includes motor board, the outer wall of motor board is fixedly connected with the outer wall of mainboard, the outer wall of one end of motor board close to slide rail is fixedly connected with controller, the inner wall of mainboard is rotatably connected with threaded rod, the utility model is placed by being equipped with sliding frame, with the transmission pipe of interface end is placed in sliding frame surface contact position, then limit plate is placed in with transmission pipe surface contact position, using the movement of sliding frame makes transmission pipe interface end and radioactive source interface end butt joint, again through controller start motor, it can be completed to transmission pipe and radioactive source interface end separation processing, reaches the transmission pipe can be inserted and connected processing, simultaneously reaches the transmission pipe can be limit processing.

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.

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; then e) 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.

The present invention related to a method for manufacturing at least one carbon-14 [14C, herein after] labeled alkaline earth metal carbonate from at least one neutron-irradiated metallic nitride, wherein the method comprises at least the following successive steps: a) contacting at least one neutron-irradiated metallic nitride with at least one aqueous solution to produce a gaseous stream (G) and an aqueous suspension (S); b) contacting said gaseous stream (G) with an acidic solution to produce at least one 14C-labeled enriched gaseous stream; c) subjecting said at least one 14C-labeled enriched gaseous stream to an oxidation process to produce at least one oxidized gaseous stream; d) treating said at least one oxidized gaseous stream with an alkaline solution comprising at least one alkali metal hydroxide base to produce a 14C-labeled aqueous solution comprising at least one 14C-labeled alkali metal carbonate; and e) treating said 14C-labeled aqueous solution comprising at least one 14C-labeled alkali metal carbonate with at least one alkaline earth metal salt solution, thereby obtaining a precipitated 14C-labeled alkaline earth metal carbonate.