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.

A fuel bundle surrogate for the irradiation of a target material, having a plurality of tube sheaths, each tube sheath being parallel to a longitudinal center axis of the fuel bundle surrogate, a plurality of end caps, a pair of end plates, wherein the end plates are disposed at opposing ends of the plurality of tube sheaths, and a first target comprised of a first target material suitable for producing the isotope by way of a neutron capture event, wherein the first target is disposed in a first tube sheath, and wherein the first tube sheath of the plurality of tube sheaths comprises an elongated thickened wall portion and a pair of annular end portions, each annular end portion being disposed on a corresponding end of the thickened wall portion and having a wall thickness that is less than a wall thickness of the thickened wall portion.

An irradiation target positioning device and method for creating radioisotopes utilizing linear particle beam accelerators or cyclotron accelerators. The device positions a target proximate to a liquid reservoir and vapor expansion chamber. The target may be in a solid phase. Heat produced within the target during irradiation can be absorbed by the liquid. The liquid may be heated to its vaporization temperature and vapor emitted into the vapor chamber. The vapor chamber may utilize a cooling mechanism, allowing the vapor to condense (second phase change). The radioactive product may diffuse into the liquid, thereby allowing the irradiated product to be conveyed out of the target structure in a liquid, solution or slurry. Multiple radioisotopes may be produced simultaneously out of the target material and liquid and separated later. The target material and irradiated product may be removed from the target surface by acid.

Method of separation of a radiometal ion from a target metal ion, comprising a first liquid-liquid extraction step in which an organic phase comprising an extractant and an interfacial tension modifier is mixed with an aqueous phase comprising the radiometal ion and the target metal ion in order that the radiometal ion is at least partially transferred to the organic phase, followed by a first phase separation step, wherein the phase separation is carried out in flow comprising the use of a microfiltration membrane to separate the phases based on the interfacial tension between the phases such that a permeate phase passes through the membrane and a retentate phase does not.

A method for the manufacture of highly purified .sup.68Ge material for radiopharmaceutical purposes. The invention particularly concerns the production of .sup.68Ge-API (API=Active Pharmaceutical Ingredient) solution complying with the Guidelines for good manufacturing practices (GMP). Starting material for the method of the present invention can be a .sup.68Ge stock solution of commercial or other origin as raw material. Such .sup.68Ge containing raw solutions are purified from potential metal and organic impurities originating from production processes. The radiochemical method disclosed is based on a twofold separation of .sup.68Ge from organic and metallic impurities with two different adsorbent materials. During the first separation phase .sup.68Ge is purified from both organic and metallic impurities by adsorption in germanium tetrachloride form, after which hydrolyzed .sup.68Ge is purified from remaining metallic impurities by cation exchange. The final .sup.68Ge-API-product e.g. fulfills the regulatory requirements for specifications of the GMP production of .sup.68Ge/.sup.68Ga generators.

Disclosed is a method of producing Tc-99m by using nuclear resonance fluorescence. More specifically, and a method of preparing Tc-99m by using nuclear resonance fluorescence includes irradiating a ground-state Tc-99 nucleus with a photon beam, thereby causing a nuclear transmutation to proceed such that the nucleus excited to high energy and then undergoes a transition to Tc-99m.

Methods for purifying the molybdenum-99 isotope are disclosed. Molybdenum-99 is loaded onto an anion exchange column and extracted. In some embodiments, the extraction solution may include nitric acid and nitrate salts. In other embodiments, a two stage elution is performed in which a nitric acid containing eluent and a hydroxide containing eluent are used in succession to extract molybdenum-99.

A method for producing a fraction of xenon radioisotopes, comprising the steps of dissolving enriched uranium targets forming a slurry and a gaseous phase containing xenon radioisotopes, isolating the xenon radioisotopes using zeolite doped with silver, preferably chosen from the group consisting of aluminosilicates doped with silver, titanosilicates doped with silver and mixtures thereof, and recovering the fraction of xenon radioisotopes, in particular Xe-133.

Methods and systems for separation of thorium from uranium and their decay products are provided. The method comprises combining a nuclear fuel feedstock comprising thorium and uranium with a first acid to form a first solution. The first solution is contacted an ion exchange resin that is selective for thorium or uranium. The thorium or uranium is at least partially removed from the first solution by binding the thorium or uranium to the ion exchange resin thereby forming a second solution. The second solution is combined with oxalic acid to precipitate uranium or thorium from the second solution to form a precipitate. The precipitate is separated from the second solution.

The present invention provides a target unit and a sublimation apparatus suitable for use in a method for producing Cu67 radioisotope suitable for use in medical applications. The apparatus comprises a sublimation tube with one open end. The sublimation tube contains an ingot comprising Zn68 and Cu67 in a ceramic capsule contacting a closed end the sublimation tube. A removable vacuum dome is sealable over the open end of the sublimation tube so that interior of the apparatus can be placed under vacuum.