31 results about "Technetium-99" patented technology

A new transmutation assembly permits an efficient transmutation of a long-lived radioactive material (long-lived FP nuclides such as technetium-99 or iodine-129) which was produced in the nuclear reactor. Wire-type members of a long-lived radioactive material comprised of metals, alloys or compounds including long-lived FP nuclides are surrounded by a moderator material and installed in cladding tubes to form FP pins. The FP pins, and nothing else, are housed in a wrapper tube to form a transmutation assembly. The wire-type members can be replaced by thin ring-type members. The transmutation assemblies can be selectively and at least partly loaded into a core region, a blanket region or a shield region of a reactor core in a fast reactor. From a viewpoint of reducing the influence on the reactor core characteristics, it is optimal to load the transmutation assemblies into the blanket region.

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 relates to a process for separating technetium from a nitric solution of technetium through cathodic electrodeposition of said technetium by electrolysis. According to the process of the invention, the nitric solution of technetium is denitrified and its pH is adjusted to a value of approximately 5.5 to 7.5 before electrolysis. Electrolysis is conducted at galvanostatic rate, and the cathode potential is approximately -1.36 V/SHE to -1.16/SHE. The ratio of the cathode surface area (S) to the volume of the technetium solution to be electrolyzed may be in the region of 0.25 to 0.50 cm-1.

The invention belongs to the field of radioactive elements separation, and particularly relates to a method for extracting technetium from a molybdenum solution adopting polyamide resin. The method comprises the following steps: (1) preparing a molybdenum and technetium mixed solution with the concentration of hydroxide ions being greater than or equal to 1 mol/L; (2) adsorbing technetium in the molybdenum and technetium mixed solution obtained in the step (1) by adopting polyamide resin; (3) adopting a scrubbing solution for cleaning so as to remove a small amount of molybdenum adhered on the surface of polyamide resin; (4) desorbing technetium adsorbed on the surface of polyamide resin by adopting a leacheate with the concentration of hydroxide ions being smaller than 1 mol/L. The method for extracting technetium from the molybdenum solution adopting polyamide resin has the characteristics that the radiation resistance of a solid-phase separation material is good, the adsorption separation performance is stable, and the solid-phase separation material is low in cost and easy to obtain.

The invention belongs to the field of radioactive nuclide separation, and particularly relates to a method for extracting technetium from a molybdenum solution by means of activated carbon materials. The method comprises the following steps that 1, a molybdenum and technetium mixed solution with the hydroxide ion concentration larger than or equal to 1 mol/L is prepared; 2, technetium in the molybdenum and technetium mixed solution obtained in the first step is adsorbed through the activated carbon materials; 3, a small amount of technetium which adheres to the surfaces of the activated carbon materials is washed with a washing solution; and 4, technetium adsorbed to the surfaces of the activated carbon materials is desorbed with a leaching solution with the hydroxide ion concentration smaller than 1 mol/L. The method has the advantages that the solid-phase separation material is good in radiation-resistant performance, stable in adsorption and separation performance, low in price and easy to obtain.

A generator that allows for a non-fission based method of producing and recovering ^99mTc from neutron-irradiated molybdenum. This generator system is based on the isolation of ^99mTc, as the decay product from a source of ⁹⁹Mo labelled molybdenum carbonyl Mo(CO)₆ through a distillation process. The ^99mTc obtained from this distillation is produced with high efficiency and purity in a solvent-free form, which can then be dissolved in water or other solvents to produce a solution at the required specific activity and concentration, as reasonably determined by the operator.

This invention relates to compositions that are radiolabeled scintigraphic imaging agents, comprising a polybasic compound covalently linked to a radiolabel binding moiety and the composition further comprising a polysulfated glycan. The invention also provides methods for producing and using such compositions. Specifically, the invention relates to compositions comprised of technetium-99m (Tc-99m) labeled scintigraphic imaging agents comprising a polybasic compound having at least 5 chemical functionalities that are basic at physiological pH and a radiolabel-binding moiety, the composition further comprising a polysulfated glycan, the composition being capable of accumulating at inflammatory sites in vivo. Methods and kits for making such compositions, and methods for using such compositions to image sites of infection and inflammation in a mammalian body, are also provided.

An accelerator based systems are disclosed for the generation of isotopes, such as molybdenum-98 (“99Mo”) and metastable technetium-99 (“99mTc”) from molybdenum-98 (“98Mo”). Multilayer targets are disclosed for use in the system and other systems to generate 99mTc and 98Mo, and other isotopes. In one example a multilayer target comprises a first, inner target of 98Mo surrounded, at least in part, by a separate, second outer layer of 98Mo. In another example, a first target layer of molybdenum-100 is surrounded, at least in part, by a second target layer of 98Mo. In another example, a first inner target comprises a Bremsstrahlung target material surrounded, at least in part, by a second target layer of molybdenum-100, surrounded, at least in part, by a third target layer of 98Mo.

The invention relates to a technetium-99m labeled propyl zoledronic acid composition and a preparation method thereof, belonging to the fields of radiopharmaceuticals and nuclear medicines. The propyl zoledronic acid composition is technetium-99m labeled 1-hydroxy-2-(propyl-1H-iminazole-1-base)-ethane-1, 1-diphosphic acid (99Tcm-PIDP). The preparation method of the composition comprises the step of reacting the ligand PIDP, a reducing agent SnCI2.2H2O and a pH buffer solution with a pertechnetic acid (99TcmO4-) solution to obtain the technetium-99m labeled PIDP composition. The 99Tcm-PIDP is used for diagnostic imaging. The product of the 99Tcm-PIDP has higher bone tissue intake (Am, bone) (% ID/g) and (Am, bone/Am, blood) than a document value and rapid tissue removal speed, which shows that the product has the potential of being used as a bone developing agent.

The invention relates to a nuclear fuel element doped with technetium-99, which is characterized in that fuel pellets are overlapped to be placed into a zirconium quaternary alloy cladding pipe, after being compressed by a compression spring, two end ports of the cladding pipe are sealed and fixed by an end plug, and the nuclear fuel element is characterized in that each fuel pellet is a mixture of tachnetiuim-99 and uranium dioxide, wherein a ratio of the nuclear density of the technetium-99 and the sum of the nuclear density of technetium-99 and uranium-238 in the uranium dioxide is 10 percent to 90 percent. The resonance characteristic of the technetium-99 is utilized, and the technetium-99 is used for partially substituting the uranium-238 in the enriched uranium fuel, so that three purpose for enhancing the Doppler coefficient, reducing minor actinides nuclide so as to really reduce the minor actinides, guaranteeing the prompt negative temperature coefficient and transforming the nuclear waste technetium-99, and the safety of a reactor can be enhanced.

The invention belongs to the field of molecular imaging probes and particularly relates to a preparation method of a dual-modal nano imaging drug Dex-Rho-99mTc based on glucan, and an application of the drug in imaging diagnosis. The general formula of the drug is Rho-Dex-PEG-DTPA-99mTc, wherein the Dex represents for the glucan of which the molecular weight is 10-100k, the PEG represents for polyethylene glycol of which the molecular weight is 1-10k, the Rho represents for a fluorescent group rhodamine, the DTPA is a chelating agent of an imaging nuclide and the 99mTc is a radioisotope Technetium-99 used for SPECT imaging. In the invention, the surface of the high-molecular material glucan is modified by a certain number of amino groups and the PEG, the fluorescent group and the SPECT imaging groups are connected to the glucan supporter through the amino groups and finally the drug is marked by the radioisotope [99mTc]. The drug is good in biocompatibility, is simple in the preparation method, is safe and convenient to use and can be employed in dual-modal imaging. The dual-modal nano imaging drug has wide application prospects in the biomedical fields of early diagnosis of cancer, medicine delivery under guide of imaging, noninvasive iconography curative effect evaluation and the like.

The present invention relates generally to a system and method for producing Technetium-99m. More specifically, the present invention relates to a novel method and device for modifying commercially-available, widely-used low energy positron emission tomography (PET) cyclotrons in order to produce Technetium-99m in a more efficient, less expensive manner that previously known.

The invention discloses new application of technetium-99, in particular to application of technetium-99 as a burnable poison element in a nuclear reactor. By utilizing neutronabsorption performance of technetium-99, technetium-99 metal is made into a rod-bundle-shaped burnable poison element, which is arranged in a fuel assembly to be made into a burnable poison assembly. On one hand, the excess reactivity can be suppressed; and on the other hand, technetium-99 can be consumed, and therefore long-term radioactivity harm of technetium-99 can be reduced.

Systems and methods for separation or isolation of technetium radioisotopes from aqueous solutions of radioactive or non-radioactive molybdate salts using a polyalkyl glycol-based cross-linked polyether polymer. Some embodiments can be used for the effective purification of radio-active technetium-99m produced from low specific activity ⁹⁹Mo.

A device for concentrating ^99mTc pertechnetate and a method thereof are disclosed. The device includes a concentration device, a control device and a central processing unit. The concentration device is for concentrating ^99mTc pertechnetate, the control device connects with each members of the concentration device, and the central processing unit is used for saving an automatic control program. The automatic control program is run by the central processing unit so as to detect and monitor weight as well as activity of the concentrated ^99mTc pertechnetate. Due to the automatical control, the concentration quality and production efficiency of the ^99mTc pertechnetate are improved. Moreover, the radiation dose received by users is reduced.

The invention discloses a <99m>Tc(HYNICPBB)(tricine/TPPTS) complex as well as a preparation method and an application. The <99m>Tc(HYNICPBB)(tricine/TPPTS) complex is obtained through two steps including synthesis of a ligand HYNICPBB and preparation of <99m>Tc(HYNICPBB)(tricine/TPPTS). The complex is simple to prepare, high in radiochemical purity and good in stability, has better water solubility and has certain uptake in MCF-7 cells, the uptake can be significantly inhibited by palbociclib, which indicates that the complex has a CDK4/6 specificity. The complex has higher uptake and retention and better tumor/muscle ratios at tumor parts of female Balb/c nude mice carrying MCF-7 tumor, has obviously reduced uptake of non-target organs such as liver and can be applied to preparation of anovel CDK4/6 targeting tumor developer.

Deuterium water and tritium water are important foundations of nuclear power industry, medical treatment and the like, but an existing deuterium water concentration technology consumes much energy, is extremely high in cost and is very complex. Nuclear wastewater generated by a first nuclear power station of the Fukushima island in Japan contains a large amount of radioactive substances such as tritium, strontium 90, cobalt 16, iodine 129, carbon 14, technetium 99 and the like, and the treatment cost is high; and the Japan government decides that the nuclear wastewater is discharged into the Pacific Ocean in two years on April 13, 2021, which will cause serious influence on the ecological environment of the Pacific Ocean and the ecological environment of the whole ocean. According to the environment-friendly device and structure for absorbing external heat to evaporate water and concentrating deuterium water and tritium water, water 5 wets a water absorption substance 1 through gravity flow and capillarity and absorbs external heat to evaporate; protium water in the water 5 is discharged through a gas diffusion separation method by utilizing the difference that the molecular weight of protium water is smaller than that of deuterium water and tritium water, so that the concentrations of deuterium water, tritium water and other substances in water 5 are increased; and the deuterium water and the tritium water can be further extracted while the nuclear wastewater is harmlessly treated.

Heavy water is an important basis for nuclear power industry, medical treatment and the like, but an existing heavy water extraction technology consumes much energy, is extremely high in cost and is very complex; overweight water generated by nuclear power stations is increased gradually, particularly nuclear wastewater generated by the first nuclear power station of the Fukushima island in Japan contains a large amount of radioactive substances such as tritium, strontium 90, cobalt 16, iodine 129, carbon 14 and technetium 99, the treatment cost is high, Japan government decides that the nuclear wastewater is discharged into the Pacific Ocean in two years on April 13, 2021, and the ecological environment of the Pacific Ocean and the ecological environment of the whole ocean are seriously influenced. The invention provides an environment-friendly device for preparing heavy water and overweight water mixed liquid by evaporating light water and a structure of the environment-friendly device, water 5 wets a water guide strip 3 and an evaporation layer 1 through gravity flow and capillarity, absorbs external heat and evaporates on the surface of the evaporation layer 1, the difference that the light water is easier to evaporate in specific gravity and overweight water, the saturated vapor pressure is small is utilized, light water in the discharged water 5 is evaporated, a heavy water and overweight water mixed solution with a certain concentration is extracted, and meanwhile the surrounding environment and objects are cooled.

This invention relates to radiolabeled scintigraphic imaging agents and reagents for preparing such imaging agents and methods for producing and using such reagents. Specifically, the invention relates to reagents for preparing scintigraphic imaging agents for imaging sites in a mammalian body comprising a specific binding compound including specific-binding peptide embodiments thereof, covalently linked to a radiolabel complexing moiety. Reagents, methods and kits for making such reagents, and methods for using such reagents labeled with technetium-99m (Tc-99m) via Tc-99m complexing moieties comprising said reagents, are provided.