The present invention relates to a method for at least partially digesting a uranium (U)-based target material which comprises at least one uranium-metal (U-Me) alloy containing Mn, Fe, Co or Ni and comprising at least a U6Me phase. By means of an accelerant in a basic solution, the uranium in U-Me alloy oxidizes to U(VI). The accelerant comprises in particular KMnO4 whilst the U-Me alloy comprises a U—Mn alloy. The alloy preferably comprises two phases of an eutectic system, in particular the U6Mn/UMn2 system. The use of the accelerant enables an enhanced digestion of the U-Me alloy.

One embodiment of the present invention relates to a production method of .sup.225Ac includes; a production step of a .sup.226Ra target including an electrodeposition step of electrodepositing a .sup.226Ra-containing substance on a substrate by using an electrodeposition solution that contains .sup.226Ra ions and a pH buffer, and an irradiating step of irradiating the .sup.226Ra target with at least one selected from charged particles, photons, and neutrons.

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 system for producing technetium-99m from molybdate-100. The system comprises: a target capsule apparatus for housing a Mo-100-coated target plate; a target capsule pickup apparatus for engaging, and delivering the target cell apparatus into a target station apparatus; target station apparatus for receiving and mounting therein the target capsule apparatus. The target station apparatus is engaged with a cyclotron for irradiating the Mo-100-coated target plate with protons. The irradiated target capsule apparatus is transferred to a receiving cell apparatus comprising a dissolution/purification module for receiving therein a proton-irradiated Mo-100-coated target plate. A conveyance conduit infrastructure interconnects: (i) the target capsule pickup apparatus with the target station apparatus, (ii) the target station apparatus and the receiving cell apparatus; and (iii) the receiving cell apparatus and the dissolution/purification module.

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 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.

A method for generating a fissile material is described. The method includes positioning a fertile, non-fissile material within outer space, the position within an area of proton or other high energy particle radiation, rather naturally or artificially occurring, allowing the high energy particle radiation to impinge the fertile but non-fissile material over a time, the time based on amount of high energy particle radiation at the position, such that the non-fissile material gradually transmutes into a fissile material due to the impingement, and deploying the fissile material within a spacecraft.

A method for generating a fissile material is described. The method includes positioning a fertile, non-fissile material within outer space, the position within an area of proton or other high energy particle radiation, rather naturally or artificially occurring, allowing the high energy particle radiation to impinge the fertile but non-fissile material over a time, the time based on amount of high energy particle radiation at the position, such that the non-fissile material gradually transmutes into a fissile material due to the impingement, and deploying the fissile material within a spacecraft.