G21G1/00

Technetium 99m isolation system and technetium 99m isolation method

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.

SYSTEMS AND METHODS FOR PRODUCING ACTINIUM-225

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.

Aqueous assembly and control method

An aqueous assembly has a negative coefficient of reactivity with a magnitude. The aqueous assembly includes a vessel and an aqueous solution, with a fissile solute, supported in the vessel. A reactivity stabilizer is disposed within the aqueous solution to reduce the magnitude of the negative coefficient of reactivity of the aqueous assembly during operation of the aqueous assembly.

System, emanation generator, and process for production of high-purity therapeutic radioisotopes
11348702 · 2022-05-31 · ·

An isotope production system, emanation generator, and process are disclosed for production of high-purity radioisotopes. In one implementation example, high-purity Pb-212 and/or Bi-212 isotopes are produced suitable for therapeutic applications. In one embodiment the process includes transporting gaseous radon-220 from a radium-224 bearing generator which provides gas-phase separation of the Rn-220 from the Ra-224 in the generator. Subsequent decay of the captured Rn-220 accumulates high-purity Pb-212 and/or Bi-212 isotopes suitable for direct therapeutic applications. Other high-purity product isotopes may also be prepared.

PREPARATION OF METAL FLUORIDES AND SEPARATION PROCESSES

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.

System and Process for Purification of Astatine-211 From Target Materials
20220148751 · 2022-05-12 · ·

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.

PURIFICATION OF ACTINIUM
20220145423 · 2022-05-12 ·

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).

Method for extraction and purification of 68GA

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.

Apparatus for production of lead 212 isotope
11728062 · 2023-08-15 · ·

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.

Separation of Radiometals

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.