34 results about "Actinium" patented technology

The invention relates to a closed circulation 226Ra solution target system for producing 225Ac. The closed circulation 226Ra solution target system comprises a solution type 226Ra target, an isotope target bin, a valve, a 226Ra solution circulation structure, a radium actinide separation structure, a radium lead separation structure, a photon detection system I, a photon detection system II, a heat exchange system, a pressure reduction radon evaporator and a radon treatment system, and the solution type 226Ra target comprises a solution circulation pipeline and a radium-containing solution. The radium-containing solution is contained in the closed solution circulating pipeline; the solution circulating pipeline comprises a main loop pipeline and two branch pipelines; the photon detection system I, the 226Ra solution circulation structure, the pressure reduction radon evaporator, the heat exchange system, the valve and the photon detection system II are sequentially arranged on the main loop pipeline; and the radium actinide separation structure and the radium lead separation structure are respectively arranged on the two branch pipelines. The system can improve the preparation efficiency and yield of 225Ac.

The present invention relates to a production 225 Closed cycle of Ac 226 Ra solution target system. The closed cycle 226 Ra solution target system includes solution type 226 Ra target, isotope target chamber, valve, 226 Ra solution circulation structure, radium-actinium separation structure, radium-lead separation structure, photon detection system I, photon detection system II, heat exchange system, vacuum radon evaporator and radon treatment system, among which, solution type 226 The Ra target includes a solution circulation pipeline and a radium-containing solution, and the radium-containing solution is contained in a closed solution circulation pipeline; the solution circulation pipeline includes a main loop pipeline and two branch pipelines; the photon detection system I, 226 The Ra solution circulation structure, vacuum radon evaporator, heat exchange system, valve and photon detection system II are sequentially arranged on the main loop pipeline; the radium-actinium separation structure and the radium-lead separation structure are respectively arranged on the two branch pipelines. 225 Preparation efficiency and yield of Ac.

Disclosed herein are methods and systems for the use of extraction chromatography resins to concentrate Ac from dilute solutions that may contain Th isotopes and / or other isotopes, such as Ra. As disclosed herein, at least some extraction chromatography resins strongly retain trivalent actinides between 4 and 6 M HNO3 that can be recovered in good yields with small volumes of dilute acids. These small volumes of acid eluents result in significant concentration of the solution of the trivalent / certain tetravalent ions, such that they can be further processed without requiring lengthy evaporation steps that are utilized in standard Ac concentration methods.

The present disclosure provides a process for the separation and purification of radium and actinium from acidic solution using composite adsorbents. The process includes preparing polyoxometalates (POMs)-based mesoporous composite metal-infused resins using phosphate recovered from waste buffer solution. The resins are prepared using a modified sol-gel technique to form inorganic composite metal-oxide clusters. Embodiments of the resins include silica-coated composite metal oxide particles, including antimony-vanadium oxide particles, and tungsten-doped mesoporous titanium oxide particles. The resins have differing adsorption affinities for actinium, radium, and other metal ions and may thus be utilized for selectively separating radium and actinium from irradiated thorium targets.

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.

Techniques are described for producing actinium-225 by arranging a converter material at least partially around a target material, where the target material includes radium-226. The converter material comprises a compound of lithium and hydrogen at least partially enriched with lithium-6 and deuterium, and is configured to convert thermal neutrons to fast neutrons, which are then incident on the radium-226. If the fast neutrons have a kinetic energy of at least 6.4 MeV, they will initiate a (n,2n) reaction that converts radium-226 into radium-225, which then decays into actinium-225. The process can desirably be performed within an environment rich in thermal neutrons, such as within a fission reactor.

A method is provided of continuous manufacturing of Actinium-225 from a radium generator by repeating chemical purification is provided.

This invention discloses an electroplating bath for producing medical isotopes using an accelerator, belonging to the technical field of accelerator-produced medical isotope actinium-225. In this electroplating bath, a cavity penetrating the bottom of the bath body is provided within the bath body. A pressing plate includes a front plate and a rear plate connected in a front-to-back direction. The front plate and the rear plate are detachably connected to the bottom of the electroplating bath body via front screws and rear screws distributed on opposite sides of the cavity, respectively, so that a target covering the bottom of the cavity is clamped between the bottom of the electroplating bath body and the pressing plate. A sealing ring surrounds the bottom periphery of the cavity and is sealingly disposed between the bottom of the electroplating bath body and the target. This invention enables rapid installation and removal of the target, and has the advantages of convenient maintenance, reliable sealing, and simple structure.

The present disclosure provides various methods, systems, and devices for producing actinium-225 (Ac-225). In one aspect of the disclosure, a method for producing Ac-225 includes inserting an irradiation target assembly into a commercial nuclear reactor. The irradiation target assembly comprises a radium-226 (Ra-226) material. The method further includes producing electricity using the commercial nuclear reactor by generating a neutron flux in the commercial nuclear reactor. The method further includes irradiating the Ra-226 material with the neutron flux generated in the in the commercial nuclear reactor to produce a radium-225 (Ra-225) material. The Ra-225 material decays to produce an Ac-225 material.

The application belongs to the field of analytical chemistry detection, and particularly relates to a method for detecting radiochemical purity of an actinium 225 Ac] conjugate. The method adopts high performance liquid chromatography combined with a gamma counter, a mobile phase includes mobile phase A and mobile phase B, the mobile phase A is a mixed solution of buffer salt and cationic pair reagent, and the mobile phase B is acetonitrile. 225 The detection method can accurately detect the radiochemical purity of the actinium 225 Ac] conjugate, is stable and reliable, has high sensitivity, and is of great significance for quality control and research of the actinium [Ac] conjugate product.

Techniques are described for producing radium-225 from a sample containing radium- 226, and milking the sample for actinium- 225, which results in a higher yield of actinium-225 for a given sample in a given period of time compared with conventional approaches. In particular, returning the sample to the reactor while there is still a significant amount of radium-225 in the sample can, over time, produce more actinium- 225 than the conventional approach of milking the sample until the vast majority of radium-225 has decayed into actinium-225.

The present method entails separating thorium by anion exchange to obtain a solution of a mixture of radium and actinium radionuclides, desorbing the thorium from the anion-exchange resin, separating the actinium and radium by cation exchange, and purifying the actinium of iron salt impurities and organic impurities. The thorium is desorbed using a solution containing a mixture of ammonium acetate and acetic acid. The actinium is purified of iron salts and organic impurities in a column containing two sorbents: a bottom layer comprised of a hydrophilic macroporous resin based on a polymethyl methacrylic acid ether; and a top layer comprised of a sorbent based on di(2-ethylhexyl)phosphoric acid applied to an inert carrier. The total concentration of ammonium acetate and acetic acid used in the desorption of thorium lies in a range of from 0.5 to 4.0 mol / L, and the concentration of hydrogen ions lies in a pH range of from 3.5 to 5.0. For added purification, the column is washed with a solution of hydrochloric acid having a concentration in a range of from 0.015 to 0.025 mol / L. The actinium is eluted using a solution of hydrochloric acid. The method makes it possible to isolate radionuclidically and chemically pure actinium-225 from a mixture containing radium-224, radium-225, thorium-228 and thorium-229 radionuclides.

The present application relates to an apparatus for manufacturing a material containing radium-225 from a material containing radium-226, by which apparatus a starting material containing radium-226 is subjected to neutron irradiation from a nuclear reactor to cause 226 Ra to be converted into radium-225, thereby providing a material containing radium-225, characterized in that the neutron irradiation of the starting material containing radium-226 is carried out in a moderated nuclear reactor; and the starting material containing radium-226 is shielded with a thermal neutron absorption shield.

Methods of determining actinium-225 in a human urine sample can be used to establish the effective dose received by persons working with or otherwise exposed to this isotope. The human urine sample can be prepared to produce a pre-concentrated sample, which can include co-precipitating Ac and separating a first precipitate. At least some organic matter can be broken down in the pre-concentrated sample to produce a decomposed sample, which can include adding an oxidative agent to the pre-concentrated sample. The decomposed sample can be purified to produce a measurement sample, which can include passing the decomposed sample through a purification media and eluting actinium from the purification media.

A method of producing actinide-225 from proton spallation of a thorium target via a radium generator. The method comprises dissolving a thorium target in a thorium solution, evaporating the thorium solution to obtain a dried thorium salt, reconstructing the dried thorium salt in sulfuric acid to form a neutral thorium species, passing the neutral thorium species through a cation exchange chromatography column to remove bulk thorium, performing extraction chromatography in a mixed resin bed to elute radium, and separating the radium from the thorium species. The radium-containing eluent is evaporated, dried radium is reconstructed, and extraction chromatography is performed to elute the purified radium fraction, thereby constructing the radium generator.

A method for producing Pb-212 and Ac-225 isotopes includes irradiating a Ra-226 containing target with charged particles and producing an irradiated target having at least Ac-225 isotope particles. Following irradiation and a cooling period, actinium isotopes are separated from a residual radium-containing fraction using chromatography. Subsequently, after an additional waiting period, lead isotopes are separated from the remaining radium fraction through extraction chromatography. The extraction process employs a resin containing an 18-crown-6 ether or an equivalent in a nitric acid (HNO3) and / or hydrochloric acid (HCl) medium to isolate Pb-212 and Ac-225 isotope particles.

A method for determination of Actinium-227 (Ac-227) via indirectly produced Ra-225 / Ac-225 parent / daughter. The determination of Ac-227 or its decay daughters can be used as a “pre-release” quality control test for total Ac-227 content.

Disclosed herein are methods and systems for the use of extraction chromatography resins to concentrate Ac from dilute solutions that may contain Th isotopes and / or other isotopes, such as Ra. As disclosed herein, at least some extraction chromatography resins strongly retain trivalent actinides between 4 and 6 M HNO3 that can be recovered in good yields with small volumes of dilute acids. These small volumes of acid eluents result in significant concentration of the solution of the trivalent / certain tetravalent ions, such that they can be further processed without requiring lengthy evaporation steps that are utilized in standard Ac concentration methods.

Disclosed herein are methods and systems for the use of extraction chromatography resins to concentrate Ac from dilute solutions that may contain Th isotopes and / or other isotopes, such as Ra. As disclosed herein, at least some extraction chromatography resins strongly retain trivalent actinides between 4 and 6 M HNO3 that can be recovered in good yields with small volumes of dilute acids. These small volumes of acid eluents result in significant concentration of the solution of the trivalent / certain tetravalent ions, such that they can be further processed without requiring lengthy evaporation steps that are utilized in standard Ac concentration methods.

Liquid is irradiated in irradiation device (2) by protons, deuterium nuclei or gamma rays. 226 The radium target, and the resulting product extracted from the irradiated liquid target solution in the first extraction device (6). 225 Origin of A 226 Radium production 225 Actinium. Then, after another irradiation, it was removed. 225 Actinium liquid target solution for further production 225 Actinium. The liquid target solution is preferably circulated through the irradiation device in a closed loop (4) and through the first extraction device (6) in another closed loop (7). The advantage of this method is that the irradiated target solution does not require drying and redissolving to separate radium from the produced actinium, and no further drying and redissolving steps are needed to regenerate the liquid target from the separated radium. Therefore, radium targets can be recovered more efficiently and safely, especially considering the effects of... 226 Radon gas is continuously produced by the decay of radium.

The invention relates to the field of nuclear technology, and more particularly to technology for producing radioactive isotopes for medicinal purposes, especially actinium-225, as well as other radionuclides, formed during the charged-particle (proton) irradiation of thorium in an accelerator. A key issue for achieving a high yield of radionuclides during proton irradiation of a target is that of manufacturing the target from sufficiently thick metallic thorium enclosed in a hermetic metallic niobium casing which is resistant at high temperature to chemical and radiation damage. Effective water cooling during irradiation is achieved by assuring good contact of a niobium foil (proton beam entrance and exit windows) with the thorium, as well as with other niobium parts of the casing. For this purpose, during production of the target, diffusion welding is carried out at a temperature of 1250-1430°С and a pressure of 30-150 kg / cm2 on the surface area of the target, wherein a hollow channel is formed in advance in the niobium body of the target to compensate for greater expansion of the thorium during welding. The target may be additionally coated from the outside with a protective layer of from 40 to 100 μm of another metal resistant to water during irradiation.

A method for measuring actinium-227 (Ac-227) via indirectly generated Ra-225 / Ac-225 parent / daughter nuclides. Measurement of Ac-227 or its decay products can be used as a "pre-release" quality control test for total Ac-227 content.

In one illustrative embodiment, a target insert for the production of Ac-225 in a particle accelerator is disclosed which may include a metal body comprising a central flat area deposition of Ra-226 or any means of depositing Ra226 on target body, a channel surrounding the perimeter of the central flat area and a hollow section opposite the central flat area. The target insert also includes an area of Ra-226 disposed on the central flat area and a protective layer disposed atop the area of Ra-226 and conforming to the metal target such that the protective layer is also disposed onto the channel surrounding the perimeter of the central flat area. A crimp ring is disposed on top of the protective layer in the channel surrounding the perimeter of the central flat area, wherein the crimp ring has been compressed to fill the channel and seal the protective layer to the metal body.

Methods and apparatus for production of isotopes are disclosed, such as isotopes for use in nuclear medicine. Isotopes so produced include Actinium-225, Lead-212, Terbium-161, Gold-199, Scandium-47, Copper-64, Copper-67, Bromine- 77, and / or Yttrium-90. Optionally, a target composition comprising a target isotope is irradiated with neutron radiation, wherein the neutron radiation comprises at least 50% neutrons generated by deuterium-tritium fusion, and optionally no more than 40% neutrons generated by deuterium-deuterium fusion, such as deuterium-tritium fusion generated by lattice confinement fusion in a nuclear fusion reactor. Product isotopes are produced via a nuclear reaction, such as a nuclear transmutation reaction.

The invention belongs to the field of analytical chemistry detection, and particularly relates to a method for detecting radiochemical purity of actinide [225Ac] conjugates. According to the method, high performance liquid chromatography is adopted to be connected with a gamma counter in series, a mobile phase comprises a mobile phase A and a mobile phase B, the mobile phase A is a mixed solution of buffer salt and a cation pair reagent, and the mobile phase B is acetonitrile. The detection method can accurately detect the radiochemical purity of the 225Ac conjugate, is stable, reliable and high in sensitivity, and has important significance on quality control and research of actinide [225Ac] conjugate products.

Techniques are described for producing actinium-225 by arranging a converter material at least partially around a target material, where the target material includes radium-226. The converter material comprises a compound of lithium and hydrogen at least partially enriched with lithium-6 and deuterium, and is configured to convert thermal neutrons to fast neutrons, which are then incident on the radium-226. If the fast neutrons have a kinetic energy of at least 6.4MeV, they will initiate a (n,2n) reaction that converts radium-226 into radium -225, which then decays into actinium-225. The process can desirably be performed within an environment rich in thermal neutrons, such as within a fission reactor.

A method is provided of continuous manufacturing of Actinium-225 from a radium generator by repeating chemical purification is provided.

The invention relates to a method for determining actinide 227 (Ac-227) by means of an indirectly produced Ra-225 / Ac-225 parent / daughter. Assay of Ac-227 or decay daughters thereof may be used as a "pre-release" quality control test for total Ac-227 content. The method includes extracting actinide isotopes from purified Ra-225 to produce a feedstock A. The raw material A is stood to allow the Ac-227 to decay to Th-227. And adding a thorium tracer to the raw material A. And the Th-227 and the thorium tracer agent are separated in a chemical manner. And installing the thorium isotope to an alpha counting disc. The alpha disks are counted using an alpha spectrum counting device to determine the number of Th-227 and tracer recovery%. The amount of Ac-227 is measured by using the count.

The invention discloses a method for rapidly separating < 223 > Ra, < 225 > Ac and < 232 > Th in a radioactive solution. The method comprises the following steps: (1) loading the radioactive solution into a chromatographic column filled with an inorganic microsphere material; the radioactive solution at least contains 223 Ra, 225 Ac and 232 Th; and (2) eluting the chromatographic column by adopting a first eluting agent to respectively obtain 223Ra and 225Ac. According to the method, a high-performance chromatographic separation mode is adopted, the separation degree is higher, the three elements of thorium, radium and actinide can be completely separated, the purity of separated products is high, the separation speed is high, and separation can be completed within about 60 minutes.