Compositions comprising high levels of high specific activity copper-64, and process for preparing said compositions. The compositions comprise from about 2 Ci to about 15 Ci of copper-64 and have specific activities up to about 3800 mCi copper-64 per microgram of copper. The processes for preparing said compositions comprise bombarding a nickel-64 target with a low energy, high current proton beam, and purifying the copper-64 from other metals by a process comprising ion exchange chromatography or a process comprising a combination of extraction chromatography and ion exchange chromatography.

An apparatus for producing Pb-212. The apparatus comprises an emanation box that comprises an emanation source comprising a porous non-reactive material. The emanation box receives at least one of Th-228 and Ra-224, wherein the at least one of Th-228 and Ra-224 decays to Rn-220 within the emanation box. The apparatus further includes a carrier gas feed coupled to the emanation box. The carrier gas feed directs an inert gas into the emanation box and the inert gas carries the Rn-220 out of the emanation box through a carrier gas exit port of the emanation box. The apparatus also includes one or more Rn-220 targets coupled to the carrier gas exit port. The carrier gas carries the Rn-220 from the emanation box to the one or more Rn-220 targets and the Rn-220 decays into Pb-212 within the one or more Rn-220 targets. The Pb-212 is directed into the Pb-212 collection container.

The present invention is directed to processes for ionizing one or more lanthanide isotopes, processes for separating lanthanide isotopes, various apparatus and systems useful for these processes, and compositions prepared from these processes.

The disclosure provide an apparatus for producing a nuclide by using a liquid target which can perform the nuclear reaction process and can discharge the radioactive gas such as Radon within the vial. As described above, an apparatus for producing a nuclide by using a liquid target according to the present disclosure can minimize quantitative loss of a reactant by performing the nuclear reaction process using a target of a liquefied state and reusing a liquefied target on which the nuclear reaction process has not been performed, and can improve safety by enabling the radioactive gas generated to be disposed.

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 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.