312 results about "Technetium" 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.

The present invention provides novel amino acid compounds useful in detecting and evaluating brain and body tumors. These compounds have the advantageous properties of rapid uptake and prolonged retention in tumors and can be labeled with halogen isotopes such as fluorine-18, iodine-123, iodine-124, iodine-125, iodine-131, bromine-75, bromine-76, bromine-77, bromine-82, astatine-210, astatine-211, and other astatine isotopes. These compounds can also be labeled with technetium and rhenium isotopes using known chelation complexes. The compounds disclosed herein bind tumor tissues in vivo with high specificity and selectivity when administered to a subject. Preferred compounds show a target to non-target ratio of at least 2:1, are stable in vivo and substantially localized to target within 1 hour after administration. Preferred compounds include 1-amino-2-[¹⁸F]fluorocyclobutyl-1-carboxylic acid (2-[¹⁸F]FACBC) and 1-amino-2-[¹⁸F]fluoromethylcyclobutyl-1-carboxylic acid (2-[¹⁸F]FMACBC). The labeled amino acid compounds of the invention are useful as imaging agents in detecting and/or monitoring tumors in a subject by PET or SPECT.

There is provided a magnetoresistance element including a free layer that includes a first ferromagnetic layer and a second ferromagnetic layer whose magnetization directions are equal to each other and a nonmagnetic film intervening between the first and second ferromagnetic layers, a pinned layer including a third ferromagnetic layer that faces the free layer, and a nonmagnetic layer intervening between the free layer and the pinned layer, the nonmagnetic film containing a material selected from the group including titanium, vanadium, zirconium, niobium, molybdenum, technetium, hafnium, tungsten, rhenium, alloys thereof, semiconductors and insulators.

A dendrimer conjugate according to Formula (I), or its pharmaceutically acceptable salt, or solvate thereof: and complexes of Formula I conjugates with metals radionuclides of elements such as rhenium, technetium, yttrium, lutetium and others to provide a complex for imaging tissues or for the radiotherapeutic treatment of cancer tissue. Such complexes are specific to PSMA protein and can therefore be used in imaging or treating cancer of the prostate and other tissue where the protein is expressed.

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.

A photosensitizing transition metal complex of the formula (Ia) MLY¹, (Ib) MLX₃ (Ic) MLY²X, (Id) MLY³X or (Ie) MLY⁴X in which M is a transition metal selected from ruthenium, osmium, iron, rhenium and technetium, preferably ruthenium or osmium. X is a co-ligand independently selected from NCS—, Cl—, Br—, I—, CN—, H₂O; pyridine unsubstituted or substituted by at least one group selected from vinyl, primary, secondary or tertiary amine, OH and C_1-30 alkyl, preferably NSC and CN—; L is a tridentate polypyridine ligand, carrying at least one carboxylic, phosphoric acid or a chelating group and one substituted or unsubstituted alkyl group having 1 to 50 carbon atoms, substituted or unsubstituted alkylamide group having 2 to 30 carbon atoms or substituted or unsubstituted aralkyl group having 7 to 50 carbon atoms. A dye-sensitized electrode includes a substrate having an electrically conductive surface, an oxide semiconductor film formed on the conductive surface, and the above sensitizer of formula (Ia), (Ib), (Ic), (Id) or (Ie) as specified above, supported on the film. A solar cell includes the above electrode, a counter electrode, and an electrolyte deposited there between.

A method for cracking hydrocarbon, comprises: providing steam and hydrocarbon; and feeding steam and hydrocarbon into a reactor accessible to hydrocarbon and comprising a perovskite material of formula A_aB_bC_cD_dO_3-δ, wherein 0<a<1.2, 0≦b≦1.2, 0.9<a+b≦1.2, 0<c<1.2, 0≦d≦1.2, 0.9<c+d≦1.2, −0.5<δ<0.5; A is selected from calcium, strontium, barium, and any combination thereof; B is selected from lithium, sodium, potassium, rubidium and any combination thereof; C is selected from cerium, zirconium, antimony, praseodymium, titanium, chromium, manganese, ferrum, cobalt, nickel, gallium, tin, terbium and any combination thereof; and D is selected from lanthanum, cerium, praseodymium, neodymium, promethium, samarium, europium, gadolinium, terbium, dysprosium, holmium, ebium, thulium, ytterbium, lutetium, scandium, titanium, vanadium, chromium, manganese, ferrum, cobalt, nickel, copper, zinc, yttrium, zirconium, niobium, molybdenum, technetium, ruthenium, rhodium, palladium, silver, cadmium, hafnium, tantalum, tungsten, rhenium, osmium, iridium, platinum, gold, gallium, indium, tin, antimony and any combination thereof.

Disclosed is an oxide catalyst comprising an oxide represented by the formula Mo₁V_aNb_bX_cY_dZ_eQ_fO_n (wherein: X is at least one element selected from the group consisting of Te and Sb; Y is at least one element selected from the group consisting of Al and W; Z is at least one element selected from the group consisting of elements which individually form an oxide having a rutile structure and a Z oxide having a rutile structure is used as a source of Z for producing the catalyst; Q is at least one element selected from the group consisting of titanium, tin, germanium, lead, tantalum, ruthenium, rhenium, rhodium, iridium, platinum, chromium, manganese, technetium, osmium, iron, arsenic, cerium, cobalt, magnesium, nickel and zinc, and a Q compound not having a rutile structure is used as a source of Q for producing the catalyst; and a, b, c, d, e, f and n are, respectively, the atomic ratios of V, Nb, X, Y, Z, Q and O, relative to Mo). Also disclosed is a process for producing an unsaturated carboxylic acid or an unsaturated nitrile by using the above-mentioned oxide catalyst.

The invention provides novel amino acid compounds of use in detecting and evaluating brain and body tumors. These compounds combine the advantageous properties of α-aminoisobutyric acid (AIB) analogs namely, their rapid uptake and prolonged retention in tumors with the properties of halogen sustituents, including certain useful halogen isotopes such as fluorine-18, iodine-123, iodine-124, iodine-125, iodine-131, bromine-75, bromine-76, bromine-77, bromine-82, astatine-210, astatine-211, and other astatine isotopes. In addition the compounds can be labeled with technetium and rhenium isotopes using known chelation complexes. The amino acid compounds disclosed herein have a high specificity for target sites when administered to a subject in vivo. Preferred amino acid compounds include [¹⁸F] FAMP, ([¹⁸F]5a) and [¹⁸F]N-MeFAMP, ([¹⁸F]5b). The invention further features pharmaceutical compositions comprised of an α-amino acid moiety attached to eiher a four, five or a six member carbon-chain ring. The labeled amino acid compounds are useful as imaging agents in detecting and/or monitoring tumors in a subject by Positron Emission Tomography (PET) and Single Photon Emission Computer Tomography (SPECT).

The present invention relates to new synthetic methods for preparing 2-methoxyisobutylisonitrile and metal isonitrile complexes, such as tetrakis(2-methoxyisobutylisonitrile)copper(I) tetrafluroroborate, which are used in the preparation of technetium (^99mTc) Sestamibi, and novel intermediate compounds useful in such methods.

The present invention includes an apparatus for preparing samples for measurement by x-ray fluorescence spectrometry. The apparatus comprises a plate having one or more holes passing through the plate. The holes are covered by a film on one side of the plate. The holes are less than 500 micrometers across in one dimension where the film covers the holes. The film is translucent to x-rays. The present invention also includes an apparatus for preparing samples for measurement by x-ray fluorescence spectrometry. The apparatus comprises a plate having one or more holes passing through the plate. The holes are covered on one side of the plate by a detachable cover forming a water-tight seal against the plate. The cover is substantially free of the elements osmium, yttrium, iridium, phosphorus, zirconium, platinum, gold, niobium, mercury, thallium, molybdenum, sulfur, lead, bismuth, technetium, ruthenium, chlorine, rhodium, palladium, argon, silver, and thorium. The holes are less than about 500 micrometers across in one dimension where the cover covers the holes. The present invention also includes a method for preparing samples for measurement by x-ray fluorescence spectrometry. The method comprises providing a solution of with less than 10 micromolar solute and a volume of between about 2 microliters and about 2 milliliters. The solution is concentrated and analyzed using x-ray fluorescence spectrometry.

The invention discloses a radioactive nuclide labeled compound which is caobonyl technetium labeled 2-azomycin composition, a preparation method of the compound and a purpose of the compound. The preparation method of the caobonyl technetium labeled 2-azomycin composition comprises the following steps: firstly synthesizing a ligand NC-PEGn-NIM and heating the ligand and a newly prepared midbody <99m>Tc(CO)3(H2O)3<+>, the pH value of which is regulated to 9 to 10, to obtain the caobonyl technetium labeled 2-azomycin composition. The caobonyl technetium labeled 2-azomycin composition is concentrated in anoxybiotic tumor cells by the targeting function of azomycin and can be used for the SPECT raster display diagnosis of anoxybiotic tumors.

The invention relates to a petalite heat-resistant ceramic wok. The petalite heat-resistant ceramic wok is prepared by firing the following raw materials in parts by weight: 45 to 65 parts of petalite, 15 to 40 parts of spodumene, 12 to 20 parts of quartz, 15 to 20 parts of kaolin, 6 to 9 parts of talc, 5 to 8 parts of microcrystalline ceramic powder, 1 to 3 parts of halloysite nanotubes, 0.5 to 1part of nanometer tungsten carbide powder, 0.5 to 1 part of nanometer technetium oxide powder, 0.3 to 0.5 part of polyacrylamide. The petalite heat-resistant ceramic wok utilizes the cheaper petaliteas a main raw material, and the prepared petalite heat-resistant ceramic wok has good thermal shock resistance, good crack resistance, good wear resistance and good thermal conductivity.

Recycling of isotopically enriched molybdenum metal targets that are suitable for the large scale cyclotron production of 99mTc or 94mTc includes the charged particle irradiation of an enriched molybdenum metal target to produce a technetium isotope, separation of the technetium isotope following irradiation of the molybdenum, re-claiming the molybdenum metal and reformation of the molybdenum target for a further irradiation step. This process may then be repeated. Separation of the technetium isotope preferably is achieved by oxidative dissolution of the molybdenum thereby removing it from a target support plate, and forming molybdate and pertechnetate. The technetium isotope is isolated by various means, such as the ABEC process. To reuse the molybdenum, additional steps of isolating the molybdate and reducing it back to molybdenum metal are required. The recovered molybdenum metal may then be reformed as a target for example by pressing or pressing and sintering, followed by bonding to a target support plate.

The invention discloses a high-technetium acid radical adsorbent as well as a synthesis method and application thereof in radioactive wastewater treatment. The synthesis method comprises the following steps: by taking silver nitrate and tert[4-(1-imidazolyl) phenyl] methane as a raw material and an organic solvent and water as mediums, performing hydrothermal reaction; after the reaction is completed, washing, filtering a reaction liquid, and drying obtained filter cakes, so as to obtain the high-technetium acid radical adsorbent. The high-technetium acid radical adsorbent disclosed by the invention is of a porous three-dimensional unlimited extension structure, and high-technetium acid radicals can be effectively exchanged with free nitrate inside pores, therefore, the radioactive wastewater can be efficiently treated.

Treatment of a radioactive waste stream is provided by adding sodium hydroxide (NaOH) and/or potassium hydroxide (KOH) together with a rapidly dissolving form of silica, e.g., fumed silica or fly ash. Alternatively, the fumed silica can be first dissolved in a NaOH/KOH solution, which is then combined with the waste solution. Adding a binder that can be a mixture of metakaolin (Al₂O₃.2SiO₂), ground blast furnace slag, fly ash, or other additives. Adding an “enhancer” that can be composed of a group of additives that are used to further enhance the immobilization of heavy metals and key radionuclides such as ⁹⁹Tc and ¹²⁹I. An additional step can involve simple mixing of the binder with the activator and enhancer, which can occur in the final waste form container, or in a mixing vessel prior to pumping into the final waste form container, depending on the particular application.

The invention relates to a PUREX process for separating technetium. The PUREX process includes the steps: (1) co-decontamination and co-extraction: co-extracting uranium, plutonium, neptunium and the technetium in spent fuel nitric acid solution into an organic phase and washing co-extraction liquid; (2) plutonium and neptunium reverse extraction: reversely extracting the plutonium and the neptunium in the co-extraction liquid into a water phase by reverse extraction agents S1 containing AHA and then adding uranium supplement extraction agents for supplement extraction to obtain the water phase containing the plutonium and the neptunium and an oil phase containing the uranium and the technetium; (3) technetium reduction and reverse extraction: reducing and reversely extracting the technetium in the oil phase containing the uranium and the technetium into the water phase by reverse extraction agents S2 containing reducing agents and then adding uranium supplement extraction agents for supplement extraction to obtain a water phase containing the technetium and an oil phase containing the uranium, wherein the oil phase containing the uranium enters a subsequent uranium purification process. The neptunium, the plutonium and the technetium are reduced step by step through a step-by-step reduction method, the technetium can be separated out, the trend of elements is simpler and more uniform, all the reducing agents are salt-free reagents, remaining reagents are easily damaged, and the subsequent process is less affected.

A developing apparatus characterized in being constituted to satisfy Equation (1) shown below when an amount of a developer carried by 1 pitch of a carrying member of an auger or the like is designated by notation W(g), a toner amount supplied by 1 pitch during a time period in which the developer carried by 1 pitch passes a supply region of a toner supply roller is designated by notation M(g), a toner concentration of the developer detected by a toner concentration sensor is designated by notation Tc (%), and a mixing limit toner concentration is designated by notation Tmax (%).

(W×(Tc/100)+M)/(W+M)≦Tmax/100   (1)

Provided are a graphite material, which has excellent bonding characteristics to semiconductor and efficiently dissipates heat generated from the semiconductor, and a method for manufacturing such material. The graphite material is provided by adding at least two kinds of elements selected from among silicon, zirconium, calcium, titanium, chromium, manganese, iron, cobalt, nickel, calcium, yttrium, niobium, molybdenum, technetium, ruthenium and compounds containing such elements, and by performing heat treatment. The graphite material is characterized in having a thickness of the 112 face of the graphite crystal of 15 nm or more by X-ray diffraction, and an average heat conductivity of 250 W/(m·K) or more in the three directions of the X, Y and Z axes.