Abstract: A method for the manufacture of Actinium-225 from a Radium-226 containing material. Radium-226 containing starting target material is shielded with a thermal neutron absorption shield and is subjected to neutron irradiation from a moderated nuclear reactor. Radium-226 is thereby converted into Radium-225 to provide a Radium-225-containing material. The Radium-225 in the Radium-225 containing material is allowed to decay into Actinium-225, and the Actinium-225 is isolated from the Radium-225 containing material. The neutron absorption shield shields the starting target material from neutrons having an energy in the range of 20 eV to 1000 eV.

Abstract: Among the various aspects of the present disclosure is the provision of systems for producing radioisotopes and improving the specific activity of radioisotopes (e.g., Cu-64 chloride). As described herein, the system includes a target material area or target material shape that matches the proton beam strike area or proton beam strike shape, resulting in optimal thickness with less target material required.

Abstract: There is provided an exit window for an electron beam from a linear accelerator for use in producing radioisotopes. The exit window comprises a cylindrical channel operatively connectable at one end to a vacuum chamber configured for travel of the electron beam; and a domed dished head at the other end of the channel, the dished head comprising a convex portion having a protruding crown configured for pass-through of the electron beam wherein the geometry of the domed dished head is proportioned to resist pressure stress created by cooling medium circulating around the protruding crown and the vacuum in the cylindrical channel and to maintain the combined cooling medium pressure stress and pulsed electron beam thermal stress below the fatigue limit of the material forming the exit window.

Abstract: A method of preparing a structure, more particularly, a method of preparing a structure capable of ensuring a space for carrying an electrode active material by a simple method which includes an electrospinning process using a double nozzle electrospinning device and a heat treatment process.

Abstract: A neutron capture therapy system includes an accelerator for generating a charged particle beam, a neutron generator for generating a neutron beam having neutrons after irradiation by the charged particle beam, and a beam shaping assembly for shaping the neutron beam. The beam shaping assembly includes a moderator and a reflecting assembly surrounding the moderator. The neutron generator generates the neutrons after irradiation by the charged particle beam. The moderator moderates the neutrons generated by the neutron generator to a preset energy spectrum. The reflecting assembly includes a plurality of reflectors configured to guide deflected neutrons back to the neutron beam and a supporting member to support the plurality of reflectors. A lead-antimony alloy is for the reflecting assembly to mitigate a creep effect that occurs when only a lead material is for the plurality of reflectors, thereby improving the structural strength of a beam shaping assembly.

Abstract: A method of producing actinium by using liquefied radium includes producing Ac-225 using Ra-226 of a liquefied state, moving the produced Ac-225 in a liquefied state after Ac-225 is produced, and separating Ac-225 and reusing Ra-226. As a result, a nuclear reaction process of Ac-225 may be performed and loss of Ra-226 may be minimized. Further, such a method may improve safety by including a radon collection unit which is capable of discharging and isolating radon produced from Ra-226, thereby preventing radiation exposure due to radon.

Abstract: A neutron activator for neutron activation of a material, the neutron activator being configured to produce neutrons from an interaction with a proton beam (7), the neutron activator comprising: a neutron source comprising a metallic target (1), and a Beryllium first reflector-moderator (4) peripheral to the neutron source and comprising a neutron activation area (10) configured to accommodate the neutron source and the material to be activated, the neutron activation area (10) of the first reflector-moderator (4) comprising a bore configured to accommodate the neutron source.

Abstract: A method of generating power using a Thorium-containing molten salt fuel is disclosed. One example includes the steps of providing a vessel containing a molten salt fuel, generating a proton beam externally to the vessel, where the externally generated proton beam being of an energy level sufficient to interact with the salt in the vessel to produce a (p, n) reaction resulting in the generation of a neutron at the first energy level. Neutrons generated within the vessel through the (p, n) reactions caused by the externally generated proton's interaction with the at least one salt are utilized to produce a fission reaction where the fission reaction increases the heat content of the molten salt within the vessel. In the example, a heat exchanger is used to extract heat from the molten salt within the vessel and power is generated from the extracted heat.

Abstract: A method including providing a nuclear reactor neutron source that includes an enclosure delimiting a chamber, a nuclear reactor core arranged inside the chamber and configured to produce neutrons from a nuclear fuel element inside the nuclear reactor core; installing a beam generator arranged to generate a beam directed into the chamber; and installing, inside the chamber, a target arranged to eject neutrons upon impact of the beam such that neutrons are ejected from the target and emitted from the chamber.

Abstract: Provided herein are systems, devices, articles of manufacture, and methods for generating neutrons employing a high energy ion beam target (HEIB target) and a target backing configured to be in contact with the bottom surface of the HEIB target (e.g., to generate an ion beam target assembly). In certain embodiments, the HEIB target has a thickness that is less than the penetration depth of protons or deuterons in the high energy ion beam that strikes the target. In certain embodiments, the target backing comprises a high hydrogen diffusion metal (e.g., palladium), has open spaces dispersed throughout for reduced proton diffusion distances, and has a shape and thickness such that all, or virtually all, of the protons or deuterons that pass through the HEIB target are stopped. Also provided herein are systems, devices, and methods for changing targets in an ion beam accelerator system.

Abstract: Apparatus for radioisotope production includes housing, a plurality of target disks inside the housing and a curved windows positioned convex inward toward the disks. During operation, coolant flows though the housing across the disks and windows while electron beams passes through the window and the disks. The window temperature increases, rising the fastest in the middle of the window where the electron beam hits the window. A flat window would buckle because the center would deform during thermal expansion against the relatively unaffected periphery, but the curved window shape allows the window to endure high thermal and mechanical stress created by a combination of heating from the electron beam(s) and elevated pressure from coolant on the inside of the window. Such a window may be used for applications in which a pressurized coolant acts on only one side of the window.

Abstract: An apparatus and method are described which enable real time measurements to measure the margin to criticality in a process for manufacturing fissile materials. An exemplary apparatus includes a neutron source capable of being modulated, an optional moderator to reduce the thermal energy of neutrons from the neutron source, a collimator for controlling the direction of any neutrons emanating in use from the target, a plurality of detector arrays positioned in predetermined locations relative to a process vessel for detecting process variables and for sending signals representative of the process variables in real time to a processor for receiving the signals and converting the detected process variables into margin to criticality measurements.

Abstract: Target assembly includes a target body having a production chamber and a beam passage. The target body includes first and second grid sections that are disposed in the beam passage. Each of the first and second grid sections has front and back sides. The back side of the first grid section and the front side of the second grid section abut each other with an interface therebetween. The back side of the second grid section faces the production chamber. The target assembly also includes a foil positioned between the first and second grid sections. Each of the first and second grid sections has interior walls that define grid channels through the first and second grid sections. The particle beam is configured to pass through the grid channels toward the production chamber. The interior walls of the first and second grid sections engage opposite sides of the foil.

Abstract: The present invention provides a novel neutron source. A neutron source (1) of the present invention includes a neutron producing material layer (3) and a metal layer (2), and the metal layer (2) contains a metal element which has a high hydrogen diffusivity and generates radionuclides having a short half-life upon receipt of irradiation of neutron beams.

Abstract: A radiocontrast agent for tau protein is provided. The agent is selectively and strongly bound to tau protein and its tangle found in brain diseases like Alzheimer's disease (AD). The agent is especially suitable to be used in PET imaging for brain diseases. Or, the agent can be used to inhibit tau protein overexpressive and, thus, stop the proceeding of brain disease.

Abstract: The present invention provides a novel neutron source. A neutron source (1) of the present invention includes a neutron producing material layer (3) and a metal layer (2), and the metal layer (2) contains a metal element which has a high hydrogen diffusivity and generates radionuclides having a short half-life upon receipt of irradiation of neutron beams.

Abstract: Systems and methods for operating an accelerator driven sub-critical core. In one embodiment, a fission power generator includes a sub-critical core and a plurality of proton beam generators. Each of the proton beam generators is configured to concurrently provide a proton beam into a different area of the sub-critical core. Each proton beam scatters neutrons within the sub-critical core. The plurality of proton beam generators provides aggregate power to the sub-critical core, via the proton beams, to scatter neutrons sufficient to initiate fission in the sub-critical core.

Abstract: The invention relates to a method for producing a radioisotope, which method comprises irradiating a volume of radioisotope-precursor fluid contained in a sealed cell of a target using a beam of particles of a given current, which beam is produced by a particle accelerator. The target is cooled and the internal pressure in the sealed cell is measured. During the irradiation, the internal pressure (P) in the sealed cell is allowed to vary freely. The irradiation is interrupted or its intensity is reduced when the internal pressure (P) in the sealed cell departs from a first tolerated range defined depending on various parameters that influence the variation in the internal pressure in the sealed cell during the irradiation. These parameters for example comprise, for a given target, particle beam and radioisotope-precursor fluid: the degree of filling of the hermetic cell, the cooling power used to cool the given target, and the beam current (I).

Abstract: Methods of synthesizing 100Mo2C and 99mTcO4? are disclosed. Methods of 100Mo2C generation involve thermally carburizing 100MoO3. Methods of 99mTcO4 generation involve proton bombardment of 100Mo2C in a cyclotron. Yields of 99mTcO4 can be increased by sintering 100Mo2C prior to bombardment. The methods also include recycling of 100Mo2C to form 100MoO3. SPECT images obtained using 99mTcO4 generated by the disclosed methods are also presented.

Abstract: Systems and methods for operating an accelerator driven sub-critical core. In one embodiment, a fission power generator includes a sub-critical core and a plurality of proton beam generators. Each of the proton beam generators is configured to concurrently provide a proton beam into a different area of the sub-critical core. Each proton beam scatters neutrons within the sub-critical core. The plurality of proton beam generators provides aggregate power to the sub-critical core, via the proton beams, to scatter neutrons sufficient to initiate fission in the sub-critical core.

Abstract: A method is provided for producing first and second radioactive isotopes using an accelerated particle beam that is directed to a first material and the first radioactive isotope is produced by a first nuclear reaction based on the interaction of the particle beam with the first material, said particle beam is also slowed down and subsequently directed to a second material, and the second radioactive isotope is produced by a second nuclear reaction based on the interaction of the particle beam with the second material. The effective cross-section for the induction of the first nuclear reaction at a first peak for a first particle energy is higher than an effective cross-section for the induction of the second nuclear reaction at a second peak for a second particle energy. A corresponding device includes an acceleration unit, a first exposure target having the first material and a second exposure target having the second material.

Abstract: The present invention is related to an irradiation cell for producing a radioisotope of interest through the irradiation of a target material by a particle beam, comprising a metallic insert forming a cavity designed to house the target material and to be closed by an irradiation window, wherein said metallic insert comprises at least two separate metallic parts of different materials, being composed of at least a first part comprising said cavity.

Abstract: A system for simultaneously imaging the corona and inner heliosphere of the Sun from a space borne platform. The system includes, a wide-field annular coronagraph (WAC) having annular, aspheric reflecting optics centered on an axis coinciding with the azimuthal orientation of the imaging system towards the Sun. The WAC incorporates an occulting cone having an axis of symmetry coinciding with that of the reflecting optic system and a baffle system for reducing stray light at angles far from the Sun. The system includes a solar coronal imager (SCI) positioned within the occulting cone of the WAC. The SCI includes axially aligned refracting optics centered on an axis coinciding with the azimuthal orientation of the imaging system and includes at least one occulting disk. The WAC and SCI each utilize digital electronic imaging and associated image processing instrumentation. The occulting cone of the WAC also functions as a radiative cooler.

Abstract: Provided is a modified target assembly in which the target fluid is moved within the target assembly in a manner that increases the effective density of the target fluid within the beam path, thereby increasing beam yield utilizing forced convection. The target may also include optional structures, such as nozzles, diverters and deflectors for guiding and/or accelerating the flow of the target fluid. The target assembly directs the target fluid along an inner sleeve in a direction opposite the direction of the beam current to produce a counter current flow and may also direct the flow of the target fluid away from the inner surface of the inner sleeve and toward a central region in the target cavity. This countercurrent flow suppresses natural convection that tends to reduce the density of the target fluid in the beam path and tends to increase the heat transfer from the target.

Abstract: A radioisotope production gas target for producing gas isotopes such as C-11. The radioisotope production gas target includes a target chamber that is in the shape of a hollow cylinder and has a plurality of inner fins protruding from an inner surface thereof along a length thereof, and a body that is shaped of a hollow cylinder enclosing the target chamber, and has a target gas inlet for feeding target gas to a hollow region of the target chamber, a target gas outlet for collecting the target gas after a nuclear reaction occurs, and a first coolant inlet and a first coolant outlet respectively feeding and discharging a coolant flowing along an outer surface of the target chamber, and includes a thin metal sheet in front thereof through which a beam of protons passes.

Abstract: The present invention relates to targets, systems and methods for the cyclotron production of 124I from aluminum telluride (Al2Te3) targets. The systems and methods utilize low energy proton cyclotrons to produce 124I by the 124Te(p,n) reaction from enriched Al2Te3 glassy melts. The 124I is recovered in high yield from the glassy melt by adapted methods of common thermal distillation techniques.

Abstract: An F-18 production target system having an internal support produces F-18 by means of a nuclear reaction of protons and H218O, and reduces the deformation of thin sheets to thus increase the durability of the thin sheets. The F-18 production target system includes a frame, which has the shape of a cylinder the central portion of which is bored, holds H218O in the central portion, and includes through-holes bored from the central portion to the outer circumference thereof, thin sheets, which are installed on opposite sides of the frame so as to seal the central portion, and a support, which is installed in the central portion so as to prevent the thin sheets from being deformed.

Abstract: The invention provides for a method for producing isotopes using a beam of particles from an accelerator, whereby the beam is maintained at between about 70 to 2000 MeV; and contacting a thorium-containing target with the particles. The medically important isotope 225Ac is produced via the nuclear reaction (p,2p6n), whereby an energetic proton causes the ejection of 2 protons and 6 neutrons from a 232Th target nucleus. Another medically important isotope 213Bi is then available as a decay product. The production of highly purified 211At is also provided.

Abstract: A portable neutron generator includes a Radio Frequency Quadrupole linear accelerator designed to accelerate charged particles of hydrogen (protons) to energies useful for producing neutrons with the (p,n) reaction on lithium. The ion source is driven by a coaxial feed and a spiral antenna to couple the microwave power into the plasma. The linear accelerator is driven by a 600 MHz pulsed RF power supply. A differential pumping scheme is used to balance the need for a high gas load on the ion source end and good vacuum on the accelerator end.

Abstract: A neutron source includes a low atomic number element target that is bombarded by incident energetic particles to provide a neutron flux. The source receives a controlled flow of liquid gallium that cools the target. The energetic particles may be for example protons or deuterons and the target is housed in a moderator/reflector assembly. Advantageously, the liquid gallium provides improved heat transfer, smaller flow rates and reduced stress on the target in comparison to prior art liquid coolants.

Abstract: The present invention provides a system and method for a system for accommodating a solid target in an accelerator. The system and method includes a target changer having at least one port for accommodating the solid target, an insert for receiving the solid target in the target changer, a piston for providing a vacuum and a cooling system for the solid target, a cylinder for displacing the piston in one of three positions; and a bracket for securing the insert, piston and cylinder to the target changer.

Abstract: The present invention provides a system and method for a system for accommodating a solid target in an accelerator. The system and method includes a target changer having at least one port for accommodating the solid target, an insert for receiving the solid target in the target changer, a piston for providing a vacuum and a cooling system for the solid target, a cylinder for displacing the piston in one of three positions; and a bracket for securing the insert, piston and cylinder to the target changer.

Abstract: Target, computer software and method for direct production of 99mTc using small energy accelerators. The method includes positioning a target holder to be bombarded with a beam of protons, the target holder having a target that includes a first hard core layer, a second hard core layer, a third layer of highly enriched 100Mo and a substrate, distributed in this order; bombarding the target with the beam of protons, wherein the protons have an energy between 10 and 35 MeV and a current between 20 and 500 ?A; and terminating the bombarding with the beam of protons after a time interval between half an hour and 8 hours.

Abstract: The present invention relates to targets, systems and methods for the cyclotron production of 124I from aluminum telluride (Al2Te3) targets. The systems and methods utilize low energy proton cyclotrons to produce 124I by the 124Te(p,n) reaction from enriched Al2Te3 glassy melts. The 124I is recovered in high yield from the glassy melt by adapted methods of common thermal distillation techniques.

Abstract: A method of producing multiple batches of a radiopharmaceutical, such as FDG. The method includes the steps of transferring the appropriate liquids to a production apparatus, processing the liquids to produce the radiopharmaceutical, delivering the radiopharmaceutical to a container, automatically cleaning the apparatus, and repeating the previous steps, as desired. The apparatus for multi-batch production of FDG includes a reagent delivery system, a reaction vessel, a filter assembly, and a control system. The combination of these components provides a method that is capable of producing multiple batches of a radiopharmaceutical with minimal operator intervention and, consequently, minimal radiation exposure.

Abstract: A target system for producing intense epithermal and sub-MeV neutron fluxes from proton beams by the Li-7(p,n)Be-9 nuclear reaction by use of a layer of solid metallic lithium as the target material, which, in concert with a novel conical substrate to provide support and cooling, is designed to accept proton-beam power densities in excess of 1 MW m?2. The lithium is of limited thickness so that protons exit the lithium layer after reaching the threshold of the (p,n) reaction and deposit their remaining kinetic energy in the cooled substrate. In addition, the target system is configured in a novel geometry intended to confer symmetry around the beam axis of the resulting neutron fields—a feature particularly relevant to utilization of the claimed invention in boron-neutron capture therapy (BNCT).

Abstract: A method of purifying the used O-18 enriched cyclotron target water contaminated by the various organic compounds, the method including: supplying gaseous oxygen into the target water to be purified; irradiating UV rays having wavelengths of 254 nm and 185 nm on the target water; and releasing the gases generated during the purification oxidation process.

Abstract: Neutron bundles are formed as a result of interactions between polarized atomic core neutrons and anti-polar neutrons injected into atomic cores. Neutron bundles are groups of neutrons that can be produced and used in a process for making elements and isotopes, and also used in a process for the production of nuclear binding energy as the ultimate clean fuel for energy with an unlimited supply. Elements and isotopes are formed upon the introduction of protons onto neutron bundles. Nuclear fusion energy is produced when neutron bundles are made to react with each other in equipment designed for this purpose that includes a neutron bundle nuclear chain reactor.

Abstract: A radioisotope production gas target for producing gas isotopes such as C-11. The radioisotope production gas target includes a target chamber that is in the shape of a hollow cylinder and has a plurality of inner fins protruding from an inner surface thereof along a length thereof, and a body that is shaped of a hollow cylinder enclosing the target chamber, and has a target gas inlet for feeding target gas to a hollow region of the target chamber, a target gas outlet for collecting the target gas after a nuclear reaction occurs, and a first coolant inlet and a first coolant outlet respectively feeding and discharging a coolant flowing along an outer surface of the target chamber, and includes a thin metal sheet in front thereof through which a beam of protons passes.

Abstract: An F-18 production target system having an internal support produces F-18 by means of a nuclear reaction of protons and H218O, and reduces the deformation of thin sheets to thus increase the durability of the thin sheets. The F-18 production target system includes a frame, which has the shape of a cylinder the central portion of which is bored, holds H218O in the central portion, and includes through-holes bored from the central portion to the outer circumference thereof, thin sheets, which are installed on opposite sides of the frame so as to seal the central portion, and a support, which is installed in the central portion so as to prevent the thin sheets from being deformed.

Abstract: An apparatus for producing a radionuclide includes a target chamber, a particle beam source operatively aligned with the target chamber, and a regenerative turbine pump for circulating a target fluid through the target chamber via first and second liquid transports. During bombardment of the target liquid in the target chamber by the particle beam source, the target liquid is prevented from reaching vaporization due to the elevated pressure within the target chamber and/or the rapid flow rate through the target chamber. A cooling system can be provided to circulate coolant to the first and second liquid transport conduits, the target chamber and the pump to ensure that the target liquid is cooled upon recirculation back into the target chamber.

Abstract: A high power high yield target for the positron emission tomography applications is introduced. For production of Curie level of Fluorine-18 isotope from a beam of proton it uses about one tenth of Oxygen-18 water compared to a conventional water target. The target is also configured to be used for production of all other radioisotopes that are used for positron emission tomography. When the target functions as a water target the material sample being oxygen-18 or oxygen-16 water is heated to steam prior to irradiation using heating elements that are housed in the target body. The material sample is kept in steam phase during the irradiation and cooled to liquid phase after irradiation. To keep the material sample in steam phase a microprocessor monitoring the target temperature manipulates the flow of coolant in the cooling section that is attached to the target and the status of the heaters and air blowers mounted adjacent to the target.

Abstract: A system is provided for generating high-energy particles and for inducing nuclear reactions. The system includes a laser and for emitting a laser beam, an irradiation target for receiving the laser beam and producing high-energy particles, and a secondary target for receiving the high-energy particles, thereby inducing a nuclear reaction. A method is also provided including producing a laser beam of high-intensity with an ultra-short pulse duration, irradiating the laser beam onto an irradiation target in order to ionize the irradiation target and produce a collimated beam of high-energy particles, and colliding the collimated beam of high-energy particles onto a secondary target containing a nuclei, thereby inducing a nuclear reaction on the secondary target.

Abstract: A spallation device for production of neutrons includes a spallation target that produces neutrons by interaction with a hollow particle beam propagating within a first chamber, a second chamber containing the spallation target, and a leak tight partition separating the first and second chambers. The spallation device is particularly applicable to basic physics, medicine, and transmutation.

Abstract: A system and method for producing 18F-Fluoride by using a proton beam to irradiate 18Oxygen in gaseous form. The irradiated 18Oxygen is contained in a chamber that includes at least one component to which the produced 18F-Fluoride adheres. A solvent dissolves the produced 18F-Fluoride off of the at least one component while it is in the chamber. The solvent is then processed to obtain the 18F-Fluoride.

Abstract: A method for transmuting spent fuel from a nuclear reactor includes the step of separating the waste into components including a driver fuel component and a transmutation fuel component. The driver fuel, which includes fissile materials such as Plutonium239, is used to initiate a critical, fission reaction in a reactor. The transmutation fuel, which includes non-fissile transuranic isotopes, is transmuted by thermal neutrons generated during fission of the driver fuel. The system is designed to promote fission of the driver fuel and reduce neutron capture by the driver fuel. Reacted driver fuel is separated into transuranics and fission products using a dry cleanup process and the resulting transuranics are mixed with transmutation fuel and re-introduced into the reactor. Transmutation fuel from the reactor is introduced into a second reactor for further transmutation by neutrons generated using a proton beam and spallation target.

Abstract: The subject apparatus provides a means to identify the presence of fissionable material or other nuclear material contained within an item to be tested. The system employs a portable accelerator to accelerate and direct protons to a fluorine-compound target. The interaction of the protons with the fluorine-compound target produces gamma rays which are directed at the item to be tested. If the item to be tested contains either a fissionable material or other nuclear material the interaction of the gamma rays with the material contained within the test item with result in the production of neutrons. A system of neutron detectors is positioned to intercept any neutrons generated by the test item. The results from the neutron detectors are analyzed to determine the presence of a fissionable material or other nuclear material.

Abstract: An apparatus for producing a radionuclide includes a target chamber, a particle beam source operatively aligned with the target chamber, and a regenerative turbine pump for circulating a target fluid through the target chamber via first and second liquid transports. During bombardment of the target liquid in the target chamber by the particle beam source, the target liquid is prevented from reaching vaporization due to the elevated pressure within the target chamber and/or the rapid flow rate through the target chamber. A cooling system can be provided to circulate coolant to the first and second liquid transport conduits, the target chamber and the pump to ensure that the target liquid is cooled upon recirculation back into the target chamber.

Abstract: A method of producing an isotope comprising directing electrons at a converting material coated with a coating material, the coating material having an atomic number of n, whereby interaction of the electrons with the converting material produces photons, and whereby the photons produced interact with the coating material to produce an isotope having an atomic number of n−1. In preferred embodiments, the converting material is Tungsten, the coating material having an atomic number of n is Radium-226, and the isotope having an atomic number of n−1 is Radium-225.

Abstract: The invention relates to a method for producing neutrons with the aid of a spallation effect. The method includes the diversion of a partial cooling stream out of the main cooling stream and an acceleration of the partial cooling stream in such a manner that vapor bubbles are formed in the vacuum region produced by the acceleration, and after introduction into the main cooling stream, said vapor bubbles act upon generated pressure waves in an attenuating manner during the impingement of a proton beam.