58 results about "Technetium" patented technology

To provide a calcined body that is processed easier than a conventional calcined body and where differences in hardness between production lots are suppressed.SOLUTION: A calcined body comprises: at least one first transition metal element selected from the group consisting of manganese (Mn), iron (Fe), cobalt (Co), nickel (Ni), copper (Cu), molybdenum (Mo), technetium (Tc), ruthenium (Ru), rhodium (Rh), palladium (Pd), and silver (Ag); a coloring element of at least one of a lanthanoid rare earth element and a second transition metal element different in kind from the first transition metal element; and zirconia containing a stabilizing element. A content of the first transition metal element is 100 mass.ppm or more, a content of the second transition metal element is less than 100 mass.ppm, and an absolute value of a difference in hardness relative to a hardness of a calcined body obtained from a commercially available powder is 10 HV or less.SELECTED DRAWING: None

Provided here are methods for producing a shaped metal-supported catalyst. One such method includes the steps of mixing a support hydroxide with an aqueous mixture of an active metal compound to form a malleable mixture of an active metal incorporated support hydroxide, passing the malleable mixture through a molding device to produce a shaped metal-supported wet catalyst; and drying and calcining the shaped metal-supported wet catalyst. The support hydroxide contains one or more of aluminium hydroxide, silica hydroxide, zirconia hydroxide, cerium hydroxide, titanium hydroxide, lanthanum hydroxide, gallium hydroxide, or niobium hydroxide. The active metal compound can be one or more of vanadium, niobium, tantalum, chromium, molybdenum, tungsten, manganese, technetium, and rhenium.

A grease composition that includes at least an oil-based medium, a thickener, and a fullerene-like nano-structure. The fullerene-like nano-structure includes a plurality of layers each comprised of a metal chalcogenide composition has a molecular formula of MX2, where M is a metallic element selected from the group consisting of titanium (Ti), vanadium (V), chromium (Cr), manganese (Mn), iron (Fe), cobalt (Co), nickel (Ni), copper (Cu), zinc (Zn), zirconium (Zr), niobium (Nb), molybdenum (Mo), technetium (Tc), ruthenium (Ru), rhodium (Rh), palladium (Pd), silver (Ag), cadmium (Cd), hafnium (Hf), tantalum (Ta), tungsten (W), rhenium (Re), osmium (Os), iridium (Ir), platinum (Pt), gold (Au), mercury (Hg) and combinations thereof, and X is a chalcogen element selected from the group consisting of sulfur (S), selenium (Se), tellurium (Te), oxygen (O) and combinations thereof.

The invention relates to a technetium [99mTc]-labeled deuterated tropane derivative and application thereof, and belongs to the technical field of nuclear medicine. The invention provides a technetium [99mTc]-labeled deuterated tropane derivative, which can be specifically combined with a dopamine transporter, and can be used for preparing the technetium [99mTc]-labeled deuterated tropane derivative. The technetium [99mTc]-labeled deuterated tropane derivative has the advantages of good affinity to a dopamine transporter, high radioactive uptake of a target region (striatum) in a brain and high target / background ratio, and has an extremely high application prospect in the aspect of SPECT (Single Photon Emission Computed Tomography) imaging of the dopamine transporter.

To extract technetium-99m from low-specific-activity molybdenum-99 in a short time without being influenced by the volume of molybdenum solution.The method for recovering technetium-99m from low-specific-activity molybdenum-99 is a method in which the daughter nuclide technetium-99m produced through the decay of molybdenum-99 with a low specific activity contained in a high-concentration molybdenum solution containing the molybdenum-99 with a low specific activity is separated by using activated charcoal and recovered, and the method is characterized in that the activated charcoal is immersed into the molybdenum solution and selectively adsorbs a trace amount of technetium-99m in the solution, even when molybdenum-99 is present 1016 times or more abundantly in terms of the ratio of the number of atoms.

This invention discloses a fluorine-free, environmentally friendly nanomaterial for pretreatment of metal surfaces, its preparation method, and its application method, belonging to the field of coating pretreatment technology. The fluorine-free, environmentally friendly nanomaterial for pretreatment of metal surfaces provided by this invention includes ammonium zirconia nanoparticles and an adsorption modifier; the ammonium zirconia nanoparticles are obtained by coordination aggregation of ammonium ions and hydrated zirconium ions, and the adsorption modifier is obtained by reacting a metal oxide salt with diethylenetriaminepentamethylenephosphonic acid; the metal oxide salt includes one or more of hafnium, technetium, or antimony. The nanomaterial provided by this invention exhibits rapid film formation and high corrosion resistance on metal substrate surfaces. The material does not contain fluorine, avoiding fluorine pollution. The preparation and application processes are environmentally friendly and simple, and it has broad application prospects in the field of coating pretreatment.

To extract technetium 99m from low specific activity Mo 99 in a short time, without being influenced by an amount of a molybdenum solution.SOLUTION: A method for recovering technetium-99m from low specific radioactivity molybdenum-99 involves separating and collecting the daughter nuclide technetium-99m, which is produced by the decay of molybdenum-99 contained in a high-concentration molybdenum solution with low specific activity, using activated carbon. The activated carbon is characterized by being immersed in the molybdenum solution and selectively adsorbing trace amounts of technetium-99m present, even when the molybdenum-99 to atom ratio is 1016 or higher.SELECTED DRAWING: Figure 1

The invention discloses a method for extracting technetium from PUREX process waste liquid. The method comprises the working procedures of material blending, extraction, washing, reduction reverse extraction and reverse extraction. According to the technetium extraction and purification process, the technetium is separated from elements such as zirconium, niobium, ruthenium, uranium, neptunium and plutonium by using the technetium as a raw material, tributyl phosphate (TBP) as an extracting agent and hydrogenated kerosene (OK) as a diluent, meanwhile, the economy and safety of the reagents adopted by the process are verified by engineering, and the operation process of each procedure also meets the requirements of high flux, continuous treatment and remote operation.

The present invention concerns dosimetry-related uses and methods that rely on a metastable technetium-99 (99mTc) radionuclide-comprising (dosimetric) radioimmunoconjugate (RIC) to evaluate or establish therapeutic doses of yttrium-90 (90Y) radionuclide-comprising (therapeutic) radioimmunoconjugates, both RICs targeting the same molecular target. More specifically, radioimmunoconjugates that comprise a CD66-binding component are used. Another aspect of the invention relates to Single Time Point dosimetry procedures replacing the need for traditionally used Multiple Time Point dosimetry procedures for yttrium-90 (90Y) radionuclide-comprising radioimmunoconjugates.

A process for producing technetium-99m from a molybdenum-100 metal powder, comprising the steps of:(i) irradiating in a substantially oxygen-free environment, a hardened sintered target plate coated with a Mo-100 metal, with protons produced by a cyclotron;(ii) dissolving molybdenum ions and technetium ions from the irradiated target plate with an H2O2 solution to form an oxide solution;(iv) raising the pH of the oxide solution to about 14;(v) flowing the pH-adjusted oxide solution through a resin column to immobilize K[TcO4] ions thereon and to elute K2[MoO4] ions therefrom;(vi) eluting the bound K[TcO4] ions from the resin column;(vii) flowing the eluted K[TcO4] ions through an alumina column to immobilize K[TcO4] ions thereon;(viii) washing the immobilized K[TcO4] ions with water;(ix) eluting the immobilized K[TcO4] ions with a saline solution; and(x) recovering the eluted Na[TcO4] ions.

The present invention extracts, at a use point such as a hospital: a radiopharmaceutical using radioactive molybdenum-99 having low specific activity as a raw material; and radioactive technetium-99m, which serves as a labeling compound raw material for the radiopharmaceutical.　Activated carbon or alumina is charged into a metal net-like cylindrical container which is not a column in which flow rate is limited. The metal net-like cylindrical container is immersed in a molybdenum solution brought to a low-pH acidic state and kept flowing by stirring, thereby preparing a molybdenum-99-adsorbed column in which the molybdenum-99 is adsorbed on the activated carbon or the alumina. The technetium-99m generated from the molybdenum-99 is eluted out from the molybdenum-99-adsorbed column and is then passed through a technetium-99m purification column filled with aluminum oxide, thereby capturing the technetium-99m. Physiological saline having a neutral pH is passed through the technetium-99m purification column, thereby separating and eluting out the technetium-99m, which is purified and recovered after impurities are removed therefrom.

The present invention relates to a two-column inverse selection type molybdenum-99 / technetium-99m generator device and a separation method. The device includes a host computer (1), a fully automatic molybdenum-99 / technetium-99m separation device (3), a two-column reaction module (16), a Mo-Tc feed liquid bottle (19), a product bottle (21), a liquid preparation solution bottle (9), an eluent No. 1 bottle (10), and an eluent No. 2 bottle (11). The fully automatic molybdenum-99 / technetium-99m separation device (3) includes a chassis (5), an injection pump module (14), a multi-channel switching valve (8), a pneumatic control valve (4), and a reaction module slide (17). The two-column reaction module (16) includes a drain valve switch (15), a syringe (13), an adsorption column (6), and a guard column (7). The device has the characteristics of high automation degree, fast preparation speed, high separation rate, etc. The high automation degree also reduces the radiation impact of radioactive radiation on operators.

This invention relates to a method for extracting technetium from nuclear fuel reprocessing waste using an extraction method, comprising the following steps: preparing a technetium-zirconium co-extraction feed; co-extracting technetium and zirconium using a TBP-kerosene organic solution as the extractant; reducing and back-extracting the technetium in the TBP organic phase co-extraction solution using a reducing stripping agent; and back-extracting the zirconium in the remaining TBP organic phase using a complexing stripping agent. This method improves upon existing techniques for extracting technetium from nuclear fuel reprocessing waste using extraction methods, which generate a significant amount of organic phase radioactive waste other than tributyl phosphate and require an additional solvent treatment system. It avoids introducing additional solvents and metal ion groups into the reprocessing system and is better compatible with the main process flow and facilities of reprocessing plants using the PUREX process, thus making the technetium extraction process easier to implement in reprocessing plants. The method provided by this invention prevents technetium from entering vitrification and geological disposal, thus preventing long-term hazards to the biosphere.

The present invention relates to the fields of radiopharmaceutical chemistry and clinical nuclear medicine technology, and specifically to a D-proline-modified folate derivative and its use. The radioactive preparation obtained by labeling the D-proline-modified folate derivative with a radionuclide can be prepared by kitting. It has high radiochemical purity and good stability. It exhibits significant uptake at the tumor site in tumor-bearing mice, is significantly inhibited by inhibitors, has a good target / non-target ratio, and exhibits low renal uptake. It can be used as a novel tumor imaging agent targeting folate receptors.

To constantly produce technetium Tc-99m from molybdenum Mo-99, and easily recover and recycle an expensive molybdenum sample (Mo-100 and Mo-98) with high efficiency in a constant period.SOLUTION: When Tc-99m is thermally separated from Mo-99 of a parent nuclide using a sublimation method, a plurality of sublimation devices 8 in which a sample 10 is arranged in a plurality of stages of sample shelves 14 are inserted into a plurality of tubular furnaces 100 and heated, a new sample 10 is arranged in the uppermost stage or lowermost stage of the sample shelf 14 of one sublimation device for each first predetermined period, the sublimation devices 8 are rotated by only a predetermined angle, the sample shelves 14 are moved downward or upward by one stage for each second predetermined period longer than the first predetermined period, and an oldest sample 10 is taken out from the lowermost stage or uppermost stage of the sample stage 14 of the sublimation devices 8 for each third predetermined period longer than the second predetermined period.SELECTED DRAWING: Figure 12

The invention relates to the technical field of composite carbon materials, in particular to a metal carbide modified carbon material and a preparation method and application thereof. The preparation method provided by the invention comprises the following steps: mixing a carbon material with a modification element precursor to obtain mixed powder; and calcining the mixed powder in a protective atmosphere or a vacuum environment to obtain the metal carbide modified carbon material, the modification elements in the modification element precursor comprise one or more of scandium, titanium, vanadium, chromium, manganese, iron, cobalt, nickel, yttrium, zirconium, niobium, molybdenum, technetium, ruthenium, rhodium, palladium, hafnium, tantalum, tungsten, iridium and rhenium; the carbon material is an unmodified carbon material or a three-dimensional structure graphene modified carbon material. According to the preparation method, the coupling and adhesion capacity between the metal carbide and the carbon material can be remarkably improved, so that the carbon material has excellent structural stability, and the carbon material is applied to the fields of thermal management materials, high-strength and high-conductivity metal-based composite materials, high-conductivity and high-thermal-conductivity resin-based composite materials and polishing agent abrasives.

It would be advantageous with the close quarters in breast procedure rooms to create a Gamma Probe system incorporating multi modalities, sensitivities, and multiple ranges for utilization in breast intervention procedures for the diagnosis and verification for breast cancer. Systems for specimen radiography assist radiologists and surgeons in the detection and classification of abnormal lesions in medical images gleaned from breast biopsies / lumpectomies and a Gamma Probe system with a sensor to detect radioactive, metallic / magnet, or RFID waves to help locate a lump or abnormality which were placed by an Interventional Radiologist. Radio guided surgery (RGS) uses gamma probes to localize radioactive targets. The three common RGS radioisotopes: technetium-99m (99mTc), indium-111 (111In), and iodine-125 (125I). The aspects of the disclosed embodiments pertain to a gamma probe that is able to simultaneously detect 2-3 isotopes automatically without actuating a physical switch.

Water containing less than 60 Hz of minerals is disclosed. The water containing less than 60 Hz of minerals contains, as active ingredients, 0.04-34 parts by weight of minerals from which at least one electron has been removed, among germanium (Ge), silver (Ag), iridium (Ir), nickel (Ni), palladium (Pd), tantalum (Ta), antimony (Sb), zinc (Zn), indium (In), boron (B), astatine (At), thallium (Tl), magnesium carbonate (MgCO3), tin (Sn), iron (Fe), calcium sulfide (CaS), molybdenum (Mo), chromium (Cr), sodium (Na), tungsten (W), gallium (Ga), strontium (Sr), potassium (K), beryllium (Be), barium (Ba), magnesium (Mg), scandium (Sc), yttrium (Y), calcium (Ca), titanium (Ti), vanadium (V), hafnium (Hf), bromine (Br), zirconium (Zr), copper (Cu), manganese (Mn), rubidium (Rb), technetium (Tc), platinum (Pt), niobium (Nb), gold (Au), phosphate (Pi), rhenium (Re), ruthenium (Ru), cobalt (Co), zinc oxide (ZnO), aluminum (Al), selenium (Se), bismuth (Bi), phosphorus (P), rhodium (Rh), silicon (Si), iodine (I), tellurium (Te), sulfur (S), lithium (Li), osmium (Os), magnesium hydroxide (Mg(OH)2), and cesium (Cs), mixed with 100 parts by weight of water, wherein there are at least 5 types of minerals.

The invention relates to a method for recovering one or more metals selected from the group consisting of technetium, ruthenium, palladium and rhenium from an aqueous solution, comprising: adding to said solution a reagent to precipitate the one or more metals in the solution, and then collecting the precipitate thus formed, characterized in that the reagent comprises or consists of 1, 3-butanediol, 1, 3-butanediol, 1, 3-butanediol, 1, 3-butanediol, 1, 3-butanediol, 1, 3-butanediol, 1, 3-butanediol, 1, 3-butanediol, or 1, 3-butanediol. The invention relates to a composition consisting of a mixture of 1, 10-phenanthroline and a nickel (II) salt selected from the group consisting of nickel (II) nitrate and nickel (II) sulfate. Application: recovering all or part of technetium, ruthenium and / or palladium from an aqueous solution of the fission product prior to an operation intended to vitrify the fission product; and recovering all or part of ruthenium, palladium and / or rhenium from the solution obtained by pickling the industrial and / or municipal waste with nitric acid.

A switching device including a first electrode layer, a second electrode layer arranged to face the first electrode layer, and a selection layer arranged between the first electrode layer and the second electrode layer, wherein the first electrode layer is doped with at least one of manganese (Mn), iron (Fe), niobium (Nb), molybdenum (Mo), technetium (Tc), ruthenium (Ru), rhodium (Rh), hafnium (Hf), tantalum (Ta), tungsten (W), rhenium (Re), iridium (Ir), or platinum (Pt), may be provided.

The invention discloses a method for solidifying radionuclide technetium in a solution and application of the method, and belongs to the technical field of spent fuel post-treatment. The curing method comprises the following steps: firstly, acidifying a technetium-containing solution by using nitric acid, then adding the acidified technetium-containing solution into a sodium metaaluminate solution, and reacting under a low-temperature condition to ensure that technetium is covalently bonded with high-activity mu < 1->-OH in a curing product in a form of pertechnetate (TcO4 <->) and is cured in pseudo-boehmite-like mixed crystals with stable crystal structures; the curing method is mild in operation condition and simple in technological process, overcomes the defects that in a traditional cement curing and glass curing method, the size of a cured product is increased, technetium is prone to volatilization and the like, has the advantages of being small in cured product size, high in curing efficiency, low in cost and environmentally friendly, the maximum curing amount can reach 100 mg / g, and the curing method is suitable for industrial production. The method is suitable for treating technetium-containing acidic nucleus waste liquid generated in the spent fuel post-treatment process.

This invention provides a technetium-99m preparation system, its usage method, and its applications. The system includes a reaction module and a purification module. The reaction module includes an electron beam channel, a shell, and a gamma photon fabrication unit inside the shell, forming a Mo-containing solution region between the shell and the gamma photon fabrication unit. The gamma photon fabrication unit is used to produce gamma photons, and the Mo-containing solution region is used to contain the Mo-containing solution and carry out the reaction. The gamma photon fabrication unit includes a metal outer layer and at least one target plate disposed inside the metal outer layer. The electron beam channel penetrates the shell and connects to the metal outer layer of the gamma photon fabrication unit. The Mo-containing solution region and the purification module also include a circulation loop. The mixture generated in the Mo-containing solution region is passed through the circulation loop into the purification module for purification to form a technetium-99m separation solution and a Mo separation solution. The Mo separation solution is returned to the Mo-containing solution region through the circulation loop. By using the technetium-99m preparation system provided by this invention, low-cost and high-efficiency production of technetium-99m can be achieved.

To extract, at hospitals or other use points, a radiopharmaceutical made from low-specific-activity radioactive molybdenum-99 and of radioactive technetium-99m as a raw material for a labeling compound for the radiopharmaceutical. Pack activated charcoal or alumina into a cylindrical metal mesh rather than a column, with which the flow rate is limited, in advance, adjust the molybdenum solution to a low-pH, acidic state, and then immerse the cylindrical metal mesh into the molybdenum solution while the molybdenum solution is flowing as a result of being stirred, to prepare a molybdenum-99-adsorbing column in which the molybdenum-99 has been adsorbed onto the activated charcoal or alumina, then elute the technetium-99m produced from the molybdenum-99 from the molybdenum-99-adsorbing column, and pass the eluate through a technetium-99m-purifying column packed with aluminum oxide to trap the technetium-99m, and then pass neutral-pH physiological saline through the technetium-99m-purifying column to separate and elute the technetium-99m, thereby purifying and recovering the technetium-99m while removing impurities.

The utility model relates to the technical field of liquid medicine production, in particular to an integrated molybdenum technetium generator. The integrated molybdenum technetium generator comprises a shell; the lead shielding seat is arranged in the shell and is provided with a mounting hole penetrating through the surface of one side of the lead shielding seat; the generating column is mounted in the mounting hole; the liquid inlet assembly and the liquid collecting assembly are both installed on the shell, the liquid inlet assembly is used for injecting leacheate into the generation column, and the liquid collecting assembly is used for extracting liquid from the generation column; and the lead shielding block is mounted on the shell and blocks the hole opening of the mounting hole. By means of the structure, radiation shielding can be better carried out in the using process by means of the lead shielding block, and therefore the integrated molybdenum technetium generator can be used without being placed in a shielding body outside a shell.

A system is provided that utilizes radiation emitted by radioactive technetium produced by the radioactive decay of radioactive molybdenum. [Solution] The system comprises a radioactive molybdenum production unit that produces radioactive molybdenum by irradiating a molybdenum solution with neutrons using a small accelerator neutron source, and a radioactive technetium extraction unit that extracts radioactive technetium, a daughter nuclide produced by radioactive decay of the radioactive molybdenum produced in the radioactive molybdenum production unit. The radioactive technetium extraction unit is integrated with the radioactive molybdenum production unit and applies ultrasonic vibrations to rod-shaped activated carbon immersed in the molybdenum solution containing the radioactive molybdenum and the radioactive technetium, thereby selectively adsorbing the radioactive technetium onto the surface of the activated carbon, thereby extracting the radioactive technetium, which has a short half-life, so that it can be used at the point of use.

This invention discloses a uranium-aluminum alloy for uranium-molybdenum-technetium targets and its preparation method. The uranium content in the uranium-aluminum alloy is 25.4 ± 2.0 wt%. The impurity content of the uranium-aluminum alloy meets the following requirements: B ≤ 1 μg / g, Cd ≤ 2 μg / g, Li ≤ 8 μg / g, C ≤ 600 μg / g, Cr ≤ 240 μg / g, Cu ≤ 100 μg / g, Fe ≤ 1000 μg / g, Ni ≤ 250 μg / g, and Gd ≤ 0.25 μg / g. The density of the uranium-aluminum alloy is 3.0–3.4 g / cm³. 3 The uranium-aluminum alloy comprises Al, UAl3, and UAl4 phases. The preparation method of the uranium-aluminum alloy includes the following steps: first, heating to 1190-1220℃ within 50-80 minutes; then holding at 1190-1220℃ for 57-63 minutes; then cooling naturally to 990-1030℃; finally, tilting and casting into a mold at 350-500℃, followed by annealing the prepared ingot under vacuum at 580-640℃ for 10-25 hours. This invention enables the production of uranium-aluminum alloys with controllable composition, density, phase, and microstructure through induction melting-tilt casting-annealing, meeting production requirements. 99 Requirements for uranium-aluminum alloy targets for Mo.

The invention provides a method for determining the content of moisture in a matched medicine box for injection of technetium [99mTc] radiopharmaceutical by a combined method of a cassette stove and a Karl Fischer moisture meter, which comprises the following steps: heating the medicine box by using the cassette stove, then conveying the moisture into a Karl Fischer test solution of the Karl Fischer moisture meter, stirring and then determining the moisture. According to the method, the moisture in the complex components of the stannous MIBI medicine box for injection can be accurately measured, the specificity is good, methanol and auxiliary material components have no interference in moisture detection, the accuracy is high, the reproducibility is good, the linear range is wide, and the automation degree is high.

The invention relates to the technical field of uranium and plutonium separation, and provides a treatment method in a PUREX process, the treatment method comprises the following steps: adding a reducing agent, a characteristic complexing agent and a feed liquid containing uranium, plutonium and technetium into a plutonium back extractor, the plutonium in the feed liquid is reduced by the reducing agent, and technetium in the feed liquid and the characteristic complexing agent generate a liquid complex so as to jointly generate a plutonium-containing aqueous phase back extraction liquid; the feed liquid subjected to reduction back extraction generates uranium-containing organic phase back extraction liquid. Tc (V) and Tc (IV) are selectively complexed by the characteristic complexing agent, and the catalytic action of technetium can be inhibited or even blocked, so that technetium catalytic cycle failure is promoted, excessive use of a reducing agent can be avoided to a certain extent, the effective separation effect of uranium and plutonium is improved, the influence of technetium on the valence state of neptunium can be avoided to a certain extent, and the catalytic action of technetium can be inhibited or even blocked; the method is of great significance in controlling neptunium and technetium trend, improving uranium and plutonium product quality and reducing radionuclide harm.

A generator column assembly for the elution of a radioisotope, having a generator column container having a bottom wall defining a flow outlet aperture, an open top end, and a sidewall extending from the open top end to the bottom wall that defines an interior volume having a substantially cylindrical upper volume portion and a substantially cylindrical lower volume portion, the upper volume portion having a diameter that is greater than a diameter of the lower volume portion, and a closure cap assembly including a container cap defining a flow inlet aperture.