342results 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.

Means and method for photo-enhanced electro-catalytic process using nuclear thermal NTAC-integrated PEEC (PEEC-NTAC) catalytic processes combining ECM with energetic photon sources, such gamma rays, and sono-catalytic driver.

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.

An automatic doctor blade (1) for scraping a radioactive target (101) to be used for a radiopharmaceutical, the automatic doctor blade comprising: a target holder (2) for holding a radioactive target; a scraping unit (3) comprising a scraping member for scraping the radioactive target located in the target holder; a receiver (5) for receiving 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. A surface (102) of the radioactive target to be scraped is arranged at an angle between 45 degrees and 315 degrees, the angle of 0 degrees corresponding to the radioactive target being oriented such that the surface of the radioactive target to be scraped is perpendicular to the vertical direction and facing upward, the angle of the target corresponding to a clockwise rotation of the target from 0 degrees.

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.

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 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.

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.

The present disclosure provides a nuclear power source, a nuclear battery assembly, and a method of manufacture thereof. The nuclear power source comprising a radiation source layer, a first electrical insulator layer disposed over the radiation source layer, a first casing layer disposed over the first electrical insulator layer, a first electrode in contact with the radiation source layer, and a second electrode in contact with the first casing layer. The radiation source layer comprises a composition configurable to emit beta radiation. A voltage potential is present between the first electrode and the second electrode when the radiation source layer emits beta radiation. The first electrical insulator layer has a thickness that reduces an average energy of the beta-radiation from the radiation source layer that contacts the first casing layer such that Bremsstrahlung radiation emitted when the beta-radiation reaches the first casing layer is reduced.

The present disclosure relates to a microsphere having a plurality of pores that have a gradient characteristic gradually decreasing along the direction from the surface to the center of the microsphere, wherein the microsphere includes: a first nuclide, which is distributed in the microsphere and whose concentration in the center of the microsphere is greater than that in the surface of the microsphere; and a second nuclide and gradually decreasing along the direction from the surface to the center of the microsphere, wherein the first and second nuclides are capable of being radioactive after neutron activation to produce β-rays, γ-rays or a combination thereof. The present disclosure also provides methods of preparing a microsphere. The functions of radiotherapy, imaging and tracking can be achieved by introducing the first and second nuclides into the microsphere, and the plurality of pores can increase the surface area of the microsphere to enhance adhesion with a shell.

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 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

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.

The invention provides a radioactive source for a thickness measuring device, and the radioactive source comprises a box body part which is provided with a containing cavity and an exit window, and the containing cavity is used for containing beta radioactive gas; the collimation part is arranged on the box body part, a plurality of emergent channels which are arranged at intervals are formed, the emergent channels are conducted in the first direction, and the emergent window covers one end of each emergent channel; the electric field generating part is arranged in the box body part and is used for forming an electric field in the accommodating cavity; the direction of the electric field is parallel to the first direction, and the electric field points to the interior of the containing cavity from the emergent window. According to the radioactive source, beta rays emitted to the emergent window in the accommodating cavity or beta rays emitted through the emergent window can be screened by utilizing the collimating part, so that part of beta rays with high consistency with the first direction can be emitted out of the box body part through the emergent channel and the emergent window so as to participate in thickness measurement of an object to be measured; therefore, the collimation of the emitted beta ray is improved, and the measurement precision of the thickness measurement device is improved.

The utility model discloses an electro-deposition tank for a large-area beta radioactive source. The electro-deposition tank comprises a deposition tank fixing frame, a pressure bracket and a tank body, electro-deposition liquid is contained in the tank body, a first through hole allowing the anode wire to penetrate through and go deep into the electro-deposition liquid is formed in the top of the tank body, a lower opening is formed in the bottom of the tank body, and a gasket is arranged at the lower opening; the deposition tank fixing frame comprises a cathode base and a door-shaped frame erected on the cathode base, a groove matched with the tank body is formed in the cathode base, an electro-deposition source sheet is placed in the groove, the lower end of the tank body is placed in the groove, and electro-deposition liquid in the tank body is in contact with the electro-deposition source sheet; a pressure rod is screwed on the door-shaped frame, the lower end of the pressure rod acts on a pressure bracket, and the pressure bracket is arranged on the tank body; through the pressure applied by the pressure rod, the gasket is in close contact with the electro-deposition source sheet. According to the utility model, a screw fastening mode of the conventional tank body is changed into a pressure fastening mode, so that the disassembly and assembly efficiency is improved, the stress of the whole electro-deposition tank is uniform, and electro-deposition liquid cannot leak.

To provide simple method of manufacturing a material activation member capable of reducing friction resistance.SOLUTION: A method of manufacturing a material activation member for reducing friction resistance is provided, the method comprising: a material activation material forming step of forming a fluidic material activation material by mixing and agitating powder of a natural mineral containing a radioactive substance, powder of an electron-generating material that generates electrons when subjected to alpha rays emitted from the natural mineral, and a fluid binder; and a material activation member filling step of filling a cylindrical magnet having an N-pole at one end and an S-pole on the other end with the material activation material. The powder of the electron-generating material comprises titanium dioxide powder, magnesium metal powder, silicon metal powder, black silica powder, lanthanum hexaboride powder, and copper powder.SELECTED DRAWING: None

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.

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.

225 Actinium is converted into liquid by proton, deuterium or gamma irradiation in the irradiation device (2). 226 The radium target is irradiated and the resulting liquid target solution in the first extractor (6) is extracted. 225 By extracting actinium, 226 It is produced from radium. 225 The liquid target solution from which actinium has been removed is irradiated again to generate more 225 The liquid target solution is preferably circulated through the irradiation device in a closed loop (4) and through the first extraction device (6) in a further closed loop (7). The advantage of such a method is that the irradiated target solution does not have to be dried and redissolved so that the produced actinium can be separated from the radium, and no further drying and redissolution steps are required to regenerate the liquid target starting from the separated radium. The radium target is therefore in particular 226 Taking into account the radon gas that is continuously produced by the decay of radium, it can be recycled in a more efficient and safe way.

The present disclosure is directed compositions and formulations comprising high levels of copper-64, and process for preparing said compositions and formulations. The present disclosure also relates to methods of administering copper-64 compositions to a patient in need thereof.

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.