A method for producing a radionuclide comprises irradiating a target material with a linear accelerator to produce a radionuclide, dissolving the irradiated target material comprising the radionuclide, and separating the radionuclide from the irradiated target material. Additional methods are disclosed.

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.

The present disclosure relates in general to nuclear medicine and generators for the production of radiopharmaceuticals for medical use. In particular, present disclosure relates to a generator column that resists high heat such as depyrogenation and sterilization. This allows some steps of the preparation of the column to be performed in a non-sterile environment. This also allows the generator column to be reusable. The present disclosure further describes methods for the preparation of a generator where a parent radioisotope is charged on the column matrix before or after the matrix is loaded in the column.

The present invention relates to monolithic bodies, uses thereof and processes for the preparation thereof. Certain embodiments of the present invention relate to the use of a monolithic body in the preparation of a radioactive substance, for example a radiopharmaceutical, as part of a microfluidic flow system and a process for the preparation of such a monolithic body.

The present invention relates to assemblies and method for obtaining a container comprising .sup.212Pb on the walls obtained from a .sup.212Pb precursor isotope source. The invention provides an improved system and method for producing .sup.212Pb high purity without the need for processing, with high yields, and which safely and efficiently can be transported to the locations where it is to be used.

Embodiments of the present invention provide for assessing the state of an .sup.82Rb elution system. In certain embodiments, a system begins an assessment that comprises an elution, and a metric may be measured. This metric may be a concentration of .sup.82Rb, .sup.82Sr, or .sup.85Sr in a fluid that is eluted from the generator, the volume of the fluid that is eluted from the generator, or the pressure of the fluid flowing through at least one portion of the system. If the assessment is completed, an output may be generated on a user interface that recommends a course of action, or no course of action, based on a result of the assessment. Should the assessment not complete successfully because it is interrupted, a .sup.82Sr/.sup.82Rb generator of the system may be halted so as to prevent a user from performing an end-run around these quality control mechanisms of the .sup.82Rb elution system.

The present disclosure relates in general to nuclear medicine and generators for the production of radiopharmaceuticals for medical use. In particular, present disclosure relates to a generator column that resists high heat such as depyrogenation and sterilization. This allows some steps of the preparation of the column to be performed in a non-sterile environment. This also allows the generator column to be reusable. The present disclosure further describes methods for the preparation of a generator where a parent radioisotope is charged on the column matrix before or after the matrix is loaded in the column.

There is disclosed a method of generating non-ionizing radiation, non-ionizing .sup.4He atoms, or a combination of both, the method comprising: contacting graphene materials with a source of deuterium; and aging the graphene materials in the source of deuterium for a time sufficient to generate non-ionizing radiation, non-ionizing .sup.4 1-le atoms. In one embodiment, graphene materials may comprise carbon nanotubes, such as nitrogen doped single walled or multi-walled carbon nanotubes. Unlike an alpha particle, the non-ionizing .sup.4He atoms generated by the disclosed method are a low energy particles, such as one having an energy of less than 1 MeV, such as less than 100 keV. Other non-ionizing radiation that can be generated by the disclosed process include soft x-rays, phonons or energetic electrons within the carbon material, and visible light.

There is disclosed a method of generating non-ionizing radiation, non-ionizing .sup.4He atoms, or a combination of both, the method comprising: contacting graphene materials with a source of deuterium; and aging the graphene materials in the source of deuterium for a time sufficient to generate non-ionizing radiation, non-ionizing .sup.4 1-le atoms. In one embodiment, graphene materials may comprise carbon nanotubes, such as nitrogen doped single walled or multi-walled carbon nanotubes. Unlike an alpha particle, the non-ionizing .sup.4He atoms generated by the disclosed method are a low energy particles, such as one having an energy of less than 1 MeV, such as less than 100 keV. Other non-ionizing radiation that can be generated by the disclosed process include soft x-rays, phonons or energetic electrons within the carbon material, and visible light.

A method for producing Pb-212 and Ac-225 isotopes is disclosed. The method comprises irradiating a Ra-226 containing target with charged particles and/or photons for producing at least Ac-225 isotopes and Ac-224 isotopes. The method further comprises after a cooling time, applying chromatography for separating actinium from the remaining fraction containing radium. The method also comprises, after a first further waiting time, applying extraction chromatography using a resin having an 18-crown-6 ether or an equivalent of an 18-crown-6 ether, as extractant in HNO3 and/or HCl for separating Pb from the remaining fraction containing radium.