A radioisotope power source is disclosed. In one embodiment, the power source includes a dielectric liquid held within a vessel, a radioisotope material dissolved as an ionic salt within the dielectric liquid thereby forming an ionic salt solution, and a thermal-to-electric power conversion system configured to receive thermal heat generated from the decay of the radioisotope material and to generate electrical power.

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.

A radioisotope elution system is provided. The radioisotope elution system may comprise a controller that is configured to calculate the available amount of daughter radioisotope at any time during establishment of the equilibrium for decay of the parent radioisotope into its daughter radioisotope. The radioisotope elution system may comprise a controller that is configured to schedule various patient infusions planned for the next following days and weeks in accordance with the available amount of daughter radioisotope on each day. The elution system may also comprise a controller that is connected to the imaging software of a radioisotope imaging device, where the radioisotope imaging device is arranged for imaging the patient or a region of the patient; and the controller is configured to start an image acquisition at a predetermined time.

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.

A closure includes a body extending longitudinally along a central longitudinal axis from a first, upper surface to a second, lower surface. The body defines a cavity extending into the body from the lower surface to a third, interior surface. The cavity is sized and shaped to receive a portion of a container therein. The body includes a shroud extending from the interior surface to the lower surface, and a container insert depending from the interior surface and positioned within the cavity. The container insert is sized and shaped to fit within an opening of the container. The body further includes an outlet flow path in fluid communication with the cavity, and at least one inlet flow path in fluid communication with the cavity. The at least one inlet flow path is positioned and oriented to generate a vortex gas flow within the container when connected thereto.

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 nuclear medicine infusion system (10) may be used to generate and infuse radioactive liquid into a patient undergoing a diagnostic imaging procedure. In some examples, the infusion system includes a frame (30) that carries a radioisotope generator (52) that generates radioactive eluate via elution. The frame may also carry a beta detector (58) and a gamma detector (60). The beta detector can be positioned to measure beta emissions emitted from the radioactive eluate supplied by the generator. The gamma detector can be positioned to measure gamma emissions emitted from a portion of the radioactive eluate to evaluate a safety of the radioactive eluate delivered by the infusion system.

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.

A method of separating actinium and/or radium from proton-irradiated thorium metal. The thorium metal is irradiated to produce isotopes including thorium, actinium and/or radium. The resultant product is dissolved in solution and a selective precipitant is used to precipitate a bulk portion of the thorium. The precipitated thorium can be recovered. Chromatography is carried out on the remaining solution to remove residual thorium and to separate the actinium from the radium.