Abstract: 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.

Abstract: 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.

Abstract: Among the various aspects of the present disclosure is the provision of methods for producing radioisotopes and improving the specific activity of radioisotopes (e.g., Cu-64 chloride). As described herein, the method includes matching of the target material and the proton beam strike area, resulting in improved specific activity while reducing the amount of target material used.

Abstract: 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.

Abstract: A liquid target device includes a liquid accommodation portion in which a target liquid is accommodated, a beam passage through which a charged particle beam emitted from a particle accelerator passes to reach the liquid accommodation portion, a target foil that separates the beam passage and the liquid accommodation portion from each other, and a vacuum foil that separates a vacuum region provided upstream of the beam passage and the beam passage from each other. The beam passage is provided with a first gas chamber into which a cooling gas is supplied at a position on the vacuum foil side and a second gas chamber into which a cooling gas is supplied at a position closer to the target foil side than the first gas chamber and the first gas chamber and the second gas chamber are separated from each other by an intermediate foil.

Abstract: Devices, systems, and methods for efficiently preparing and containing a small volume of liquid target material for irradiation by a cyclotron are provided. In various embodiments, a device includes a housing having a chamber and the housing has a top surface that is substantially flat. The chamber has a substantially flat base and a wall having a first portion extending from the base with a first radius of curvature and a second portion extending from the first portion having a second radius of curvature that is less than the first radius. The chamber also includes an inlet aperture, an outlet aperture, and a lip having a second surface that is substantially flat and recessed from the first surface. In various embodiments, the device includes a heat sink including a plurality of parallel fins disposed around the chamber.

Abstract: 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.

Abstract: The disclosure provide an apparatus for producing a nuclide by using a liquid target which can perform the nuclear reaction process and can discharge the radioactive gas such as Radon within the vial. As described above, an apparatus for producing a nuclide by using a liquid target according to the present disclosure can minimize quantitative loss of a reactant by performing the nuclear reaction process using a target of a liquefied state and reusing a liquefied target on which the nuclear reaction process has not been performed, and can improve safety by enabling the radioactive gas generated to be disposed.

Abstract: Methods for rapid isolation of radionuclides (e.g., 68Ga) produced using a cyclotron and methods for recycling of the parent isotope (e.g., 68Zn) are disclosed. In one version of the method, a solution including a radionuclide (e.g., 68Ga) is created from a target including cations (e.g., 68Zn). The solution including the radionuclide is passed through a first column including a sorbent comprising a hydroxamate resin to adsorb the radionuclide on the sorbent, and the radionuclide is eluted off the sorbent. The cations (e.g., 68Zn) are recovered from a recovery solution that has passed through the first column by passing the recovery solution through a second column including a second sorbent comprising a cation exchange resin.

Abstract: The radionuclide 43Sc is produced at commercially significant yields and at specific activities and radionuclidic purities which are suitable for use in radiodiagnostic agents including imaging agents. In a method, a solid target having an isotopically enriched target layer prepared on an inert substrate is positioned in a specially configured target holder and irradiated with a charged-particle beam of protons or deuterons. The beam is generated using an accelerator such as a biomedical cyclotron at energies ranging from 3 to about 22 MeV. The method includes the use of three different nuclear reactions: a) irradiation of enriched 43Ca targets with protons to generate the radionuclide 43Scin the nuclear reaction 43Ca (p,n)43Sc, b) irradiation of enriched 42Ca targets with deuterons to generate the radionuclide 43Sc in the nuclear reaction 42Ca(d,n)43Sc, and c) irradiation of enriched 46Ti targets with protons to generate the radionuclide 43Sc in the nuclear reaction 46Ti (p,a)43Sc.

Abstract: Isotope enrichment by laser activation wherein a multi-isotopic element Q, like Uranium, Silicon, Carbon is incorporated into gaseous QFn, QF6, QF4, QOmFn, etc and diluted in gas G like He, N2, Ar, Xe, SF6 or other inert gas; and wherein that mixture is cooled by adiabatic expansion or other means encouraging formation of dimers QF6:G in a supersonic super-cooled free jet; and wherein that jet is exposed to laser photons at wavelengths that selectively excite predetermined molecules iQF6 to iQF6*, thereby inducing rapid VT conversions and dissociations of iQF6*:G?iQF6+G+kT, while leaving non-excited dimers jQF6:G intact; and wherein a skimmer separates the supersonic free-jet core stream containing heavier jQF6:G dimers from lighter core-escaped iQF6-enriched rim gases.

Abstract: Production assembly for an isotope production system. The production assembly includes a mounting platform including a receiving stage that faces an exterior of the mounting platform. The mounting platform includes a beam passage that opens to the receiving stage and a stage port that is positioned along the receiving stage. A particle beam is configured to project through the beam passage and through the receiving stage during operation of the isotope production system. The stage port is configured to provide or receive a fluid through the receiving stage during operation of the isotope production system. The production assembly also includes a target assembly having a production chamber configured to hold a target material for isotope production. The target assembly includes a mating side that is configured to removably engage the receiving stage during a mounting operation.

Abstract: Target windows for isotope production systems are provided. One target window includes a plurality of foil members in a stacked arrangement. The foil members have sides, and wherein the side of a least one of the foil members engages the side of at least one of the other foil members. Additionally, at least two of the foil members are formed from different materials.

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: 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: 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 the production of radiostrontium. The problem to be solved by the invention is the extraction of radiostrontium from a large pool of liquid metallic rubidium to improve the efficiency of radiostrontium production and simplify the technology. Sorption is carried out directly on the inner surface of the target shell at a temperature of 275 to 350° C., or by means of extraction of radiostrontium from circulating rubidium via sorption on the heated surface of a trap at a temperature of 220 to 350° C., or by means of filtering liquid rubidium through a filtering unit made of a porous material resistant to liquid rubidium metal.

Abstract: The present disclosure generally relates to a new process for generating germanium-68 from an irradiated target body. The process includes irradiation of the target body followed by various extraction techniques to generate the germanium-68.

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: Isotope enrichment by laser activation wherein a multi-isotopic element Q, like Uranium, Silicon, Carbon is incorporated into gaseous QFn, QF6, QF4, QOmFn, etc and diluted in gas G like He, N2, Ar, Xe, SF6 or other inert gas; and wherein that mixture is cooled by adiabatic expansion or other means encouraging formation of dimers QF6:G in a supersonic super-cooled free jet; and wherein that jet is exposed to laser photons at wavelengths that selectively excite predetermined molecules iQF6 to iQF6*, thereby inducing rapid VT conversions and dissociations of iQF6*:G?iQF6+G+kT, while leaving non-excited dimers jQF6:G intact; and wherein a skimmer separates the supersonic free-jet core stream containing heavier jQF6:G dimers from lighter core-escaped iQF6-enriched rim gases.

Abstract: A tritium removal device for a lithium loop comprises a neutron source (1) for colliding proton on a lithium flow, thereby generating neutrons, a lithium tank (11) for letting the lithium passing through this neutron source (1) to flow into through a flow passage (9), thereby for temporality accumulating it therein, and a lithium pump (17) for circulating and supplying the lithium of this lithium tank (11) to the neutron source (1) through a supply-side flow passage (9?). The lithium tank (11) and the lithium pump (17), into which hydrogen gas containing tritium therein can be easily collected, are enclosed within a hermetically sealed container (7) including an inactive gas therein, so that even if the hydrogen gas including the tritium therein is leaked into the hermetically sealed container (7), it is removed by a hydrogen isotope removal filter. It is possible to remove the tritium, with safety, without diffusing the tritium from an inside of the lithium loop for forming a target flow into an atmosphere.

Abstract: A process for producing technetium-99m from a molybdenum-100 metal powder, comprising the steps of: (i) irradiating in a substantially oxygen-free environment, a hardened sintered target plate coated with a Mo-100 metal, with protons produced by a cyclotron; (ii) dissolving molybdenum ions and technetium ions from the irradiated target plate with an H2O2 solution to form an oxide solution; (iv) raising the pH of the oxide solution to about 14; (v) flowing the pH-adjusted oxide solution through a resin column to immobilize K[TcO4] ions thereon and to elute K2[MoO4] ions therefrom; (vi) eluting the bound K[TcO4] ions from the resin column; (vii) flowing the eluted K[TcO4] ions through an alumina column to immobilize K[TcO4] ions thereon; (viii) washing the immobilized K[TcO4] ions with water; (ix) eluting the immobilized K[TcO4] ions with a saline solution; and (x) recovering the eluted Na[TcO4] ions.

Abstract: A target supply apparatus includes a tank for storing a liquid target material, a nozzle for outputting the liquid target material in the tank, and a gas supply source for supplying gas into the tank, and controls a gas pressure inside the tank with a pressure of the gas supplied from the gas supply source which is provided with a pressure regulator. The target supply apparatus also includes a pressure-decrease gas passage of which one end is connected to the tank and the other end forms an exhaust port, a pressure-decrease valve provided on the pressure-decrease gas passage, and a controller for controlling open/close of the pressure-decrease valve. The controller, when the target material is caused not to output from the nozzle, opens the pressure-decrease valve and decreases the pressure inside the tank.

Abstract: A method for producing 99mTc may include: providing a solution comprising 100Mo-molybdate-ions; providing a proton beam having an energy suitable for inducing a 100Mo (p, 2n) 99mTc-nuclear reaction when exposing 100Mo-molybdate-ions; exposing the solution to the proton beams and inducing a 100Mo (p, 2n) 99mTc-nuclear reaction; and applying an extraction method for extracting the 99mTc from the solution. Further, a device for producing 99mTc may include: a solution with 100Mo-molybdate-ions; an accelerator for providing a proton beam with energy which is suitable for inducing a 100Mo (p, 2n) 99mTc-nuclear reaction when exposing 100Mo-molybdate-ions, for exposing the solution and for inducing a 100Mo (p, 2n) 99mTc-nuclear reaction; and an extraction step for extracting 99mTc from the solution.

Abstract: A method for producing a reaction product containing 99mTC may include providing 100Mo-metal targets to be irradiated, irradiating the 100Mo-metal target with a proton stream having an energy for the induction of a 100Mo(p, 2n)99mTC core reaction, heating the 100Mo-metal target to over 300° C., recovering incurred 99mTc in a sublimation-extraction process with the aid of oxygen gas which is conducted over the 100 Mo-metal target forming 99mTc-Technetium oxide. Further, a device for producing the reaction product containing 99mTc may include a 100Mo metal target, an acceleration unit for providing a proton stream, which can be directed to the 100Mo-Metal target, such that a 100Mo(p, 2n)99mTC core reaction is induced upon irradiation of the 100Mo-metal target by the proton stream, a gas supply line for conducting oxygen gas onto the irradiated 100Mo-metal target to form 99mTC-Technetium oxide, and a gas discharge line to discharge the sublimated 99mTC-Technetium oxide.

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: 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 power generation device that converts matter into energy. A solenoid is rotated circumferentially at high speed clockwise or counter-clockwise. A coiled semi-conductor tube of similar size, which contains charged particles in gas or plasma form is rotated at high speed in the opposite direction. The hollow coil is wrapped in a conducting coil that creates a magnetic field inside it, holding the particles in place as an RF coil injects a resonant frequency to align the spins of the particles. The particles are driven at a high rate of speed into the solenoid's Magnetic field. The resulting energy output is collected.

Abstract: Disclosed is a device for separating radioisotope thallium-201. The device includes an evaporation unit for a solution vial, a first glass vial connected to a first valve and a second valve, an ion exchange column connected to a third valve, a second glass vial connected to a fourth valve and a fifth valve, a collection vial for receiving solution from the fifth valve, a product vial with a membrane filter and a vacuum unit connected to the first valve, the fourth valve and a sixth valve. This device can separate out high-concentration thallium-201 solution from which radioisotope thallium-201 can be obtained.

Abstract: The invention relates to the field of nuclear technology and radiochemistry, more specifically to the production and isolation of radionuclides for medical purposes. The method for producing actinium-225 and isotopes of radium comprises irradiating a solid block of metallic thorium of a thickness of 2 to 30 mm, which is contained within a hermetically sealed casing made of a material which does not react with thorium, with a flow of accelerated charged particles with high intensity. The irradiated metallic thorium is removed from the casing and is either heated with the addition of lanthanum and the distillation of radium or is dissolved in nitric acid with the recovery of actinium-225 by extraction. A target for implementing this method consists of blocks of metallic thorium of a thickness of 2 to 30 mm, which are contained within a hermetically scaled casing made of different materials which do not react with thorium.

Abstract: An improved biomarker generator and a method suitable for efficiently producing short lived radiopharmaceuticals in quantities on the order of a unit dose. The improved biomarker generator includes a particle accelerator and a radiopharmaceutical micro-synthesis system. The micro-accelerator of the improved biomarker generator is optimized for producing radioisotopes useful in synthesizing radiopharmaceuticals in quantities on the order of one unit dose allowing for significant reductions in size, power requirements, and weight when compared to conventional radiopharmaceutical cyclotrons.

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: Methods for producing Tc-99m radioisotope by proton irradiation of a fluid target matrix. A method of producing Tc-99m includes irradiating a fluid target matrix comprising Mo-100 with a proton beam to transform at least a portion of Mo-100 to Tc-99m. Optionally, the fluid target matrix further includes at least one of O-18, O-16, or N-14, which upon exposure to the proton beam concurrently transform at least a portion of O-18 to F-18, at least a portion of O-16 to N-13, at least a portion of the O-16 to O-15, or at least a portion of N-14 to C-11. The method further includes isolating Tc-99m and optionally at least one of F-18, N-13, O-15, or C-11 from the irradiated fluid target matrix. An additional source of Tc-99m is available from the decay of Mo-99 that is co-produced from the Mo-100 during irradiation with the proton beam.

Abstract: The present invention is related to a device and a method for producing a radioisotope of interest from a target fluid irradiated with a beam of accelerated charged particles, the device includes in a circulation circuit (17): an irradiation cell (1) having a metallic insert (2) able to form a cavity (8) designed to house the target fluid and closed by an irradiation window (7), the cavity (8) including at least one inlet (4) and at least one outlet (5); a pump (16) for circulating the target fluid inside the circulation circuit (17); an external heat exchanger (15); the pump (16) and the external heat exchanger (15) forming external cooling means of the target fluid; the device means for pressurizing (14) of the circulation circuit (17) and the external cooling means of the target fluid are arranged in such a way that the target fluid remains inside the cavity (8) essentially in the liquid state during the irradiation.

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: An apparatus for containing and cooling enriched water for the production of activated fluorine (18F). A target assembly includes internal cooling channels in which developed flow of a coolant removes the heat from the target liquid in the target chamber. In one embodiment, the target assembly is fabricated of tantalum.

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 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: A system for automatic production of radioisotopes includes an irradiation unit connectable to a cyclotron and having an electrolytic cell; a purification unit for purifying the radioisotope formed in the irradiation unit; two conduits for transferring an irradiated and electrodissolved target from the irradiation unit to the purification unit; and a central control unit for controlling both the operating units and the transfer means. The method for producing radioisotopes is such that the target carrier is not dissolved together with the irradiated target.

Abstract: The present invention provides a method and an apparatus for extracting an isotope from a gas. More specifically, the present invention depicts a system that has been devised which provides [18F] fluoride from a cyclotron target in non-aqueous media.

Abstract: In a method for producing a radionuclide, a target chamber is filled with target fluid and pressurized. A particle beam is applied to the target chamber to irradiate target material of the target fluid, and the target fluid becomes heated. The heated target liquid may expand out from the target chamber through a lower opening. A space including target fluid vapor may be created in an upper region of the target chamber. The upper region is sealed to maintain the vapor space.

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: 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 (2) forming a cavity (7) designed to house the target material and to be closed by an irradiation window, characterized in that said metallic insert (2) comprises at least two separate metallic parts (8,9) of different materials, being composed of at least a first part (8) comprising said cavity (7).

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: An apparatus for producing a radionuclide includes a target chamber including a beam strike region for containing a liquid and a condenser region for containing a vapor. A particle beam source is operatively aligned with the beam strike region, and a lower liquid conduit communicates with the beam strike region. The condenser region is disposed above the beam strike region in fluid communication therewith for receiving heat energy from the beam strike region and transferring condensate to the beam strike region. The lower liquid conduit transfers liquid to and from the beam strike region. In operation, the target chamber acts as a thermosyphon that is self-regulating in response to heat energy deposited by the particle beam source. A portion of the liquid expands into the lower liquid conduit prior to boiling. After boiling begins, a vapor void is created above the liquid and an evaporation/condensation cycle is established, with additional liquid being displaced into the lower liquid conduit.

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 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 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: A process and apparatus for producing the 18F isotope from water enriched with the 18O isotope using high energy protons from a cyclotron. The apparatus has a cyclotron target cavity that is connected to a fluid loop that contains a water reservoir, pump, and pressure regulator. Water is continuously recirculated through the target cavity to increase reliability. After irradiation long enough to produce a desired amount of 18F, water in the target loop is diverted through an 18F extraction device before being returned to the target loop. The returning water may also be purified and additional water added to the target loop as needed to permit continuous irradiation and production of 18F.