Methods for purifying .sup.89Zr are provided, .sup.89Zr compositions are provided, isotope compositions are provided that can include: a radio isotope and a nanoparticle, and methods for radio labeling monoclonal antibodies are provided.

A radionuclide production method and system makes it possible to separate a target radionuclide generated by irradiation with a radioactive ray, and to reduce the generation of a radioactive waste along with the separation. The radionuclide production method includes irradiating, with a radioactive ray, a target material in which a starting material nuclide is present, to generate a radionuclide; and eluting the radionuclide into a liquid by bringing the target material into contact with the liquid. The radionuclide production system includes a target material having a starting material nuclide; an irradiation unit for the target material that generates a radionuclide; and an elution unit that elutes the radionuclide into a liquid by bringing the target material into contact with the liquid. For both the radionuclide production method and system, the target material is a porous body or a granular material through which the liquid is passable.

An elution generator including an elution column having a container defining an interior volume and a septum, a radiation shield having an upper shield portion defining a central recess and a coaxial flow needle extending downwardly into the central recess, and a lower shield portion having body portion defining a central recess, wherein the elution column is disposed in the central recess of the lower shield portion, the body portion of the lower shield portion is disposed in the central recess of the upper shield portion, and the coaxial flow needle extends downwardly through the septum into the internal volume of the elution column.

An initial introduction control part introduces an aqueous solution containing molybdenum 99 and technetium 99m, and an organic solvent being capable of dissolving the technetium 99m into an extraction tank. A micro-mixing control part micro-mixes the aqueous solution and the organic solvent by heating and stirring a mixed solution of the aqueous solution and the organic solvent introduced into the extraction tank with a heater, while applying ultrasonic to the mixed solution. A separation control part separates the mixed solution micro-mixed into two phases of aqueous solution and an organic solvent. A taking-out introduction control part passes the organic solvent separated into two phases through an adsorption column be capable of adsorbing molybdenum 99 and introduces the organic solvent into an evaporation elution tank. An evaporation control part evaporates the organic solvent and leaves residue by reducing pressure inside the evaporation elution tank and heating the organic solvent introduced into the evaporation elution tank with a heater, while applying ultrasonic to the organic solvent. An elution control part introduces physiological saline solution into the residue and elutes technetium 99m into the physiological saline solution from the residue.

This disclosure provides systems, methods, and apparatus related to the production of actinium-225. In one aspect, a target is irradiated with a beam of deuterons to generate a beam of neutrons. A radium-226 target is irradiated with the beam of neutrons to generate radium-225.

An irradiation target for the production of radioisotopes, comprising at least one plate defining a central opening and an elongated central member passing through the central opening of the at least one plate so that the at least one plate is retained thereon, wherein the at least one plate and the elongated central member are both formed of materials that produce molybdenum-99 (Mo-99) by way of neutron capture.

Provided is a process which allows uranium and molybdenum fluorides to be efficiently separated, said process comprising a step of providing a mixture containing MoF.sub.6 and UF.sub.6; a step of reducing the UF.sub.6 to UF.sub.5 in the gas phase or in a liquid phase; and a step of separating the UF.sub.5 and the MoF.sub.6 or a conversion product thereof which may be obtained by further converting the molybdenum fluoride to another molybdenum compound. In a further aspect, a process for the fluorination of metals or semimetals is provided.

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 purifying Ac from a mixture includes Ac and at least one element selected from Ra, Pb, Po, Bi and La. The method includes the steps of: (a) performing a first separation using a first extraction chromatographic column based on a first resin (either a diglycolamide resin or a dialkylphosphoric acid resin) and a first matrix solution; and (b) performing a second separation using a second extraction chromatographic column based on a second resin (respectively either a dialkylphosphoric acid resin or a diglycolamide resin).

Disclosed herein are methods preparing a purified, carrier-free 68Ga solution. Tire present disclosure also provides systems for preparing a purified, carrier-free 68Ga solution. The present disclosure also provides compositions comprising the purified, carrier-free 68Ga solutions disclosed herein. Also provided are methods of administering compositions of the present disclosure to a patient in need thereof, for example, for imaging a disease or disorder, such as cancer.