A carrier for an irradiated target includes a first portion and a second portion having inner walls. One or both of the first and second portions has a recess extending inwardly from the inner wall thereof to receive the irradiated target. The first and second portions are removably attachable in sealing engagement. The inner walls face each other and form a barrier around the recess upon the first and second portions being removably attached. A fastening system provided on one or both of the first and second portions maintains the first and second portions in sealing engagement. There is also disclosed a kit of the carrier and the irradiated target, a dissolution system for producing a solution from the irradiated target, and a corresponding method.

A method that includes accelerating ions toward a lattice of carbon fibers and capturing the ions in the lattice of carbon fibers.

A new column-based purification system and approach are described for rapid separation and purification of the alpha-emitting therapeutic radioisotope .sup.211At from dissolved cyclotron targets that provide highly reproducible product results with excellent .sup.211At species distributions and high antibody labeling yields compared with prior art manual extraction results of the prior art that can be expected to enable enhanced production of purified .sup.211At isotope products suitable for therapeutic medical applications such as treatment of cancer in human patients.

The present invention relates to monolithic bodies, uses thereof and processes for the preparation thereof. Certain embodiments of the present invention relate to the use of a monolithic body in the preparation of a radioactive substance, for example a radiopharmaceutical, as part of a microfluidic flow system and a process for the preparation of such a monolithic body.

A method for the manufacture of Actinium-225 from a Radium-226 containing material. Radium-226 containing starting target material is shielded with a thermal neutron absorption shield and is subjected to neutron irradiation from a moderated nuclear reactor. Radium-226 is thereby converted into Radium-225 to provide a Radium-225-containing material. The Radium-225 in the Radium-225 containing material is allowed to decay into Actinium-225, and the Actinium-225 is isolated from the Radium-225 containing material. The neutron absorption shield shields the starting target material from neutrons having an energy in the range of 20 eV to 1000 eV.

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.

An apparatus for producing .sup.99Mo from a plurality of .sup.100Mo targets through a photo-nuclear reaction on the .sup.100Mo targets. The apparatus comprises: (i) an electron linear accelerator component; (ii) an energy converter component capable of receiving the electron beam and producing therefrom a shower of bremsstrahlung photons; (iii) a target irradiation component for receiving the shower of bremsstrahlung photons for irradiation of a target holder mounted and positioned therein. The target holder houses a plurality of .sup.100Mo target discs. The apparatus additionally comprises (iv) a target holder transfer and recovery component for receiving, manipulating and conveying the target holder by remote control; (v) a first cooling system sealingly engaged with the energy converter component for circulation of a coolant fluid therethrough; and (vi) a second cooling system sealingly engaged with the target irradiation component for circulation of a coolant fluid therethrough.

Methods of performing targeted alpha therapy of a cancer patient utilizing actinium-225, methods of preparing a targeted alpha therapy drug that includes actinium-225, methods of preparing actinium-225 from radium-226, and methods of recovering radium-226 from an aqueous produced material stream generated from a natural resource extraction process. The methods of recovering radium-226 include separating the radium-226 from the produced material stream to generate recovered radium-226. The methods of preparing actinium-225 include converting the recovered radium-226 into actinium-225. The methods of preparing the targeted alpha therapy drug include incorporating the actinium-225 into the targeted alpha therapy drug. The methods of performing targeted alpha therapy include treating the cancer patient with the targeted alpha therapy drug.

Apparatus for radioisotope production includes housing, a plurality of target disks inside the housing and a curved windows positioned convex inward toward the disks. During operation, coolant flows though the housing across the disks and windows while electron beams passes through the window and the disks. The window temperature increases, rising the fastest in the middle of the window where the electron beam hits the window. A flat window would buckle because the center would deform during thermal expansion against the relatively unaffected periphery, but the curved window shape allows the window to endure high thermal and mechanical stress created by a combination of heating from the electron beam(s) and elevated pressure from coolant on the inside of the window. Such a window may be used for applications in which a pressurized coolant acts on only one side of the window.

An object of the present invention is to provide a method for purifying efficiently and easily a .sup.226Ra-containing solution obtained when .sup.225Ac is produced from a .sup.226Ra target, a method for producing a .sup.226Ra target by using the purified .sup.226Ra-containing solution obtained by the above purification method, and a method for producing .sup.225Ac including these above methods. The method for purifying a .sup.226Ra-containing solution according to the present invention is characterized by including an adsorption step (R1) of allowing .sup.226Ra ions to adsorb onto a carrier having a function of selectively adsorbing divalent cations by bringing a .sup.226Ra-containing solution (a) into contact with the carrier under an alkaline condition; and an elution step (R2) of eluting the .sup.226Ra ions from the carrier under an acidic condition.