154results about "Isotope delivery systems" patented technology

A biomarker generator system for producing approximately one (1) unit dose of a biomarker. The biomarker generator system includes a small, low-power particle accelerator (“micro-accelerator”) and a radiochemical synthesis subsystem having at least one microreactor and / or microfluidic chip. The micro-accelerator is provided for producing approximately one (1) unit dose of a radioactive substance, such as a substance that emits positrons. The radiochemical synthesis subsystem is provided for receiving the radioactive substance, for receiving at least one reagent, and for synthesizing the approximately one (1) unit dose of a biomarker.

Systems and methods are disclosed for producing customized, predictable and reproducible supplies of radioisotopes using, for example, a reactor housing that is fabricated from a radioactive shielding material and has both an internal volume and a surface that comprises an entry port and an exit port, a chromatographic column that is positioned within said internal volume such that a first end of said column is in fluid communication with said entry port and a second end of said column is in fluid communication with said exit port, and a changeable filter module that is disposed external to said reactor housing and in fluid communication with said exit port.

A combinatorial heterogeneous-homogeneous reactor configuration in which an array or groups of homogeneous fuel assemblies are interlinked together in a heterogeneous lattice. The present invention removes the limitation of a homogeneous reactor by providing a reactor concept that utilizes the inherent advantages of homogeneous fuel elements but in a heterogeneous fuel lattice arrangement that limits the power density of any one homogeneous fuel element and yet forms a reactor arrangement that is capable of producing any product demand of interest. The present invention provides a method for producing medical isotopes by the use of a modular reactor core comprised of homogeneous fuel assemblies arranged in a regular rectangular or triangular pitch lattice. The aqueous fuel solution is contained within individual fuel assemblies that are right circular cylinders clad in corrosion-resistant alloys such as stainless steel, zircalloy, zircalloy alloys, or other metal alloys that are resistant to corrosive fissile environments but preserve neutron economy. The fuel assemblies are supported below by a core plate that is tied directly to the lower reactor support structure. The bottom of each assembly opens into a common plenum area which provides a hydrodynamic communication / coupling path between the individual assemblies in the lattice. The fuel assemblies are supported above by an upper plate that is welded to each assembly tube. The top of each assembly opens to a common upper plenum which provides a means of thermodynamic pressure equalization among the four assemblies in the reactor core lattice.

Example embodiments are directed to methods of producing desired isotopes in commercial nuclear reactors and associated apparatuses using instrumentation tubes conventionally found in nuclear reactor vessels to expose irradiation targets to neutron flux found in the operating nuclear reactor. Example embodiments include assemblies for retention and producing radioisotopes in nuclear reactors and instrumentation tubes thereof. Example embodiments include one or more retention assemblies that contain one or more irradiation targets and are useable with example delivery systems that permit delivery of irradiation targets. Example embodiments may be sized, shaped, fabricated, and otherwise configured to successfully move through example delivery systems and conventional instrumentation tubes while containing irradiation targets and desired isotopes produced therefrom.

A system and method for monitoring progress of a radiopharmaceutical injection procedure includes: measuring and monitoring radiopharmaceutical activity of a radiopharmaceutical remaining in at least a portion of a disposable administration set used with a radiopharmaceutical fluid delivery system; and displaying the radiopharmaceutical activity remaining in at least the portion of the disposable administration set to an operator.

A system and method for employing the in-core movable detectors of a commercial nuclear powered electric generating facility to transmute a user-specified target material into a desired isotope. The process is conducted remotely resulting in a shielded end product available for shipment for further processing.

A saline water cartridge for radiopharmaceuticals injection includes a casing in which a primary passage extends from an outlet of a saline water reservoir to a radiopharmaceuticals inlet port of the cartridge and a secondary passage extends from an opening defined in the primary passage to a radiopharmaceuticals outlet port where a patient injection device is connected to supply the radiopharmaceuticals to the patient. A first one-way membrane valve is arranged in the opening of the primary passage to allow the radiopharmaceuticals injected into the primary passage from a radiopharmaceuticals carrying syringe to flow to the outlet port, while preventing reverse flow. A second one-way membrane valve is arranged in the outlet of the saline water reservoir to allow saline water to replenish into the primary passage while preventing reverse flow.

A low-volume biomarker generator for producing ultra-short lived radiopharmaceuticals. The low-volume biomarker generator system includes a low-power cyclotron and a radiochemical synthesis system. The cyclotron of the low-volume biomarker generator is optimized for producing radioisotopes useful in synthesizing radiopharmaceuticals in small quantities down to approximately one (1) unit dose. The cyclotron incorporates permanent magnets in place of electromagnets and / or an improved rf system to reduce the size, power requirements, and weight of the cyclotron. The radiochemical synthesis system of the low-volume biomarker is a small volume system optimized for synthesizing the radiopharmaceutical in small quantities of approximately one (1) unit dose.

Described herein are methods and devices for infusion of a radioactive compound, such as yttrium-90 radiolabeled somatostatin peptide or analog. A radiation shield defining a shielded cavity suitable for storing a radioactive substance includes a first aperture providing external access to the shielded cavity and a second aperture suitable for transferring a dosage vial into and out of the shielded cavity. A removable shielded plug and panel are adapted to shield respective apertures of the radiation shield. At least one dose of a radiolabeled compound stored in a vial in the radiation shield is delivered through a fluid communication channel at a rate of about 500 mL / hour. The fluid communication channel is washed after delivery, such that the process substantially reduces radiation exposure during infusion of the radiolabeled compound into a patient.

A multicolumn selectivity inversion generator separation method has been developed in which actinium ions, a desired daughter radionuclide, are selectively extracted from a solution of the thorium parent and daughter radionuclides by a primary separation column, stripped, and passed through a second guard column that retains any parent or other daughter interferents, while the desired daughter actinium ions and radium ions elute. This separation method minimizes the effects of radiation damage to the separation material and permits the reliable production of radionuclides of high chemical and radionuclidic purity for use in diagnostic or therapeutic nuclear medicine.

Example embodiments are directed to methods of producing desired isotopes in commercial nuclear reactors and associated apparatuses using instrumentation tubes conventionally found in nuclear reactor vessels to expose irradiation targets to neutron flux found in the operating nuclear reactor. Example embodiments include irradiation targets for producing radioisotopes in nuclear reactors and instrumentation tubes thereof. Example embodiments include one or more irradiation targets useable with example delivery systems that permit delivery into instrumentation tubes. Example embodiments may be sized, shaped, fabricated, and otherwise configured to successfully move through example delivery systems and conventional instrumentation tubes while producing desired isotopes.

The present invention relates to an apparatus for synthesizing F-18 labeled radioactive pharmaceutical. The apparatus for synthesizing F-18 labeled radioactive pharmaceutical includes an F-18 radioactive isotope supplier, a reagent supplier, a polymer precursor cartridge, a first heating unit, a polymer compound cartridge, a synthesizing container, a second heating unit, a water liquid container, a transmitting gas supplier, a cleansing liquid supplier, a connection tube, a plurality of control valves, and a controller.

An automated dispenser for radiopharmaceuticals is mainly for a platform to have a moving mechanism being able to move three-dimensionally back and forth, a syringe holder and a bottle holder. The syringe holder is for holding a plural number of syringes. The bottle holder has a reverse drug bottle. The moving mechanism has a syringe clamp rotatable around a horizontal axis and a syringe driving mechanism. The syringe clamp is activated to hold a syringe and move it to where the syringe needle is inserted to the drug bottle. The syringe driving mechanism and the syringe clamp are simultaneously associated with the syringe for drug-withdrawing action.

Components and systems for a PET radiopharmacy include a transport shield for a radioisotope cartridge, a cassette for dispensing from a transport shield, a cassette synthesis platform for a cassette, and a synthesizer shield.

Disclosed herein are embodiments of a radiation shielding lid of a radiation shielding container (e.g., auxiliary radiation shield) designed to house a radioisotope generator assembly.

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.

Target assembly for an isotope production system. The target assembly includes a target body having a production chamber and a beam cavity that is adjacent to the production chamber. The production chamber is configured to hold a target liquid. The beam cavity opens to an exterior of the target body and is configured to receive a particle beam that is incident on the production chamber. The target assembly also includes a vibrating device that is secured to the target body. The vibrating device is configured to cause vibrations that are experienced within the production chamber.

A multicolumn selectivity inversion generator separation method has been developed in which a desired daughter radionuclide is selectively extracted from a solution of the parent and daughter radionuclides by a primary separation column, stripped, and passed through a second guard column that retains any parent or other daughter impurities, while the desired daughter elutes. This separation method minimizes the effects of radiation damage to the separation material and permits the reliable production of radionuclides of high chemical and radionuclidic purity for use in diagnostic or therapeutic nuclear medicine.

The present invention provides a system for dispensing radiopharmaceuticals and measuring a radiation dosage thereof. In the system, the operation of dispensing a predetermined dose of radiopharmaceuticals from a vial (21) to an syringe (31) and the operation of measuring a radiation dosage of the radiopharmaceuticals dispensed to the syringe can be sequentially conducted without a risk of radiation leaking. Therefore, the system can markedly reduce the frequency of radiation exposure and the radiation exposure dose. Furthermore, when the syringe is moved downwards from a radiopharmaceutical dispensing apparatus (101) into a radiation dosage measuring apparatus (141) to measure a radiation dosage, the filling opening of the vial is displaced from a position aligned with the syringe, thus preventing radiopharmaceuticals remaining in the vial from affecting the measurement of the radiation dosage of the syringe.

Disclosed herein are an automated simultaneous separation system for radionuclides in multiple samples and a method for automatically separating uranium (U) using the same, which can automatically and simultaneously separate multiple samples. The automated simultaneous separation system includes: a solution distributor(30) for distributing a separation solution in seven directions; independent columns (80) of the same number as that of the samples, the columns (80) containing resin for chemical separation; a 8-channel tubing pump (60) for separately injecting the samples into the columns (80); first and second 3-way solenoid valves (50, 90) mounted at the front end and the rear end of the columns (80), and a digital pump speed controller (70) for freely controlling injection speed of the samples and solutions according to separation steps.

A multicolumn selectivity inversion generator has been developed in which bismuth-213 is selectively extracted from an HCl solution of the actinium-225 parent (and its radiogenic descendents) by a primary separation column containing a separation medium containing a neutral oxygenated organophosphorus extractant. After rinsing with dilute HCl, the bismuth-213 is stripped with a buffered NaCl solution. The stripped solution is passed through a cation-exchange resin guard column that retains the actinium-225 and radium-225 contaminants while the bismuth-213 elutes. This generator method minimizes the unpredictable effects of radiation damage to the support material and permits the reliable production of bismuth-213 of high chemical and radionuclidic purity.