14 results about "Actinium" patented technology

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.

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.

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.

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.

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.

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.

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.

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 commercial nuclear reactor to produce a radium-225 (Ra-225) material. The Ra-225 material decays to produce an Ac-225 material.

A method of separating actinium and / or radium from proton-irradiated thorium metal. The thorium metal is irradiated to produce isotopes including thorium, actinium and / or radium. The resultant product is dissolved in solution and a selective precipitant is used to precipitate a bulk portion of the thorium. The precipitated thorium can be recovered. Chromatography is carried out on the remaining solution to remove residual thorium and to separate the actinium from the radium.