Abstract: The invention provides a new chemical process, a new cassette configuration, and new software. The invention allows one synthesizer in one hot cell to produce sequentially two batches of [18F]-labelled PET tracer in the same day.

Abstract: Target assembly for an isotope production system. The target assembly includes a target body having a production chamber and a beam cavity that is adjacent to the production chamber. The production chamber is configured to hold a target material. The beam cavity is configured to receive a particle beam that is incident on the production chamber. The target assembly also includes a target foil positioned to separate the beam cavity and the production chamber. The target foil has a side that is exposed to the production chamber such that the target foil is in contact with the target material during isotope production. The target foil includes a material layer having a nickel-based superalloy composition.

Abstract: The present invention provides a method for the treatment of malignant neoplasias comprising the step of administering an L-phenylalanine conjugated to a beta- or alpha-emitting isotope to a subject in the need thereof. Moreover, the invention provides a method for the monitoring of the progress of such treatment of malignant neoplasias.

Abstract: The present invention relates to an automatic system for synthesizing iodine-123 meta-iodobenzylguanidine (123I-MIBG), which comprises a first reactor for subjecting radioactive iodine-containing sodium iodide and meta-iodobenzylguanidine (MIBG) sulfate to an iodine-iodine exchange reaction to obtain radioactive iodine labeled MIBG; a purification unit for purifying the iodine labeled MIBG; and a second reactor for substituting a solvent used in purification with a phosphate buffer to obtain a phosphate solution containing 123I-MIBG. The present invention also relates to an automatic device for dispensing 123I-MIBG, which comprises the automatic system for synthesizing 123I-MIBG, a radioactivity measuring unit, and a dispensing and packing unit.

Abstract: The subject of the invention is a process for heat production with nuclear interactions. During the process the gas is pumped through a stack of nanoparticles in a device featuring an internal and an external chamber via an inlet and an outlet opening, and the process is initiated by heating the device. Further, the subject of the invention is a device accomplishing said process. The device has an interconnected internal chamber, and surrounding said chamber there is an external chamber having at least one inlet and one exit opening. There are nanoparticles in the internal chamber. There is an impermeable wall between the two said chambers. The internal chamber is separated from the exit opening by a heat resistant, porous ceramic wall. There is a heating element on the internal side wall.

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: 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: A material is exposed to a neutron flux by distributing it in a neutron-diffusing medium surrounding a neutron source. The diffusing medium is transparent to neutrons and so arranged that neutron scattering substantially enhances the neutron flux to which the material is exposed. Such enhanced neutron exposure may be used to produce useful radio-isotopes, in particular for medical applications, from the transmutation of readily-available isotopes included in the exposed material. It may also be used to efficiently transmute long-lived radioactive wastes, such as those recovered from spent nuclear fuel. The use of heavy elements, such as lead and/or bismuth, as the diffusing medium is particularly of interest, since it results in a slowly decreasing scan through the neutron energy spectrum, thereby permitting very efficient resonant neutron captures in the exposed material.

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: 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 device for preparing a radioactive water solution to be infused in a patient includes a reaction chamber (13) in which radioactive water vapour is formed by the catalysed reaction of oxygen gas containing oxygen-15 and hydrogen gas. A diffusion chamber (14) is provided which allows the radioactive water to penetrate, but which prevents the penetration of gasses. Tubes (26) and valves (16, 18) direct a sterile saline solution to the diffusion chamber (14), and then direct the saline solution containing radioactive water out from the diffusion chamber to a patient, or to a decay coil (22) being a part of the device. A measuring instrument is provided for measuring the radioactivity of the radioactive solution. The device is characterized in that the diffusion chamber (14), the tubes (26) the valves (16, 18), the radioactivity measuring instrument (17), and preferably also the reaction chamber 913), are mounted in the same frame 50, whereby they form a separate unit i.e.

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: 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: 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: Insuring a constant supply of radioisotopes is of great importance to medicine and industry. This invention addresses this problem, and helps to solve it by introducing a new apparatus for transmutation of isotopes which enables swift and flexible production on demand.

Abstract: Insuring a constant supply of radioisotopes is of great importance to medicine and industry. This invention addresses this problem, and helps to solve it by introducing a new apparatus for transmutation of isotopes which enables swift and flexible production on demand.

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: 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: Actinides metals are recovered from spent nuclear fuel oxides containing fission products by a pyrochemical process. The process comprises, in part, electrorefining the metal complex from an anode by electrolytically oxidizing actinides into a salt and then electrodepositing actinides onto a cathode to form an actinide metal deposit. The actinide metal deposit is then melted to separate the salts and the actinide metals. The separated salt is recycled into an electrorefiner and the actinide metals are recovered and then transferred to a fuel fabrication system.

Abstract: This invention relates to a method for synthesizing Iodine-124 and also a class of radiopharmaceutical which, by virtue of an Iodine-124 label, can be used for both diagnostic and therapeutic purposes. The method comprises an innovative technique for preparing an irradiation target, irradiating the prepared target, and finally collecting Iodine-124 created by the irradiation. The method of this invention provides Iodine-124 in sufficient yields and radionuclidic purity that can be used with positron emission tomography. The invention further relates to the use of Iodine-124 in a chemical form incorporated into organic and inorganic radiopharmaceuticals.

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.