446results about "Radioactive sources" patented technology

An infusion system may include a radioisotope generator that generates a radioactive eluate via elution, a beta detector, a gamma detector, and a controller. The beta detector and the gamma detector may be positioned to measure beta emissions and gamma emissions, respectively, emitted from the radioactive eluate. In some examples, the controller is configured to calibrate the infusion system using the gamma detector. For example, the controller may generate a radioactive eluate and measure the activity of the radioactive eluate using both the beta detector and the gamma detector. The high accuracy of the activity measured by the gamma detector may be used to calibrate the infusion system. In subsequent use, the infusion system calibrated using the gamma detector may adjust measurements made to monitor and / or control patient infusion procedures.

The invention provides a solid target system for simultaneously producing Ge-68 and PET nuclides under a high-power beam, and the system comprises an intermediate-energy cyclotron which is used for transmitting an intermediate-energy high-intensity proton beam; the cascade target is arranged beside the intermediate-energy cyclotron and comprises a shell, and a first aluminum target body, a second aluminum target body, a Ga4Ni alloy capsule target and a metal sealing target which are sequentially arranged along the emission direction of the intermediate-energy high-current proton beam, and the shell is filled with cooling water; the target film is erected between the intermediate energy cyclotron and the first aluminum target body; the helium cooling unit is erected between the target film and the first aluminum target body; and the control unit is used for controlling to start the helium cooling unit and the medium-energy cyclotron, so that the medium-energy high-intensity proton beam sequentially passes through the target film, the first aluminum target body, the shell and the cooling water, then enters the Ga4Ni alloy capsule target to produce Ge-68 nuclide, and then enters the metal sealing target to produce PET nuclide. The method has the beneficial effects that the melting of the target material can be reduced, the probability of direct chemical reaction of molten Ga and Nb is reduced, and the types of nuclide production are increased.

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

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.

To provide a method and an apparatus capable of efficiently producing volatile radioactive isotopes including an astatine isotope.SOLUTION: Provided is a method of producing radioactive isotopes, including: an evaporation step of heating a target to evaporate a radioactive isotope by heating; a mixing step of mixing the evaporated radioactive isotope and an aerosol with each other; a collection step of collecting, through a collection filter, the radioactive isotope and the aerosol mixed in the mixing step; a cleaning step of cleaning the collection filter by ultrasonic cleaning; and a recovery step of recovering a cleaning liquid used in the cleaning step.SELECTED DRAWING: Figure 1

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 present invention provides a radionuclide production system, a radionuclide production method, and an accelerator system with which a beam profile of radiation irradiated on a target can be monitored in real time using a destructive monitor, and with which appropriate irradiation on the target can be carried out according to the beam profile. The radionuclide production system comprises: an accelerator that accelerates charged particles; and a target that produces a radionuclide by nuclear reaction upon being irradiated with an accelerated charged particle beam or radiation generated by a charged particle beam. The radionuclide production system further comprises, behind targets (T205, T207) in the direction of advancement of the charged particle beam, destructive monitors (T206, T209) which are detectors for detecting radiation and which interact with the radiation. On the basis of a spatial distribution of intensity of the charged particle beam or radiation measured by the destructive monitors, the radionuclide production method produces a radionuclide while determining, as a beam profile at positions of the targets, at least one of a spatial distribution of intensity, a position of a beam center, and a beam spread.

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.