An equatorial anthropic radiation source and a method of making an equatorial anthropic radiation source are described. The radiation source is useful in diagnostic imaging applications in healthcare or other industries (e.g. computerized three-dimensional segmental imaging; Crompton scattering imaging techniques; radiation detector check and calibration, in particular CdZnTe detectors commonly used in medical imaging).

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 process for minimizing waste and maximizing utilization of uranium involves recovering uranium from an irradiated solid target after separating the medical isotope product, molybdenum-99, produced from the irradiated target. The process includes irradiating a solid target comprising uranium to produce fission products comprising molybdenum-99, and thereafter dissolving the target and conditioning the solution to prepare an aqueous nitric acid solution containing irradiated uranium. The acidic solution is then contacted with a solid sorbent whereby molybdenum-99 remains adsorbed to the sorbent for subsequent recovery. The uranium passes through the sorbent. The concentrations of acid and uranium are then adjusted to concentrations suitable for crystallization of uranyl nitrate hydrates. After inducing the crystallization, the uranyl nitrate hydrates are separated from a supernatant. The process results in the purification of uranyl nitrate hydrates from fission products and other contaminants. The uranium is therefore available for reuse, storage, or disposal.

A method of producing enriched .sup.47Sc comprises irradiating a V structure comprising .sup.51V with at least one incident photon beam having an endpoint energy within a range of from about 14 MeV to about 44 MeV to convert at least some of the .sup.51V to .sup.47Sc and form a .sup.47Sc-containing structure. The .sup.47Sc of the .sup.47Sc-containing structure is separated from additional components of the .sup.47Sc-containing structure using a chromatography process. Systems and apparatuses for producing enriched .sup.47Sc are also described.

The present disclosure is directed to a nuclear thermionic avalanche cell (NTAC) systems and related methods of generating energy comprising a radioisotope core, a plurality of thin-layered radioisotope sources configured to emit high energy beta particles and high energy photons, and a plurality of NTAC layers integrated with the radioisotope core and the radioisotope sources, wherein the plurality of NTAC layers are configured to receive the beta particles and the photons from the radioisotope core and sources, and by the received beta particles and photons, free up electrons in an avalanche process from deep and intra bands of an atom to output a high density avalanche cell thermal energy through a photo-ionic or thermionic process of the freed up electrons.

A method for producing lead-212 of very high radiological purity from an aqueous solution comprising thorium-228 and daughters thereof. Manufacture of radiopharmaceuticals based on lead-212, which are useful in nuclear medicine and, in particular, in targeted alpha radiation therapy for the treatment of cancers.

The present invention relates to a column chromatographic method of manufacturing non-carrier-added high-purity .sup.177Lu compounds for medicinal purposes. In the method in accordance with the invention a cation exchanger and a suitable chelating agent are used. With the method in accordance with the invention it is possible for the first time to provide non-carrier-added high-purity .sup.177Lu compounds in milligram amounts for pharmaceutical-medicinal purposes from .sup.176Yb compounds irradiated with thermal neutrons, the radionuclides .sup.177Lu and .sup.176Yb being present in an approximate mass ratio of 1:10.sup.2 to 1:10.sup.10 for purification.

An equatorial anthropic radiation source and a method of making an equatorial anthropic radiation source are described. The radiation source is useful in diagnostic imaging applications in healthcare or other industries (e.g. computerized three-dimensional segmental imaging; Crompton scattering imaging techniques; radiation detector check and calibration, in particular CdZnTe detectors commonly used in medical imaging).

The present disclosure relates to systems and methods for producing tailored solutions or medicaments containing radioactive isotopes (e.g., alpha particle emitting radioactive isotopes). The solutions may be produced by appropriate aging and separation steps. Therapeutically effective amounts of Ac-225 and/or Bi-213 may thus be obtained.

A nuclear fuel, the nuclear fuel comprising uranium aluminide grains, wherein the uranium aluminide grain properties are selected for good isotope extraction after irradiation and chemical digestion.