A method for transferring a radioisotope which is fixed on a first stationary phase contained in a first chromatography column to a second stationary phase contained in a second chromatography column, to fix the radioisotope on the second stationary phase, wherein the radioisotope is selected from the radioactive isotopes of thorium, radium, lead, bismuth and uranium, the method comprising at least the following steps: a) eluting the radioisotope from the first stationary phase with an aqueous solution A1 comprising an agent complexing the radioisotope, whereby an aqueous solution A2 which comprises complexes of the radioisotope is obtained; b) dissociating the complexes of the radioisotope present in the aqueous solution A2 by modifying the pH of the aqueous solution A2, whereby an aqueous solution A3 comprising the decomplexed radioisotope is obtained; c) loading the second stationary phase with the aqueous solution A3; and d) washing at least one the second stationary phase with an aqueous solution A4.

The invention provides a method for generating medical isotopes, the method comprising contacting a primary radiation beam with a converter for a time sufficient to produce a secondary beam of gamma particles, and contacting the beam of gamma particles to a target, where the cross section dimension of the beam of gamma particles is similar to the cross section dimension of the target. Both the converter and target are small in diameter and very closely spaced. Also provided is a system for producing medical isotopes, the device comprising a housing having a first upstream end and a second downstream end, a radiotransparent channel (collimator) with a first upstream end and a downstream end, wherein the upstream end is adapted to receive a radiation beam, a target positioned downstream of the downstream end of the channel and coaxially aligned with the channel, wherein the target has a cross section that is similar to the cross section of the channel.

A breeder blanket for generating tritium using neutrons produced by nuclear fusion of deuterium and/or tritium within a plasma confined within a fusion reactor. The breeder blanket comprises: a plasma-facing first wall; a breeder layer comprising lithium containing material for generating tritium from the neutrons; and neutron moderator material comprising metal hydride and/or deuteride arranged between the first wall and the lithium-containing material.

The method and kit for detecting technetium-99m radioisotopes provide color-change solutions for visual detection of technetium-99m radioisotope-based tracers. A first color-change solution is formed from a mixture of thymol blue sodium salt solution and bromocresol purple solution. A first sample to be tested is determined to be a substance containing technetium-99m radioisotopes when the first sample to be tested turns yellow in color following spraying with the first color-change solution. A second color-change solution is formed from a mixture of bromocresol green solution and neutral red solution. A second sample to be tested is determined to be a substance containing technetium-99m radioisotopes when the second sample to be tested turns purple in color following spraying with the second color-change solution. The method and kit provide a rapid test for distinguishing a spill of radioactive TC-99m tracer from a saline spill in a nuclear medicine facility.

Methods and systems for producing Xenon-133 are disclosed. A method for producing Xenon-133 includes collecting an off gas from a Molybdenum-99 production process in a storage tank. The off gas includes Xenon-133 and Krypton-85. The method further includes selectively adsorbing Xenon-133 from the off gas onto a charcoal column assembly such that Xenon-133 is selectively adsorbed onto the charcoal column assembly relative to Krypton-85. The method further includes desorbing the Xenon-133 from the charcoal column assembly by heating the charcoal column assembly, and condensing the Xenon-133 within a coil assembly.

A method for producing .sup.225Ac solution includes steps (I) to (III): a step (I) of passing a solution containing .sup.226Ra and .sup.225Ac through a solid-phase extraction agent (a) that contains a compound represented by formula (A) so as to cause the solid-phase extraction agent (a) to retain .sup.225Ac; a step (II) of passing a liquid containing an eluate, which is obtained by eluting the retained .sup.225Ac from the solid-phase extraction agent (a), through a solid-phase extraction agent (b) that contains a compound represented by formula (B) so as to cause the solid-phase extraction agent (b) to retain .sup.225Ac; and a step (III) of eluting the retained .sup.225Ac from the solid-phase extraction agent (b) to obtain an .sup.225Ac solution.

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Apparatus (10) for the production of radioisotopes that has a connection element (9) that may be connected to a radiation source, a foil holder block (8) connected to this connection element (9) and a first foil (80a) secured by the foil holder block (8) in a beam channel (11) delimited by the connection element (9), the foil holder block (8) and a cooling connection block (7) connected to this, a target holder (4) connected to the cooling connection block (7) and a target holder actuator (2) driving this, a dissolution chamber (5) that may be connected to the target holder (4), characterised by that the target holder (4) has two or more cavities (41), which cavities (41) are adapted for accommodating a target (42) and a dissolution chamber actuator (3) is connected to the dissolution chamber (5), and a method for producing radioisotopes in such an apparatus.

A method of providing alpha particle emitters and materials suitable for use in generating the alpha particles for medical treatment is disclosed. Metal oxide targets, preferentially Bi.sub.2O.sub.3 pellets and Bi.sub.2O.sub.3 coatings on metallic or metal oxide substrates are formed. The targets placed in a heated vacuum chamber subjecting to irradiation using a .sup.6Li beam at an elevated temperature below the melting point of the target generate a radioactive gas, such as .sup.211Rn, the radioactive gas is carried by an inert gas which is delivered a carrier for, such as a carbon column or oil for delivery to a treatment facility. The radioactive gas such as .sup.211Rn generates .sup.211At, which has a useable half-life of at least about 14 hours, in turn releases alpha particles which are effective for use in medical procedures.

A target irradiation system for irradiating a radioisotope target in a vessel penetration of a fission reactor, including a target delivery assembly including a body defining a central bore, a basket that is slidably receivable within the central bore of the body, and a winch that is connected to the basket by a cable, the target delivery assembly being affixed to the vessel penetration of the reactor, and a target passage that is in fluid communication with the target delivery assembly, wherein the basket is configured to receive the radioisotope target therein via the target passage and be lowered into the vessel penetration of the reactor when irradiating the radioisotope target, and the target delivery system forms a portion of the pressure boundary of the reactor when in fluid communication with the reactor.

Methods for setting up, maintaining and operating a radiopharmaceutical infusion system, that includes a radioisotope generator, are facilitated by a computer of the system. The computer may include pre-programmed instructions and a computer interface, for interaction with a user of the system, for example, in order to track contained volumes of eluant and/or eluate, and/or to track time from completion of an elution performed by the system, and/or to calculate one or more system and/or injection parameters for quality control, and/or to perform purges of the system, and/or to facilitate diagnostic imaging.