A method for producing 225.sup.A including: a method (X) for purifying a .sup.226Ra-containing solution, including an adsorption step of allowing a .sup.226Ra ion to adsorb onto a carrier having a function of selectively adsorbing a divalent cation by bringing a .sup.226Ra-containing solution into contact with the carrier under an alkaline condition, and an elution step of eluting the .sup.226Ra ion from the carrier under an acidic condition; a method for producing a .sup.226Ra target, including an electrodeposition liquid preparation step of preparing an electrodeposition liquid by using a purified .sup.226Ra-containing solution obtained by the method (X), and an electrodeposition step of electrodepositing a .sup.226Ra-containing substance on a substrate by using the electrodeposition liquid; and a step of irradiating a .sup.226Ra target produced by the method for producing a .sup.226Ra target with at least one selected from a charged particle, a photon, and a neutron by using an accelerator.

A method of making Lu-177 involving dissolving enriched Yb.sub.2O.sub.3, loading dissolved enriched Yb.sub.2O.sub.3 on a first guard column containing resin prepared from (2-ethyl-1-hexyl)phosphonic acid mono(2-ethyl-1-hexyl)ester (HEH[EHP]), passing a first separation of a stream exiting from first guard column through a first resin cartridge containing dipentyl pentylphosphonate, collecting Lu-177 onto a first collection column having resin containing tetraoctyl diglycolamide (DGA), loading an exiting stream from first collection column on a second guard column containing resin prepared from (2-ethyl-1-hexyl)phosphonic acid mono(2-ethyl-1-hexyl)ester (HEH[EHP]); passing a first separation of a stream exiting from second guard column through a second resin cartridge containing dipentyl pentylphosphonate; collecting Lu-177 onto a second collection column having resin containing DGA; passing a second separation of a stream exiting from second guard column through a third resin cartridge containing dipentyl pentylphosphonate; and collecting Lu-177 having passed through the third resin cartridge onto a third collection column having resin containing DGA.

Among the various aspects of the present disclosure is the provision of methods for producing radioisotopes and improving the specific activity of radioisotopes (e.g., Cu-64 chloride). As described herein, the method includes matching of the target material and the proton beam strike area or the proton beam strike shape, resulting in improved specific activity while reducing the amount of target material used.

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.

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 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.

The present disclosure is directed to a nuclear thermionic avalanche cell (NTAC) systems and related methods of generating energy comprising a radioisotope core, a plurality of thin-layered radioisotope sources configured to emit high energy beta particles and high energy photons, and a plurality of NTAC layers integrated with the radioisotope core and the radioisotope sources, wherein the plurality of NTAC layers are configured to receive the beta particles and the photons from the radioisotope core and sources, and by the received beta particles and photons, free up electrons in an avalanche process from deep and intra bands of an atom to output a high density avalanche cell thermal energy through a photo-ionic or thermionic process of the freed up electrons.

A neutron activator for neutron activation of a material, the neutron activator being configured to produce neutrons from an interaction with a proton beam (7), the neutron activator comprising: a neutron source comprising a metallic target (1), and a Beryllium first reflector-moderator (4) peripheral to the neutron source and comprising a neutron activation area (10) configured to accommodate the neutron source and the material to be activated, the neutron activation area (10) of the first reflector-moderator (4) comprising a bore configured to accommodate the neutron source.