Patent classifications
G21G1/00
TARGET CARRIER ASSEMBLY AND IRRADIATION SYSTEM
A target carrier assembly includes a housing, a target, and a collimator. The housing includes a collimator compartment and a target compartment divided by a vacuum window foil, the collimator being removably disposed within the collimator compartment, and the target being disposed within the target compartment. The collimator compartment is attached to a cyclotron beam line in the irradiation position, and the target compartment is in fluid communication with a cooling fluid supply line and a cooling fluid return line in the irradiation position. The target is cooled by the cooling fluid from the cooling fluid supply line. The collimator directs a particle beam from the cyclotron beam line to irradiate the target and includes a beam entry diameter and a beam exit diameter. The collimator is in thermal contact with the collimator compartment.
TARGET CARRIER ASSEMBLY AND IRRADIATION SYSTEM
A target carrier assembly includes a housing, a target, and a collimator. The housing includes a collimator compartment and a target compartment divided by a vacuum window foil, the collimator being removably disposed within the collimator compartment, and the target being disposed within the target compartment. The collimator compartment is attached to a cyclotron beam line in the irradiation position, and the target compartment is in fluid communication with a cooling fluid supply line and a cooling fluid return line in the irradiation position. The target is cooled by the cooling fluid from the cooling fluid supply line. The collimator directs a particle beam from the cyclotron beam line to irradiate the target and includes a beam entry diameter and a beam exit diameter. The collimator is in thermal contact with the collimator compartment.
Method for producing Ac-225 from Ra-226
The embodiments of the present disclosure provide a method for producing Ac-225 from Ra-226, comprising submitting Ra-226 to a photo-nuclear process, collecting an electrochemical precipitation of an Ac-225 on a cathode in a recipient, removing the cathode from the recipient after the electrochemical precipitation of the Ac-225, transferring the cathode to a hot cell environment, and extracting the Ac-225 from the cathode in the hot cell environment. The Ra-226 may comprise a liquid solution in the recipient, and submitting Ra-226 to the photo-nuclear process may comprise irradiating the Ra-226 to produce Ra-225. The Ra-225 may decay into Ac-225 upon irradiation of the Ra-226.
Methods of isolating radioactive mercury and uses thereof
Provided herein are methods of isolating and using radioactive mercury. In particular, provided herein are methods of isolating radioactive mercury including the use of a thiacrown ether, and using the isolated radioactive mercury in therapeutic and/or imaging applications.
Production of copper-67 from an enriched zinc-68 target
An apparatus including a heating element and a sublimation vessel disposed adjacent the heating element such that the heating element heats a portion thereof. A collection vessel is removably disposed within the sublimation vessel and is open on an end thereof. A crucible is configured to sealingly position a solid mixture against the collection vessel.
RADIOISOTOPE GENERATOR EARLY BREAKTHROUGH DETECTION
An infusion system can include a radioisotope generator that generates a radioactive eluate via an elution, an activity detector configured to measure an activity of the radioactive eluate generated by the radioisotope generator, and a controller. The controller can analyze a radioactivity profile of the radioactive eluate to determine a characteristic of the profile indicative of breakthrough. The controller may issue a user alert, cease elution, or perform yet other actions based on the analysis.
PURIFICATION PROCESS FOR THE PREPARATION OF NON-CARRIER ADDED COPPER-64
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.
Apparatus for Production of Lead 212 Isotope
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.
HIGH THROUGHPUT SURFACE ION SOURCE FOR SEPARATION OF RADIOACTIVE AND STABLE LANTHANIDE ISOTOPES
The present invention is directed to processes for ionizing one or more lanthanide isotopes, processes for separating lanthanide isotopes, various apparatus and systems useful for these processes, and compositions prepared from these processes.
Apparatus of producing nuclide using fluid target
The disclosure provide an apparatus for producing a nuclide by using a liquid target which can perform the nuclear reaction process and can discharge the radioactive gas such as Radon within the vial. As described above, an apparatus for producing a nuclide by using a liquid target according to the present disclosure can minimize quantitative loss of a reactant by performing the nuclear reaction process using a target of a liquefied state and reusing a liquefied target on which the nuclear reaction process has not been performed, and can improve safety by enabling the radioactive gas generated to be disposed.