423 results about "Radio isotopes" patented technology

The invention belongs to the field of medical radioactive isotope preparation, and particularly relates to a method for extracting lead-212 and bismuth-212 from a thorium-232 decay chain, a solution containing a thorium-232 decay chain substance passes through an anion exchange resin column, the solution containing the thorium-232 decay chain substance contains halide ions, and the anion exchange resin column is used for extracting the lead-212 and the bismuth-212 from the thorium-232 decay chain substance. The concentration of hydrogen ions in the solution containing the thorium-232 decay chain substance is greater than 0.01 mol / L, the lead-212 and the bismuth-212 are adsorbed by the anion exchange resin column, other nuclides directly penetrate through the anion exchange resin column and are not adsorbed, a leaching reagent is introduced to desorb the lead-212 and the bismuth-212 from the anion exchange resin column, and the lead-212 and the bismuth-212 are separated and extracted; the method can be used for simultaneously extracting lead-212 and bismuth-212, has the advantages of high extraction speed and high purity, and is not easy to cause organic pollution to products.

An infusion system may include a radioisotope generator that generates a radioactive eluate via elution, a beta detector, a gamma detector, and a controller. The beta detector and the gamma detector may be positioned to measure beta emissions and gamma emissions, respectively, emitted from the radioactive eluate. In some examples, the controller is configured to calibrate the infusion system using the gamma detector. For example, the controller may generate a radioactive eluate and measure the activity of the radioactive eluate using both the beta detector and the gamma detector. The high accuracy of the activity measured by the gamma detector may be used to calibrate the infusion system. In subsequent use, the infusion system calibrated using the gamma detector may adjust measurements made to monitor and / or control patient infusion procedures.

The present invention relates to ultrasound (US) mediated delivery of therapeutic agents, such as the delivery of a drug, gene, nanoparticle or radioisotope, using a bi-phasic microparticle system comprising gas microbubbles, emulsion microdroplets and clusters thereof. Thus, the present invention relates to a cluster composition and a pharmaceutical composition, and their use for delivery of therapeutic agents and as a contrast agent for ultrasound imaging. It further relates to methods for delivering such therapeutic agents and to the use of said compositions.

The present disclosure generally relates to materials, processes, generators, and / or systems, for generating radioisotope. The present disclosure also generally relates to ceramic materials comprising radioisotope suitable for use in a radioisotope generator. The present disclosure also generally relates to processes, generators and / or systems, for producing and capturing radioisotope. The present disclosure also generally relates to the preparation of radioisotope solutions for use in radiopharmacy and / or other clinical applications.

Main characteristic of the invention is the exploitation of the very large flux of high energy neutrons generated in a nuclear fusion tokamak with beam-driven plasma for the purpose of producing radioisotopes. It specifically relates to the deployment of precursor materials into the core of a nuclear fusion tokamak with beam-driven plasma for the purpose of exposing these materials to the neutron flux generated in the plasma by the process of nuclear fusion of Deuterium (D) and Tritium (T) to generate radioactive isotopes, so-called radioisotopes. The precursor materials contained in metallic capsules are incorporated into the blankets that surround the plasma.

The invention discloses an actinide purification method and device, and belongs to the technical field of medical radioactive isotope separation and purification. The method comprises the following steps: passing a thorium target solution containing actinide through a cation exchange column, and leaching with inorganic acid to obtain a first effluent containing Ac < 3 + >; enabling the first effluent containing the Ac < 3 + > to pass through a TK221 resin extraction column to obtain a second effluent containing the Ac < 3 + >; the second effluent containing Ac3 + passes through a TRU resin extraction column, and actinide is obtained. The TK221 resin also contains phosphine oxide and a small amount of long alkyl chain alcohol on the basis of diglycolamide, and shows better performance on purification of Ac < 3 + >. Meanwhile, the elution acidity in the TRU resin separation process is properly improved, and the outflow speed of Ac, La and Ce can be delayed, so that the effect of separating Ac from La and Ce is achieved, and the yield of 225Ac is improved while the concentration of metal impurities is reduced.

The disclosure relates to radiolabeled aromatic electrophile prosthetic groups, which can be used to prepare bioactive ligands containing PET, SPECT, alpha- or beta-emitting radioisotopes, and their use in treating and / or imaging cancer.

The present invention relates to the nanoparticles (NP) of the invention, compositions thereof and their use as therapeutic agents, in particular in the field of oncology and / or as imaging agents. The NPs consist of first nanoparticles of at least one high-Z metal oxide material, to which smaller second nanoparticles are covalently bonded at the surface of the first nanoparticles. The second nanoparticles consist of a) at least one noble metal or at least one metal oxide, metal sulfide, metal selenide or metal sulfide / selenide as a Fenton or Fenton-like reaction catalyst. The NPs of the invention produce a surprising therapeutic effect when exposed to ionizing radiation such as X-rays, gamma-rays, protons, neutrons, radioisotopes and / or electron beams. Therefore, these NPs can be used as radiosensitizers in the field of oncology. These nanoparticles can also be used as contrast agents.

Described herein are novel linkers for use with immunoconjugates to connect a targeting moiety to a radiochelator moiety without impairing the functionality of either. The linkers of the invention may provide a stable linkage in circulation, permit fast total body clearance including from organs such as the liver, high tumor uptake and high tumor-to-normal-organ radiation exposure (for example, in the liver and kidneys). The immunoconjugates can be used to deliver radioisotopes including alpha and beta emitters for the treatment of tumors or cancer.

Radiation shielding technologies for radioisotope battery-powered vehicles to protect computer systems and humans and increase the energy efficiency, mass efficiency, and duration capability of the vehicle during operation. A radioisotope power system includes a radioisotope power unit that emits a plurality of radiation particles. The radioisotope power system further includes a radiation shield configured to block a first radiation particle of the plurality of radiation particles. The radioisotope power system further includes a decoupling device configured to decouple the radiation shield from a vehicle. The radioisotope power unit can include one or more radioisotopes for power, propulsion, or both power and propulsion of the vehicle. The one or more radioisotopes can include an alpha emitting isotope, a beta emitting isotope, a gamma emitting isotope, or a combination thereof. The one or more radioisotopes can be for heat generation. The vehicle can be a spacecraft or an aircraft.

The invention discloses a combined analysis method for iodine-plutonium-uranium radioisotope in a coral sample, and belongs to the field of analytical chemistry technology and environmental geochemistry. The method comprises the following steps: infiltrating a coral sample, adding 125I and 242Pu tracers, uniformly mixing, and treating to obtain a pretreated sample solution; the contents of 127I and 238U are measured; adding a 127I carrier and a reducing agent into the pretreated sample solution, and performing extraction and back extraction under an acidic condition to respectively obtain a first water phase solution and a second water phase solution; carrying out precipitation reaction on the second water phase solution to obtain a precipitate, and preparing the precipitate into a target sample to measure the content of 129I; separating and purifying the first water phase solution to obtain a plutonium effluent, eluting to obtain a plutonium eluent, and measuring the contents of 239Pu and 240Pu; and purifying and eluting the plutonium effluent to obtain uranium eluent, and measuring the content of 236U. According to the method, iodine, plutonium and uranium are subjected to joint analysis by using one coral sample, so that the use amount of the coral sample is reduced.

The disclosure relates to double halogenated phenylalanine derivatives, which can be radiolabeled with PET or SPECT radioisotopes, and their use in treating and / or imaging cancer.

Targetry coupled separation refers to enhancing the production of a predetermined radiation product through the selection of a target (including selection of the target material and the material's physical structure) and separation chemistry in order to optimize the recovery of the predetermined radiation product. This disclosure describes systems and methods for creating (through irradiation) and removing one or more desired radioisotopes from a target and further describes systems and methods that allow the same target to undergo multiple irradiations and separation operations without damage to the target. In contrast with the prior art that requires complete dissolution or destruction of a target before recovery of any irradiation products, the repeated reuse of the same physical target allowed by targetry coupled separation represents a significant increase in efficiency and decrease in cost over the prior art.

A radioisotope target station, including a target housing. The target housing includes a target material, and a target backing material. The radioisotope target station includes a loader mechanism comprising at least one jaw configured to secure the target housing, a loading position comprising a magazine, wherein the magazine is configured to hold two or more target housings, an irradiation position comprising a beam, where the beam is configured to irradiate the target housing orthogonally, a cooling fluid source fluidly coupled to the loader mechanism, where the cooling fluid source is configured to cool the target housing as the target housing is irradiated, and an ejection position comprising an ejector and an ejection chute, where the ejector is configured to detach the target housing from the loader mechanism and the ejection chute is configured to receive the target housing when detached.

The invention relates to a specific PET molecular probe of a targeted KRASG12D mutant as well as a preparation method and application of the specific PET molecular probe. Pyridopyrimidine compounds and R5 are subjected to cooling reaction under the action of N, N-diisopropylethylamine to generate a compound 2; the compound 2 and (2-fluorotetrahydro-1H-pyrrolizine-7A (5H)-yl) methanol are subjected to a heating reaction under the action of N, N-diisopropylethylamine, and a compound 3 is generated; carrying out heating reaction on the compound 3 and biphenyl boronic acid pinacol ester under the action of N, N-diisopropylethylamine and tetrakis (triphenylphosphine) palladium to generate a compound 4; carrying out heating reaction on the compound 4 and 1, 2-bis (tolyloxy) alkane under the action of potassium carbonate to generate a compound 5; the compound 5, radioisotope < 18 > F and an anion complexing agent are subjected to a heating reaction under the action of potassium carbonate to generate the trisubstituted pyridopyrimidine < 18 > F labeled PET molecular probe. Compared with the prior art, the kit has a positioning diagnosis effect on KRASG12D mutant tumors, and image typing of mutant and non-mutant tumors and pathological evaluation after tumor treatment are realized at the same time.

Targetry coupled separation refers to enhancing the production of a predetermined radiation product through the selection of a target (including selection of the target material and the material's physical structure) and separation chemistry in order to optimize the recovery of the predetermined radiation product. This disclosure describes systems and methods for creating (through irradiation) and removing one or more desired radioisotopes from a target and further describes systems and methods that allow the same target to undergo multiple irradiations and separation operations without damage to the target. In contrast with the prior art that requires complete dissolution or destruction of a target before recovery of any irradiation products, the repeated reuse of the same physical target allowed by targetry coupled separation represents a significant increase in efficiency and decrease in cost over the prior art.

The present application relates to a kind of methods for separating actinium from irradiated thorium target, belong to medical radioisotope manufacturing technical field, solve the problem that thorium element and lanthanide element impurity content in final actinium product in prior art is higher.The present application discloses a kind of methods for separating actinium from irradiated thorium target, first, irradiated thorium target is dissolved, then using cation exchange resin column, UTEVA or TK200 resin extraction column, DGA resin extraction column, LN resin extraction column four-stage series separation purification process, obtain final actinium product.Actinium is efficiently and selectively recovered, and the thorium element and lanthanide element impurity content in final actinium product is significantly reduced.

The present disclosure generally relates to materials, processes, generators, and / or systems, for generating radioisotope. The present disclosure also generally relates to ceramic materials comprising radioisotope suitable for use in a radioisotope generator. The present disclosure also generally relates to processes, generators and / or systems, for producing and capturing radioisotope. The present disclosure also generally relates to the preparation of radioisotope solutions for use in radiopharmacy and / or other clinical applications.

The invention relates to the technical field of environmental pollutant detection, and discloses 14C and fluorescent molecule double-labeled polystyrene nanoparticles as well as a preparation method and application thereof, the polystyrene nanoparticles have the following structural formula, * C represents 14C, the range of m is 30-100, the range of n is 10-30, and m: n = (3-10): 1. The preparation method comprises the following steps: preparing a 14C-styrene monomer by using 14C-containing methyl triphenyl phosphine iodide as a raw material, and polymerizing the 14C-styrene monomer with N-3-butenyl-7-nitro-2, 1, 3-benzofuran-4-amine to obtain the polystyrene nanoparticles. The PS-NPs marked by the radioisotope 14C and the fluorescent molecule can be traced by means of the radioisotope, the trace amount is accurate, and the PS-NPs are irreplaceable, so that the micro-plastic can be subjected to fluorescence imaging, and the micro-plastic nano-particles can be visually and accurately positioned. # imgabs0 #

The invention provides a test method and equipment for characterizing etching sediment distribution, and the method comprises the steps: arranging a sampling cabin on the side wall of an etching chamber, and placing a sampling piece in the sampling cabin; introducing radioactive isotope labeled etching gas to carry out an etching process; and performing radioisotope imaging analysis on the sampling piece to obtain distribution data of the etching sediment. The radioactive isotope labeled sediments are collected through the sampling piece to obtain the distribution of the sediments in the etching chamber, so that the adjustment precision of etching process parameters is improved, and the device yield is improved; meanwhile, the representativeness of sediment distribution data is improved through the position distribution of the sampling bins; in addition, a sampling piece is placed in the sampling bin, so that the sampling piece effectively reflects the actual distribution condition of sediments on the side wall of the etching chamber, and meanwhile, operation and maintenance are convenient; finally, after the sampling piece is taken out, dry ice cleaning and radioactive substance detection are carried out in the etching chamber, and the influence of radioactive substance residues on the sediment distribution detection accuracy in the future and the damage to the etching chamber are avoided.

The present application belongs to a kind of medical radioisotope preparation field, specifically related to a kind of method for extracting lead-212 and bismuth-212 in thorium-232 decay chain, solution containing thorium-232 decay chain material is passed through anion exchange resin column, the solution containing thorium-232 decay chain material includes halogen ion, and the concentration of hydrogen ion in the solution containing thorium-232 decay chain material is greater than 0.01mol / L, lead-212 and bismuth-212 are absorbed by anion exchange resin column, and other nuclides directly pass through anion exchange resin column and are not absorbed, lead-212 and bismuth-212 are desorbed from anion exchange resin column by elution reagent, and lead-212 and bismuth-212 are separated and extracted;The present application can extract lead-212 and bismuth-212 simultaneously, and the extraction speed is fast, the purity is high, and the product is not easy to cause organic pollution.

The invention relates to the technical field of molecular probes, and particularly discloses a molecular probe of a targeted tyrosine kinase receptor as well as a preparation method and application of the molecular probe, the molecular probe comprises radioisotope, targeted polypeptide and a chelating group, the targeted polypeptide specifically targets the tyrosine kinase receptor, the chelating group is connected with the targeted polypeptide to form a targeted precursor, and the chelating group is connected with the targeted polypeptide to form the targeted precursor. The radioactive isotope labeled precursor forms a molecular probe, and the sequence of the targeted polypeptide is shown as any one of SEQ ID No.1-8. The targeting polypeptide has good targeting property on a tyrosine kinase receptor coded by an RET gene, can realize specific high uptake in a cell line of NEPC, has relatively good biological safety, can realize accurate imaging aiming at NEPC, and clearly and durably visualizes NEPC tumors in PET imaging; meanwhile, the molecular probe can effectively delay the growth capacity of NEPC, can provide a new treatment choice for NEPC patients, and has good clinical transformation potential.

A precursor compound and a radioligand for cancer diagnosis and treatment comprises a high-affinity ligand PL for a cancer- associated protein conjugated to a covalent warhead CW for strong or covalent binding to an amino acid sidechain of the cancer-associated protein and a chelator Ch for complexation of a radioisotope or a leaving group LR for substitution with a radioisotope, wherein the covalent warhead CW is configured for quasi-covalent ionic binding using a sulfonic acid group or for covalent binding using a sulfur fluoride exchange (SuFEx) group, a benzotriazole or N-methyl-N- arylmethanesulfonamide leaving group or a malolactone group for strain-release alkylation.

Targetry coupled separation refers to enhancing the production of a predetermined radiation product through the selection of a target (including selection of the target material and the material's physical structure) and separation chemistry in order to optimize the recovery of the predetermined radiation product. This disclosure describes systems and methods for creating (through irradiation) and removing one or more desired radioisotopes from a target and further describes systems and methods that allow the same target to undergo multiple irradiations and separation operations without damage to the target. In contrast with the prior art that requires complete dissolution or destruction of a target before recovery of any irradiation products, the repeated reuse of the same physical target allowed by targetry coupled separation represents a significant increase in efficiency and decrease in cost over the prior art.

The invention relates to the design, configuration and operation concept of a system, herein called radioisotope recovery system, to deploy and recover different precursor materials into and from the core of a nuclear fusion tokamak with beam-driven plasma for the purpose of exposing these materials to the neutron flux generated in the plasma by the process of nuclear fusion of D and T ions, which will cause the generation of radioactive isotopes (also called radioisotopes). Main characteristics of the invention are (i) a closed loop that circulates precursor materials into and out of a nuclear fusion tokamak with beam-driven plasma, (ii) the compliance of the system with the design and maintenance of a nuclear fusion tokamak with beam-driven plasma.

Liposomes encapsulating a radioisotope can be used in the treatment of cancers including, but not limited to, leptomeningeal metastases. In an embodiment, liposome encapsulating a radioisotope comprising (186Re) obisbemeda can be administered to a patient through an Ommaya reservoir. The therapies can include imaging the liposome encapsulating a radioisotopе concomitant or subsequent to administration. Longitudinal analysis of the presence of tumor cells and biomarkers can be used to inform treatment strategy.

The invention belongs to the technical field of radioactive metal isotope ion chromatographic separation, and discloses a medical radioactive isotope purification multichannel ion liquid chromatography system. The system comprises an automatic sample injection system, a parallel sampling and leaching channel, a parallel multi-column chromatographic structure, an online radiation dose monitoring module, a multi-channel tail end detection system, a recycling structure and a central control system. By adopting a full-automatic sample injection and multi-channel parallel chromatography structure, parallel separation, real-time radiation monitoring, multi-mode online detection and closed-loop recovery are realized, and the problems of insufficient nuclear purity, low separation efficiency, low target recovery rate and high radiation exposure of a traditional method are solved.

The present disclosure generally relates to materials, processes, generators, and / or systems, for generating radioisotope. The present disclosure also generally relates to ceramic materials comprising radioisotope suitable for use in a radioisotope generator. The present disclosure also generally relates to processes, generators and / or systems, for producing and capturing radioisotope. The present disclosure also generally relates to the preparation of radioisotope solutions for use in radiopharmacy and / or other clinical applications.

A system for the safe preparation and injection of a radioactive isotope of H2 15 O for use in positron emission tomography (PET). The invention also relates to a safety valve for controlling the flow rate of H2 15 O used in PET, the use of said safety valve, and a method for preparing and injecting H2 15 O.

The present application relates to a kind of neutron energy spectrum optimization method and system for improving reactor radioisotope production efficiency, method includes the following steps: initial population of genetic algorithm is randomly generated, these population individuals are all neutron energy spectrum divided into n energy group, the body average neutron energy spectrum in target piece when the neutron energy spectrum of each individual is calculated as irradiation hole incident spectrum, the radioisotope production under the body average neutron energy spectrum in target piece corresponding to each individual is calculated, the evolution of population is realized by the mutation and crossing operation of genetic algorithm, the above-mentioned process is repeatedly executed until iteration converges, obtains the neutron energy spectrum regulation scheme for realizing the maximization of radioisotope production.Compared with prior art, the present application efficiently realizes the accurate regulation of neutron energy spectrum in reactor, can provide technical support for the energy spectrum regulation process of radioisotope irradiation production in reactor.