Abstract: A particle accelerator assembly with a liquid-target holding assembly usable to produce radioisotopes in liquid targets. A particle accelerator is configured to produce a particle beam along a beam axis, and the liquid-target holding assembly connected to the particle accelerator. The liquid-target retaining assembly has a mounting portion coupled to the particle accelerator, and the mounting portion is configured to receive the particle beam therethrough. A liquid-target holder is connected to the mounting portion and has a holder body with a target cavity that contains a liquid target therein. The target cavity has a longitudinal axis oriented at an acute angle relative to the particle beam axis. The target cavity has a first depth along an axis perpendicular to the longitudinal axis and has a projected depth along the beam axis greater than the first depth.

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.

Abstract: The transmutation of radioactive material using a hybrid transmutation reactor is disclosed wherein a kinetic proton source is used to collisionally induce the transmutation of radioactive material with the generation of thermal neutrons as a byproduct. Additionally, a system and method for the production of Tritium utilizing the thermal neutrons generated in the transmutation process is further described. The present invention offers advantages and improvements over existing nuclear reactor technologies in that nuclear waste may be rendered inert, or otherwise at least partially deactivated and/or made less dangerous, with the substantially simultaneous production of energy and/or Tritium as a byproduct of the transmutation process.

Abstract: A process for the selective production and isolation of high specific activity Cu67 from proton-irradiated enriched Zn70 target comprises target fabrication, target irradiation with low energy (<25 MeV) protons, chemical separation of the Cu67 product from the target material and radioactive impurities of gallium, cobalt, iron, and stable aluminum via electrochemical methods or ion exchange using both anion and cation organic ion exchangers, chemical recovery of the enriched Zn70 target material, and fabrication of new targets for re-irradiation is disclosed.

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.

Abstract: A process for the selective production and isolation of high specific activity cu67 from proton-irradiated enriched Zn70 target comprises target fabrication, target irradiation with low energy (<25 MeV) protons, chemical separation of the Cu67 product from the target material and radioactive impurities of gallium, cobalt, iron, and stable aluminum via electrochemical methods or ion exchange using both anion and cation organic ion exchangers, chemical recovery of the enriched Zn70 target material, and fabrication of new targets for re-irradiation is disclosed.

Abstract: Flow of mercury from a liquid-heavy-metal inflow port toward an inner forward end of a container body is rectified by a plurality of incoming-passage guide vanes in a liquid-heavy-metal incoming passage. Flow of the mercury from the forward end of the container body toward a liquid-heavy-metal outflow port is rectified by a plurality of return-passage guide vanes in a liquid-heavy-metal return passage. As a result, occurrence of stagnation and/or recirculation flows of the mercury in the container body is suppressed and a steady and highly uniform stream of the mercury is formed throughout in the container body. The container body is covered with a container outer shell to prevent any leakage of the mercury to outside due to a damage of the container body.

Abstract: A target grid assembly for employment in a target assembly used to produce radioisotopes by bombarding a target material contained in the target assembly with a particle beam. The target assembly includes the target grid assembly, the target window and a target body enclosed in a target housing. The target body defines a target reservoir for receiving the target material and the target window serves to seal the target reservoir. The target grid assembly includes a vacuum window and a target grid. The target grid defines a target grid portion, a helium input and a helium output. The target grid portion defines a plurality of target grid supports which are configured to form a plurality of target grid oblong openings. The vacuum window is supported against the upstream side of the target grid portion and the target window is supported between the downstream side and the target body.

Abstract: An apparatus and method is described for transmuting higher actinides, plutonium and selected fission products in a liquid-fuel subcritical assembly. Uranium may also be enriched, thereby providing new fuel for use in conventional nuclear power plants. An accelerator provides the additional neutrons required to perform the processes. The size of the accelerator needed to complete fuel cycle closure depends on the neutron efficiency of the supported reactors and on the neutron spectrum of the actinide transmutation apparatus. Treatment of spent fuel from light water reactors (LWRs) using uranium-based fuel will require the largest accelerator power, whereas neutron-efficient high temperature gas reactors (HTGRs) or CANDU reactors will require the smallest accelerator power, especially if thorium is introduced into the newly generated fuel according to the teachings of the present invention.

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: The present invention provides a positron source essentially consisting of a carbon member having 18F bound onto the surface thereof, a method of preparing the same, and an automated system for supplying the same. In the present invention, the positron source is prepared by irradiating a solution containing both H218O and a small amount of natural fluorine ions with a beam of charged particles to generate 18F, and then passing an electric current through the solution using a carbon member 40 as an anode to cause to bind the generated 18F onto the surface of the carbon member.

Abstract: A subcritical reactor-like apparatus for treating nuclear wastes, the apparatus comprising a vessel having a shell and an internal volume, the internal volume housing graphite. The apparatus having means for introducing a fluid medium comprising molten salts and plutonium and minor actinide waste and/or fission products. The apparatus also having means for introducing neutrons into the internal volume wherein absorption of the neutrons after thermalization forms a processed fluid medium through fission chain events averaging approximately 10 fission events to approximately 100 fission events. The apparatus having additional means for removing the processed fluid medium from the internal volume. The processed fluid medium typically has no usefulness for production of nuclear weapons.

Abstract: Palladium-103 radiochemical of high radionuclidic purity can be produced in commercial scale quantities by irradiating enriched Palladium targets comprising a mixture of Pd isotopes with protons or deuterons in the 10-50 MeV energy range. Commercially viable batch sizes with acceptable specific activity of the product Pd-103 are achieved by adjusting the irradiation energy, irradiation time, irradiation current, current density, plated target mass, plated target shape, plated target size, target isotope enrichment levels, and incident angle of the target to the beam. The method for the production of Pd-103 comprises providing a target material enriched with Pd isotopes comprising atomic masses equal to or greater than Pd-103, applying the target material onto a target support; irradiating the target material with protons or deuterons of sufficient incident energy and time to convert at least some of the Pd isotopes within the target material to Pd-103; and purifying Pd from the non-Pd components.

Abstract: A cyclotron and a target system containing rotating foils composed of target nuclide to undergo nuclear reactions with the beam from the cyclotron are integrated into one unit such that the foils intercept the orbit of the accelerating beam in the cyclotron. Accordingly, the beam strikes the foils to undergo nuclear reaction therein and to correspondingly lose a small portion of its energy in its passage through the foils. The transmitted beam from the foils gains the lost energy to the foils as it circulates in the accelerating zone of the cyclotron and subsequently re-strikes the foils. This process of continuing strikes results in accumulation of the beam current striking the foils and proportionally increases the rate of nuclear reactions. Since the beam after striking the foils is re-circulated and regains the energy loss to the foils, the integrated unit is termed the Recyclotron. The targets are designed to dissipate the heat from the beam load primarily by radiation.

Abstract: Radionuclides are produced according to the present invention at commercially significant yields and at specific activities which are suitable for use in radiodiagnostic agents such as PET imaging agents and radiotherapeutic agents and/or compositions. In the method and system of the present invention, a solid target having an isotopically enriched target layer electroplated on an inert substrate is positioned in a specially designed target holder and irradiated with a charged-particle beam. The beam is preferably generated using an accelerator such as a biomedical cyclotron at energies ranging from about 5 MeV to about 25 MeV. The target is preferably directly irradiated, without an intervening attenuating foil, and with the charged particle beam impinging an area which substantially matches the target area.

Abstract: A beam of accelerated charged particles irradiates an arsenide target, such as gallium arsenide or aluminum arsenide, to produce radioisotopes of selenium and other radionuclides. The irradiated target is placed in a niobium, tantalum, or graphite vessel and inserted into a tube. Metallic reagents consisting of an alloy of iron, nickel, and chromium (stainless steel) or metallic aluminum are mixed with the target material. The target is then heated to 1000-1100.degree. C. The metallic reagents prevent arsenic sublimation, destroy the crystalline structure of arsenide target, and remove other impurities, such as zinc-65. The target is then heated a second time to about 1300.degree. C. causing the selenium-72 to sublime and be deposited on a cooler wall of the tube or on a catcher foil surface. The deposited selenium-72 is recovered from the tube or foil.

Abstract: An apparatus for the creation and detection of high velocity alpha particles accompanied by one or two captured electrons. The apparatus is a modification of the well-known Cockcroft and Walton experiment used to disintegrate lithium-7 into high energy alpha particles by bombarding the lithium with high energy protons. The resulting alpha particles with captured electrons cannot be detected by normal helium absorption spectrum techniques and have other unique attributes.

Abstract: A process for the production of radiostrontium consists in that a target of metallic rubidium is bombarded by a flow of accelerating charged particles. The target of irradiated rubidium is melted, whereas the extraction of radiostrontium is carried out by sorption on the surface of a sorbing material immersed into the irradiated molten metallic rubidium. As the sorbing material, use is made of materials selected from the group consisting of heat-resistant metals or metallic oxides or silicon which are inert with respect to rubidium. The resultant radiostrontium is extracted from the irradiated rubidium. The temperature of the sorbing material is selected to be close to the optimum one for the sorption of radiostrontium which is within the range of from the melting point of metallic rubidium to 220.degree. C. And the temperature of molten rubidium is selected to be close to the optimum one for the desorption of radiostrontium within the range of from 220.degree. C. to 270.degree. C.

Abstract: Improved efficiency process for preparing or breeding tritium gas from dense molten lithium alloy by bombardment of the alloy as a target material using a linear accelerator emitting a high energy proton beam to generate a neutron flux. The invention involves using a dense eutectic molten lead lithium alloy as the target material, directing the impact area within the body of molten target material, such as to a depth of about 2 meters of the target material, and continuously circulating the molten alloy past the impact area to dissipate the heat of reaction to provide a substantial lead source for maximum neutron production and to provide an effective lithium source to absorb the neutrons, to produce the highest possible amount of tritium per proton applied by the high energy proton beam. The formed tritium gas is insoluble in and separates from the molten alloy.

Abstract: The invention relates to a process for purifying radioiodides which comprisesa) passing a recovered solution of iodide over an anion exchange resin;b) washing the ion exchange resin in (a) with a solution comprising a weak base or anionic ion;c) washing the ion exchange resin in (a) with a stronger solution than used in (b); andd) recovering a solution with iodide.

Abstract: A process for the synthesis of .sup.13 N-ammonia in target which comprises charging target water and hydrogen into a synthesis apparatus to make a pressurized condition at 0.1-5 kg/cm.sup.2 and irradiating proton beam to the target water which is circulated to produce .sup.13 N-ammonia, a process for the synthesis of .sup.13 N-ammonia in target which comprises bringing the target water containing .sup.13 N-ammonia thus produced into contact with a Na type cation-exchange resin to collect .sup.13 N-ammonia by the cation-exchange, and then bringing the cation-exchange resin into contact with a saline solution to elute the collected .sup.

Abstract: A process for producing radionuclides using a porous carbon target. The process includes the steps of inserting a porous carbon target with tailored solid and void dimensions in the path of a bombarding beam; introducing fluid into the porous carbon target; bombarding the porous carbon target to produce at least one type of radionuclide; collecting the fluid and separating the resulting radionuclides.

Abstract: In a slow positron beam generating device comprising a target member (11) having a .beta..sup.+ decay radioisotope producing function for producing, when an incident surface (11a) of the target member is irradiated by accelerated particles (10), .beta..sup.+ decay radioisotopes due to nuclear reaction within the target member so that the .beta..sup.+ decay radioisotopes emit fast positrons around the .beta..sup.+ decay radioisotopes, a moderator (12) is disposed nearer to an opposite surface (11b) of the target member than the incident surface and has a fast positron moderating function for moderating into slow positrons the fast positrons emitted from the opposite surface. The opposite surface is opposite to the incident surface. An ejecting electrode (13) ejects the slow positrons as a slow positron beam (14). Use may be made of a different target member having not only the .beta..sup.

Abstract: In a slow positron beam generating device comprising a target member (11) having a .beta. decay radioisotope producing function for producing, when an incident surface (11a) of the target member is irradiated by accelerated particles (10 ), .beta..sup.+ decay radioisotopes due to nuclear reaction within the target member so that the .beta..sup.+ decay radioisotopes emit fast positrons around the decay radioisotopes, a moderator ( 12 ) is disposed nearer .beta..sup.+ to an opposite surface (11b) of the target member than the incident surface and has a fast positron moderating function for moderating into slow positrons the fast positrons emitted from the opposite surface. The opposite surface is opposite to the incident surface. An ejecting electrode (13) ejects the slow positrons as a slow positron beam (14). Use may be made of a different target member having not only the .beta..sup.

Abstract: A process for selective separation of sodium-22 from a proton irradiated minum target including dissolving a proton irradiated aluminum target in hydrochloric acid to form a first solution including aluminum ions and sodium ions, separating a portion of the aluminum ions from the first solution by crystallization of an aluminum salt, contacting the remaining first solution with an anion exchange resin whereby ions selected from the group consisting of iron and copper are selectively absorbed by the anion exchange resin while aluminum ions and sodium ions remain in solution, contacting the solution with an cation exchange resin whereby aluminum ions and sodium ions are adsorbed by the cation exchange resin, and, contacting the cation exchange resin with an acid solution capable of selectively separating the adsorbed sodium ions from the cation exchange resin while aluminum ions remain adsorbed on the cation exchange resin is disclosed.

Abstract: A process for selective separation of sodium-22 from an irradiated target including dissolving an irradiated target to form a first solution, contacting the first solution with hydrated antimony pentoxide to selectively separate sodium-22 from the first solution, separating the hydrated antimony pentoxide including the separated sodium-22 from the first solution, dissolving the hydrated antimony pentoxide including the separated sodium-22 in a mineral acid to form a second solution, and, separating the antimony from the sodium-22 in the second solution.

Abstract: A target is bombarded with high energy particles to generate a radioisotope, and the radioisotope is preferably extracted by one of the following: combusting the target in oxygen, stopping the bombardment and heating the target, or heating the target by induction. Bombardment may take place through a windowless path, and the radioisotope may be used for PET. The particles used may be deuterons or protons, and .sup.13 N may be generated. .sup.11 C may also be generated from either .sup.11 B or .sup.10 B using protons or deuterons. Combustion may be performed by induction heating and may be controlled by the quantity of oxygen available or the temperature. Combustion may be primarily confined to a surface layer and the target may be reused. The beam energy may be 2.2 MeV or less. Another general aspect includes trapping the oxides of .sup.13 N in a trap. The oxides may be converted into .sup.

Abstract: A process for simultaneously producing PET-usable quantities of [.sup.13 N]NH.sub.3 and [.sup.18 F]F.sup.- for radiotracer synthesis is disclosed. The process includes producing [.sup.13 N]NO.sub.2.sup.- /NO.sub.3.sup.- and [.sup.18 F]F.sup.- simultaneously by exposing a low-enriched (20%-30%) [.sup.18 O]H.sub.2 O target to proton irradiation, sequentially isolating the [.sup.13 N]NO.sub.2.sup.- /NO.sub.3.sup.- and [.sup.18 F]F.sup.- from the [.sup.18 O]H.sub.2 O target, and reducing the [.sup.13 N]NO.sub.2.sup.- /NO.sub.3.sup.- to [.sup.13 N]NH.sub.3. The [.sup.13 N]NH.sub.3 and [.sup.18 F]F.sup.- products are then conveyed to a laboratory for radiotracer applications. The process employs an anion exchange resin for isolation of the isotopes from the [.sup.18 O]H.sub.2 O, and sequential elution of [.sup.13 N]NO.sub.2.sup.- /NO.sub.3.sup.- and [ .sup.18 F]F.sup.- fractions. Also the apparatus is disclosed for simultaneously producing PET-usable quantities of [.sup.13 N]NH.sub.3 and [.sup.18 F]F.sup.

Abstract: A process for preparation of silicon-32 is provide and includes contacting an irradiated potassium chloride target, including spallation products from a prior irradiation, with sufficient water, hydrochloric acid or potassium hydroxide to form a solution, filtering the solution, adjusting pH of the solution to from about 5.5 to about 7.5, admixing sufficient molybdate-reagent to the solution to adjust the pH of the solution to about 1.

Abstract: A system and process for the production of nitrogen-13 ammonium ions from a target material in the form of a dilute solution of ethanol in natural water by the reaction of protons with oxygen-16 within the target material. The system includes a device for producing a proton beam which travels along a preselected path and strikes the target material in a target chamber. This target chamber is positioned in the path of the proton beam such that subjection of the target material to the beam produces nitrogen-13 atoms in a predetermined form. These nitrogen-13 atoms are converted in the aqueous solution to ammonium, ions and oxides and are conducted from the target holder to a purification device for collecting a purified product containing such ammonium ions. A cooling system serves to dissipate heat generated during the production of the nitrogen-13 atoms by the reaction of protons with the oxygen. Other solutes for the target material are discussed.

Abstract: A process for selective separation of strontium-82 and strontium-85 from proton irradiated molybdenum targets is provided and includes dissolving the molybdenum target in a hydrogen peroxide solution to form a first ion-containing solution, passing the first ion-containing solution through a first cationic resin whereby ions selected from the group consisting of molybdenum, niobium, technetium, selenium, vanadium, arsenic, germanium, zirconium and rubidium remain in the first ion-containing solution while ions selected from the group consisting of rubidium, zinc, beryllium, cobalt, iron, manganese, chromium, strontium, yttrium and zirconium are selectively adsorbed by the first resin, contacting the first resin with an acid solution capable of stripping adsorbed ions from the first cationic exchange resin whereby the adsorbed ions are removed from the first resin to form a second ion-containing solution, evaporating the second ion-containing solution for time sufficient to remove substantially all of the acid

Abstract: This invention relates to a method and apparatus for the generation of isotopes, and in particular radioisotopes, from a target material which is not normally a solid and which, when bombarded by selected high energy particles, produces the selected isotope. A surface is provided which is preferably of a thermally-conductive material, which surface is cooled to a temperature below the freezing temperature of the target material. A thin layer of target material is then frozen on the surface and the target material is bombarded with the high energy particles. The beam of high energy particles is preferably at an angle to the surface such that the particles pass through a thickness of the target material greater than the thickness of the layer before reaching the surface. When the desired quantity of isotope has been produced from the target material, the target material, which has now been altered nuclearly to contain the selected isotope, is removed from the surface.

Abstract: In a process for the synthesis of .sup.11 C-labeled methyl iodide which comprises producing .sup.11 CO.sub.2 by the irradiation of a proton beam, supplying .sup.11 CO.sub.2 gas to a collector of .sup.11 CO.sub.2 gas, bubbling .sup.11 CO.sub.2 gas into a reducing agent solution to reduce .sup.11 CO.sub.2, removing the reducing agent solution by evaporation, synthesizing .sup.11 CH.sub.3 I from the reduced product of .sup.11 CO.sub.2, and recovering .sup.11 CH.sub.3 I by distillation, the termination point of the .sup.11 CO.sub.2 gas supply, the termination point of the bubbling, the termination point of the evaporation of the reducing agent solution or the termination point of the distillation of .sup.11 CH.sub.3 I is decided by a radiation sensor provided in the vicinity of the reaction vessel or a transfer tube connecting the target box wherein .sup.11 CO.sub.2 gas is generated or a temperature sensor provided in an exhaust tube of the reaction vessel. The synthesizing time is shortened, and the yield of .

Abstract: Improved method and means for the detection of nitrogenous material or assaying of nitrogenous material in an object on the basis of nuclear resonant attenuation of 9.17 MeV .gamma.-rays. A target in form of one or several .sup.13 C pellets at least 25.mu. thick, or alternatively in form of a body that bears a composite thin film including at least one .sup.13 C layer not more than 1.mu. thick and at least one other substance that is capable of generating supplementary .gamma.-radiation for determining the non-resonant component of attenuation, is bombarded with 1.75 MeV protons to produce a source of 9.17 MeV .gamma.-rays. The target is placed on one side of the inspected object and a .gamma.-ray detector or an array of such detectors is placed on the other side and the total and non-resonant attenuation are read and evaluated.

Abstract: In a process for the synthesis of .sup.11 C-labeled methyl iodide which comprises producing .sup.11 CO.sub.2 by the irradiation of a proton beam, supplying .sup.11 CO.sub.2 gas to a collector of .sup.11 CO.sub.2 gas, bubbling .sup.11 CO.sub.2 gas into a reducing agent solution to reduce .sup.11 CO.sub.2, removing the reducing agent solution by evaporation, synthesizing .sup.11 CH.sub.3 I from the reduced product of .sup.11 CO.sub.2, and recovering .sup.11 CH.sub.3 I by distillation, the termination point of the .sup.11 CO.sub.2 gas supply, the termination point of the bubbling, the termination point of the evaporation of the reducing agent solution or the termination point of the distillatin of .sup.11 CH.sub.3 I is decided by a radiation sensor provided in the vicinity of the reaction vessel or a transfer tube connecting the target box wherein .sup.11 CO.sub.2 gas is generated or a temperature sensor provide in an exhaust tube of the reaction vessel. The synthesizing time is shortened, and the yield of .sup.

Abstract: Apparatus for nuclear transmutation and power production using an intense accelerator-generated thermal neutron flux. High thermal neutron fluxes generated from the action of a high power proton accelerator on a spallation target allows the efficient burn-up of higher actinide nuclear waste by a two-step process. Additionally, rapid burn-up of fission product waste for nuclides having small thermal neutron cross sections, and the practicality of small material inventories while achieving significant throughput derive from employment of such high fluxes. Several nuclear technology problems are addressed including 1. nuclear energy production without a waste stream requiring storage on a geological timescale, 2. the burn-up of defense and commercial nuclear waste, and 3. the production of defense nuclear material. The apparatus includes an accelerator, a target for neutron production surrounded by a blanket region for transmutation, a turbine for electric power production, and a chemical processing facility.

Abstract: A method of producing Al-26 from potassium chloride by exposing it to a proton beam in order to break potassium and chlorine atoms into smaller pieces, which include Al-26. The Al-26 is isolated from the potassium chloride and other substances produced by the beam by means of extraction and ion exchange.

Abstract: A system for extracting sodium, particularly radioactive .sup.22 Na, from aluminum utilizes a monel exhaust system for exhausting sodium vapor emitted from a molten aluminum target, in a draft of helium gas. The aluminum target is heated until it is melted in a graphite support cup. The graphite support does not react with the sodium. Moreover, the graphite is understood to be permeable to the helium gas, its porosity being believed to provide the significant advantage that the graphite holder will not absorb much of the sodium vapor. The use of graphite avoids a disadvantageous monel-aluminum reaction whereby an alloy from which sodium cannot be distilled is formed. The resulting sodium vapor is precipitated in a monel exhaust tube which is subjected to temperature control. Sodium can be rinsed from the monel exhaust tube with water.

Abstract: A method is provided for preparing medicinally acceptable .sup.123 I by bombarding an XI (X is alkali metal or I) target in the liquid phase with a proton beam of a predetermined amperage and energy, while continuously passing a helium stream, optionally having a small amount of xenon, through the target area. The radioactive xenon collected by the helium stream is trapped in a cold trap, purified and then isolated in a deacy vessel, where the xenon decays to .sup.123 I. An iodine scavenger is provided for the helium effluent from the target, to remove any iodine from the helium stream, which would decrease the purity of the desired isotope.

Abstract: A system and process for the production of nitrogen-13 atoms from carbon-13/fluid slurry is provided. The system (10) includes a device (14) for producing a proton beam (15) which travels along a preselected path and strikes a target in slurry. This target is positioned in the path of the proton beam (15) such that subjection of the target to such beam produces nitrogen-13 atoms in a predetermined form. The nitrogen-13 atoms are conducted from the target area and carried to a purification device for collecting a purified product containing such atoms. The cooling system serves to dissipate heat generated during the production of such nitrogen-13 atoms.

Abstract: Beryllium-7 labeled carbon particles made from the proton irradiation of carbon materials, preferably from dry carbon black are disclosed. Such particles are useful as gamma emitting radiotracers.

Abstract: A method for simultaneously preparing Radon-211, Astatine-211, Xenon-125, Xenon-123, Iodine-125 and Iodine-123 in a process that includes irradiating a fertile metal material then using a one-step chemical procedure to collect a first mixture of about equal amounts of Radon-211 and Xenon-125, and a separate second mixture of about equal amounts of Iodine-123 and Astatine-211.

Abstract: Charged-particles in the 45-15 MeV energy range incident upon isotopically enriched xenon-124 gas in a gas-target assembly cause nuclear reactions which yield radioactive xenon-123. The xenon-123, decaying either in the target assembly or in a decay vessel removed from the target assembly, yields iodine-123 with very low levels of radioactive contaminants.

Abstract: A method of producing carrier-free .sup.67 Cu by proton spallation combined with subsequent chemical separation and purification is disclosed. A target consisting essentially of pressed zinc oxide is irradiated with a high energy, high current proton beam to produce a variety of spallogenic nuclides, including .sup.67 Cu and other copper isotopes. The irradiated target is dissolved in a concentrated acid solution to which a palladium salt is added. In accordance with the preferred method, the spallogenic copper is twice coprecipitated with palladium, once with metallic zinc as the precipitating agent and once with hydrogen sulfide as the precipitating agent. The palladium/copper precipitate is then dissolved in an acid solution and the copper is separated from the palladium by liquid chromatography on an anion exchange resin.