Abstract: A system for chemically decontaminating radioactive material.

Abstract: The present invention relates to an automatic radioactivity analyzer of mixed liquid beta emitter which comprises: a sample preparation part (1, 2, 3, 4, 5, 6, and 7) for extracting a liquid sample from liquid-phase radioactive nuclear wastes; a sample injection part (9 and 10), including a sample transportation part for transporting a bottled sample to a radioactivity detection part to perform measurement; the radioactivity detection part (11) including two photon multiplier tubes; an exterior gamma-ray source injection part (12) for compensating for measurement efficiency according to quenching effects; a signal processing part (13), including a pre-amplifier circuit (14), a high-voltage generator circuit (15), an analogue-to-digital converter circuit (21), and a digital signal processor (DSP) (24), for generating beta spectrums by the aid of a fast coincidence counter (20) and a multi-channel analyzer (22); a main control PC (25) and a graphic user interface (GUI) program (29) for remotely automatically me

Abstract: An apparatus for treating polymeric materials comprises a treatment chamber adapted to maintain a selected atmosphere; a means for supporting the polymeric material within the chamber; and, a source of plasma-derived gas containing at least one reactive oxidative species whereby the polymer is stabilized and cross linked through exposure to the oxidative species in the chamber at a selected temperature. The polymer may be directly exposed to the plasma, or alternatively, the plasma may be established in a separate volume from which the reactive species may be extracted and introduced into the vicinity of the polymer. The apparatus may be configured for either batch-type or continuous-type processing. The apparatus and method are especially useful for preparing polymer fibers, particularly PAN fibers, for later carbonization treatments.

Abstract: The invention relates to an apparatus for preparing a small amount of a radioactive substance combination, including a one-part body, a mixing device integrated in the body and adapted to receive a small amount of chemical substances, and at least one receptacle integrated in the body and connected to the mixing device and adapted to hold a small amount of a chemical substance.

Abstract: The invention relates to methods and apparatus for drying [18F]fluoride which comprises (i) passing a [18F]fluoride solution comprising water, a solvent, [18F]fluoride, and a cationic counterion through a narrow bore vessel at elevated temperature such that the water and solvent are vaporised forming a vaporised component, and (ii) collecting the resulting vaporised component by condensing into a collection vessel.

Abstract: Disclosed is a reaction device including: a reaction device body including a reaction section in which a reactant reacts; and a first container to house the reaction device body, wherein the first container includes a radiation transmitting region through which radiation from the reaction device body transmits.

Abstract: An apparatus for the removal of uranium from a body of material is provided. The apparatus has at least one ultrasonic extractor, having a bottom and a top. The at least one ultrasonic extractor is configured to accept solids at the bottom and acid at the top, and has a mixing screw and at least one source of ultrasonic energy. The mixing screw is configured to transport the solids in a direction countercurrent to the acid in the at least one ultrasonic extractor; and the source of ultrasonic energy is configured to impart ultrasonic energy into the solids and the acid, as the solids and the acid traverse the at least one ultrasonic extractor countercurrently.

Abstract: A device for producing a fluid containing a radioactive constituent, comprising a shielded chamber (5) with an opening for receiving an isotope container (6) housing a radioactive isotope (7); a chamber closure (18) adapted for cooperating with and closing the chamber opening; a first fluid port comprising a first hollow needle projecting into the shielded chamber from the chamber closure for fluid communication with the isotope container; a second fluid port comprising a second hollow needle projecting into the shielded chamber from the closed end of the chamber opposite the chamber closure for fluid communication with the isotope container; first and second compressible buffers (28, 29) mounted so as to surround at least partially the respective first and second hollow needles (12, 13), each buffer providing an outer surface for contact with opposed ends of the isotope container; and a spacer of a predetermined thickness associated with one or each of the first and second compressible buffers for determinin

Abstract: This invention relates to a waste treatment furnace and method comprising: Generating a molten metal bed, which moves in a forward direction, such as to define a closed circuit in a cyclical and continuous manner, the surface of said bed comprising at least one essentially-slag-free segment. Loading waste onto the aforementioned essentially-slag-free segment, the waste being dragged by the molten metal bed such that it floats in the mentioned forward direction. Retaining the waste on the surface of the molten metal bed as it moves in the mentioned forward direction. Treating the waste under the effect of the constant and continuous heat exchange generated by the movement of the molten metal bed beneath the waste retained thereon.

Abstract: Methods and reagents for photo-initiated carbonylation with carbon-isotope labeled carbon monoxide using amines and alkyl/aryl iodides are provided. The resultant carbon-isotope labeled amides are useful as radiopharmaceuticals, especially for use in Positron Emission Tomography (PET). Associated kits for PET studies are also provided.

Abstract: A method of separating isotopes from a mixture containing at least two isotopes in a solution is disclosed. A first isotope is precipitated and is collected from the solution. A daughter isotope is generated and collected from the first isotope. The invention includes a method of producing an actinium-225/bismuth-213 product from a material containing thorium-229 and thorium-232. A solution is formed containing nitric acid and the material containing thorium-229 and thorium-232, and iodate is added to form a thorium iodate precipitate. A supernatant is separated from the thorium iodate precipitate and a second volume of nitric acid is added to the thorium iodate precipitate. The thorium iodate precipitate is stored and a decay product comprising actinium-225 and bismuth-213 is generated in the second volume of nitric acid, which is then separated from the thorium iodate precipitate, filtered, and treated using at least one chromatographic procedure.

Abstract: Methods and reagents for photo-initiated carbonylation with carbon-isotope labeled carbon monoxide using weakly nucleophilic amines and alkyl/aryl iodides are provided. The resultant carbon-isotope labeled amides are useful as radiopharmaceuticals, especially for use in Positron Emission Tomography (PET). Associated kits for PET studies are also provided.

Abstract: The present invention provides an automated method for the preparation of 99mTc radiopharmaceutical compositions, together with disposable cassettes for use in the method. The use of an automated synthesizer apparatus in the preparation of 99mTc radiopharmaceuticals is also described. Also described is the use of kits for the preparation of 99mTc radiopharmaceuticals in the method and disposable cassettes of the present invention.

Abstract: The invention is directed to improved containers for pharmaceuticals and any tubing and tubing connectors associated therewith, particularly containers for pharmaceuticals which are irradiated, heated or otherwise subjected to increased pressure. In a preferred embodiment, the invention is directed to an improved container for use in a radioisotope generator, such as a rubidium-82 generator.

Abstract: Methods for removing nuclear waste from a component are provided. In one embodiment, the method includes the steps of supplying oxalic acid to the nuclear waste on the component to form an oxalic acid/waste solution, feeding the oxalic acid/waste solution from the component, feeding an oxidant to the oxalic acid/waste solution to form carbon-dioxide, water and a precipitate, and separating the precipitate from the water. A system for removing nuclear waste is also provided.

Abstract: A method of producing [18F]F2 from [18F] fluoride through a plasma induced scrambling procedure is provided. The present invention also provides an apparatus for preparing [18F]F2 from [18F] fluoride in a plasma induced scrambling procedure. Kit claims for preparing [18F]F2 from [18F] fluoride in a plasma induced scrambling procedure as well as method of use and use of claims for preparing [18F]F2 from [18F] fluoride through a plasma induced scrambling procedure are also provided.

Abstract: Methods and reagents for photo-initiated carbonylation with carbon-isotope labeled carbon monoxide using amines and alkyl/aryl iodides are provided. The resultant carbon-isotope labeled amides are useful as radiopharmaceuticals, especially for use in Positron Emission Tomography (PET). Associated kits for PET studies are also provided.

Abstract: A vol-oxidizer of spent nuclear fuel, the spent nuclear fuel is injected to a reaction portion, the reaction portion is connected to a driving portion and oxidizes the spent nuclear fuel by rotating and back-rotating the spent nuclear fuel. The oxidized powder of the spent nuclear fuel is gathered in a discharge portion located in a lower portion of the reaction portion. By providing minute powder particles for recycling and a post process of the spent nuclear fuel, even though a size of an apparatus is small, processing a large amount is possible. Time required for oxidation can be reduced, and the powder is readily discharged by gravity since the apparatus is vertically configured.

Abstract: Methods and devices for a fully automated synthesis of radioactive compounds for imaging, such as by positron emission tomography (PET), in a fast, efficient and compact manner are disclosed. In particular, the various embodiments of the present invention provide an automated, stand-alone, hands-free operation of the entire radiosynthesis cycle on a microfluidic device with unrestricted gas flow through the reactor, starting with target water and yielding purified PET radiotracer within a period of time shorter than conventional chemistry systems. Accordingly, one aspect of the present invention is related to a microfluidic chip for radiosynthesis of a radiolabeled compound, comprising a reaction chamber, one or more flow channels connected to the reaction chamber, one or more vents connected to said reaction chamber, and one or more integrated valves to effect flow control in and out of said reaction chamber.

Abstract: Devices for generating and storing ozone. The device includes a tank for containing gas therein; an ozone generator for generating ozone and communicating the ozone with the tank; and at least one valve for admitting gas into the device, holding gas in the device, and discharging gas from the device.

Abstract: The invention relates to a device and a process for nucleophilic fluorination of a substance, especially for synthesis of an 18F-labeled substance for examination using a positron emission tomograph. The device comprises an anion exchange device (102) for extraction of [18F]fluoride ions by means of adsorption from a target fluid, whereby the anion exchange device (102) can be charged via a supply device (101) with the target fluid; and a measurement device (104) with a measurement chamber (103) for measuring initial radioactivity of the [18F]fluoride ions, the anion exchange device (102) being arranged at least partially in the measurement chamber (103) of the measurement device (104). (FIG.

Abstract: A reuse apparatus of eutectic salt waste produced in an electro refining process and a method thereof is a technology that in order to collect the eutectic salt of the eutectic salt waste, oxidizes/precipitates nuclides (rare earth and TRU) within the eutectic salt waste, an oxygen dispersing method is used to perform a layer separation into the eutectic salt layer and the precipitate layer. Then, the precipitate layer and eutectic salt layer are separated and collected, so that the eutectic salt layer is directly reused and the eutectic salt within the precipitates is reused by separating and collecting it using distillation/condensation processes. The reuse apparatus of the eutectic salt waste and a method thereof thereby increases the collecting efficiency of the eutectic salt and allows the compositions of the collected eutectic salt to have the same compositions as the eutectic salt used in the electro refining process.

Abstract: A method and device for reducing positron emitter isotope labeled CO2 to positron emitter isotope labeled CO generally includes introducing a volume of positron emitter isotope labeled CO2 into a first heated reaction vessel comprising a metal oxide, such as Iron (II) Oxide such that the CO2 is reduced to CO upon contact with the Iron (II) Oxide. The volume is then transferred to a second reaction vessel to remove any un-reacted CO2, preferably, via a soda-lime trap. The volume is then transferred to a target, e.g., a storage vessel or subject. The CO2 includes one of [11C] or [15O]. The first reaction vessel is, preferably, heated to a temperature of between 900 and 1000° C., and more preferably, to between 925 and 975° C., and even more preferably, to approximately 950° C. Preferably, the Iron (II) Oxide powdered and has a particle size of about ?10 mesh.

Abstract: A molten metal reactor (10) quickly entrains a feed material in the molten reactant metal (16) and provides the necessary contact between the molten reactant metal and the feed material to effect the desired chemical reduction of the feed material. The reactor (10) includes a unique feed structure (24) adapted to quickly entrain the feed material into the molten reactant metal (16) and then transfer the molten reactant metal, feed material, and initial reaction products into a treatment chamber (12). A majority of the desired reactions occur in the treatment chamber (12). Reaction products and unspent reactant metal are directed from the treatment chamber (12) to an output chamber (14) where reaction products are removed from the reactor. Unspent reactant metal (16) is then transferred to a heating chamber (15) where it is reheated for recycling through the system.

Abstract: The present application relates to microfluidic devices and related technologies, and to chemical processes using such devices. More specifically, the application discloses a fully automated synthesis of radioactive compounds for imaging, such as by positron emission tomography (PET), in a fast, efficient and compact manner. In particular, this application describe an automated, stand-alone, microfluidic instrument for the multi-step chemical synthesis of radiopharmaceuticals, such as probes for PET and a method of using such instruments.

Abstract: The invention describes a method for stripping alumina which is particularly suitable for removal of fluoride from alumina and comprises washing said alumina with an aqueous acid or alkali at elevated temperature. The method may be used for removal of unreacted radiofluoride such as [18F]fluoride from alumina following a radiofluorination reaction. Automated synthesis apparatus and cassettes therefor, which are adapted to perform the method are also claimed.

Abstract: A method of declogging at least one filter of a plant for manufacturing uranium oxide from uranium hexafluoride, including separating, from the wall of the filter, uranium oxyfluoride particles deposited, by a stream of inert gas such as nitrogen, injected into the filter, in a counter-currentwise direction to the flow of hydrofluoric acid.

Abstract: A process for the preparation of 11C methyl iodide comprises coating the internal surface of a first reaction vessel with a solution of lithium aluminium hydride, wherein the first reaction vessel has an internal diameter not greater than about 1.5 mm; introducing 11C carbon dioxide into the first reaction vessel such that it is reduced by the lithium aluminium hydride to give a reduction product; and reacting the reduction product with hydriodic acid.

Abstract: 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.

Abstract: A microfluidic reactor cartridge having glass capillary tubing wound in a coil and surrounded by a ceramic housing capable use in high temperatures and method for using same. In another embodiment, the microfluidic cartridge is a serpentine reactor cartridge with a serpentine microreactor channel formed in a ceramic housing. The serpentine reactor cartridge has an inlet tube attached to its inlet port and an outlet tube attached to its outlet port. The inlet port is a macro/micro interface and the outlet port is a micro/macro interface useful in gas phase reactions where solids must be used to produce a reactant. The method for using a microfluidic reactor cartridge includes two phases, the first phase for producing a radioactive labeled gas such as methyl iodide and the second phase is a methylation reaction.

Abstract: A substance in a condensed state, for example a powdered solid, is in continuous movement in the longitudinal direction (6) of a furnace (4, 5). A reactive gas mixture is brought into contact with the substance in the condensed state. A plurality of samples of the gaseous mixture are removed at a plurality of reference points (14) spaced apart from one another along the longitudinal direction (6) of the furnace (4, 5); each of the gas samples is analyzed outside the furnace to determine the composition of the gas mixture and for each point (14), the extent of a chemical reaction between the condensed substance and the reactive gas mixture is deduced from the composition of the gas mixture at each of the reference points (14). In particular, the apparatus comprises a sampling and injection rod (10) introduced into the furnace (4, 5) and disposed in its longitudinal direction (6).

Abstract: A package and process of using the package for disposal of radioactive cesium and strontium waste capsules. The package comprises a standard Hanford vitrified high-level waste canister as an outer container, which is approximately filled with three components: the first is a monolithic material with a defined cavity having a composite density less than about 3.5 grams per cubic centimeter and a melting temperature above that expected within the disposal package; the second is a frame for limiting relative movement of the capsules; and, the third are components forming an uninterrupted physical contact, thermal conduction pathway from the waste container to the outside of the package. The package includes lids for closing the disposal package. In the method of the invention, the capsules are loaded into position within the monolithic material, encased in thermally conducting material, and then lids are added to close the package.

Abstract: Methods and apparatus for production and use of carbon-isotope monoxide in labeling synthesis are provided. The resultant carbon-isotope labeled reagents are useful as radiopharmaceuticals, especially for use in Positron Emission Tomography (PET).

Abstract: The invention relates to a method and system for the treatment of radioactive wastes produced as a consequence of the operation of nuclear power plants with pressurized water reactors and boron reactivity regulation accompanied by the simultaneous production of environmentally acceptable substances of, for example, borax, calcium-magnesium borates, boron acid and sodium hydroxide solutions.

Abstract: An agitation type powder dissolving apparatus comprises a dissolving tank into which powder of spent nuclear fuel is to be supplied, an agitating member rotatably disposed in the dissolving tank, and rise inhibiting structure, disposed in the dissolving tank above the agitating member, for inhibiting the powder from swirling and rising due to rotation of the agitating member. The rise inhibiting structure is composed of a plurality of fixed blades for causing powder, which would otherwise swirl and rise due to rotation of the agitating member, to move downward. Each fixed blade has a descending slope with respect to a swirling direction during swirling and rising. This dissolving apparatus prevents non-dissolved particles from overflowing.

Abstract: Systems and methods are disclosed for producing customized, predictable and reproducible supplies of radioisotopes using, for example, a reactor housing that is fabricated from a radioactive shielding material and has both an internal volume and a surface that comprises an entry port and an exit port, a chromatographic column that is positioned within said internal volume such that a first end of said column is in fluid communication with said entry port and a second end of said column is in fluid communication with said exit port, and a changeable filter module that is disposed external to said reactor housing and in fluid communication with said exit port.

Abstract: The invention relates to a system for synthesizing radiopharmaceuticals employing one or more single-use integrated kits of materials, valves and vessels fitted to one or more stationary apparatus in the manner that the kit can be safely ejected and disposed of without manual operations. Fluidic connections on the kits are made with flexible tubing that can be inserted into the various components by hand. This, along with the use of flexible configuration rotary valves, makes it possible to configure them to carry out a variety of processes.

Abstract: A method of simply and quickly determining ?-ray releasing nuclides having long half-life without carrying out a chemical separation is provided. By inputting a data of pulses incident to an ?-ray detector in a computer, obtaining time distribution of the incident pulses by using a very short time measuring timer and plotting, and fitting the linear originated in a random event corresponding to the background and the non-linear originated in the correlated events of parent nuclides-progenies by using the least squares method, the whole generating probability P (t) from the parent nuclide to the progeny thereof is obtained. By subtracting the random events portion from the P(t), the correlated events portion is extracted. The radioactivity per unit can be obtained by dividing the extracted correlated events portion by the measured time, the amount of the supplied sample and the counting efficiency.

Abstract: A waste vitrification apparatus (10) having rotatable mixer impeller (16) functioning as a shaft electrode (60) and metallic vessel (14) functioning as a vessel electrode (62). A stream (12) of waste material and vitrifiable material are mixed and melted in the vessel (14) for vitrification. The waste vitrification method converts a feed stream (12) by mixing the feed stream into a glass melt (13) and melting glass batch of the feed stream (12) to form a foamy mass. The stream is dispersed by the impeller (16) to form a foam which is then densified in a settling zone (22), recovered through a spout (24) and solidified in storage containers. Means are provided to adjust the location of the mixing impeller (16) in the vessel (14) to change the depth of the settling zone (22). The impeller (16) is mounted on a drive shaft (18) having a recirculating coolant flow.

Abstract: A depleted UF6 processing plant including a first fluidized bed reactor configured to react depleted UF6 with steam to produce UO2F2 and hydrogen fluoride, a second fluidized bed reactor connected to the first fluidized bed reactor and configured to react the UO2F2 with steam to produce U3O8, hydrogen fluoride and oxygen, a gas cooler configured to cool the hydrogen fluoride generated in the first and second fluidized bed reactors down to 150 to 300° C., and a fluorine fixing reactor containing granular calcium carbonate and connected to the gas cooler to receive the hydrogen fluoride cooled down to 150 to 300° C. from the gas cooler. The fluorine fixing reactor is configured to form granular calcium fluoride from the granular calcium carbonate and the hydrogen fluoride passing through the fluorine fixing reactor.

Abstract: Uranium trioxide is reduced to uranium dioxide using microwave radiation or radiofrequency radiation directed in such a way that the radiation encounters an interface between uranium trioxide and the uranium-containing reduction product without first having passed through that product. By this method, and also using a reducing gas, it is possible to obtain UO2 with an O:U ratio less than 2.04:1.

Abstract: An injection and solidification operation as well as a kneading and solidification operation can be performed by a single facility. A decreased amount of radioactive secondary waste is generated. A solidifying agent paste is prepared by kneading a solidifying agent and additive water. The solidifying agent paste is injected into a solidifying container. The radioactive waste is charged into the solidifying container and kneaded.

Abstract: A fluid processing unit having first and second interleaved flow paths in a cross flow configuration is disclosed. The first flow paths are substantially longer than the second flow paths such that the pressure drop in the second flow paths can be maintained at a relatively low level and temperature variations across the second flow paths are reduced. One or more of the flow paths can be microchannels. When used as a vaporizer and/or superheater, the longer first flow paths include an upstream liquid flow portion and a downstream vapor flow portion of enlarged cross sectional area. A substantial pressure drop is maintained through the upstream liquid flow portion for which one or more tortuous flow channels can be utilized. The unit is a thin panel, having a width substantially less its length or height, and is manufactured together with other thin units in a bonded stack of thin metal sheets. The individual units are then separated from the stack after bonding.

Abstract: In a chemical decontamination apparatus, a catalyst decomposition column in an upstream side of an ion exchange resin column and a hydrogen peroxide injection apparatus in a further upstream side, reduce the amount of waste products caused by a chemical decontaminating agent where a mixed decontaminating agent for a composition trapped in a cation resin column and for a composition trapped in an anion exchange resin are used for the chemical decontaminating agent, selectively decompose the composition trapped in the cation resin column in an inlet side of a cleaning apparatus when radioactive nuclides in the decontaminating agent are cleansed using the cation resin column during decontamination, and decompose both compositions after completion of the decontamination. The chemical decontamination thus selectively decomposes the chemical decontaminating agent, which is a component of the load to the cation resin column.

Abstract: A cooled discharge unit of an apparatuses for processing homogeneous/heterogeneous radioactive wastes with ion-exchange resins. The cooled discharge unit has a discharge pipe, a cooling jacket having a U-shaped form in cross section, a collector for feeding a coolant into the jacket, a discharge gate having a pipe, on one end of which is a cone-shaped tip and on the other end of which is a lid with an aperture.

Abstract: This invention concerns a method and an installation for the treatment of radioactive wastes produced as a consequence of the operation of nuclear power plants with pressurized water reactors and boron reactivity regulation and will take place for the production of substances like borax with environmentally allowed content of radioactive isotopes that contains only the cesium isotopes with maximum total concentration of 800 Bq in one kilogram of borax; calcium, magnesium or calcium-magnesium borates with environmentally allowed content of radioactive isotopes; boron acid solution with environmentally allowed content of radioactive isotopes; sodium hydroxide solution containing only the cesium isotopes with maximum total concentration of 800 Bq in one kilogram sodium hydroxide; radioactive waste containing under 5 g/l of boron acid.

Abstract: An injection and solidification operation as well as a kneading and solidification operation can be performed by a single facility. A decreased amount of radioactive secondary waste is generated. A solidifying agent paste is prepared by kneading a solidifying agent and additive water. The solidifying agent paste is injected into a solidifying container. The radioactive waste is charged into the solidifying container and kneaded.

Abstract: This invention is provided for improvement of corrosion-resistant property of a crucible and for promotion of safety in a pyrochemical reprocessing method for the spent nuclear fuel. The spent nuclear fuel is dissolved in a molten salt placed in the crucible. In a pyrochemical reprocessing method, the nuclear fuel is deposited, and the crucible (2) is heated by induction heating. Cooling media (5, 6) are supplied to cool down, and a molten salt layer (7) is maintained by keeping balance between the heating and the cooling, and a solidified salt layer (8) is formed on inner wall surface of the crucible.

Abstract: An element for ascertaining radiation dosage comprising: a support on which is disposed a coated layer, said coated layer comprising a binder and alanine; wherein the alanine, upon exposure to ionizing radiation, produces radicals that remain stable for long periods.

Abstract: An agitation type powder dissolving apparatus for reprocessing spent nuclear fuel is provided. The apparatus comprises a dissolving tank (1) to which powder of spent nuclear fuel is supplied, an agitating member (3) rotatably disposed in the dissolving tank; and rise inhibiting means, disposed in the dissolving tank above the agitating member, for inhibiting the powder from swirling and rising due to the rotation of the agitating member. The rise inhibiting means is composed of a plurality of fixed blades (11) for causing the powder which would otherwise swirl and rise due to the rotation of the agitating member to move downward. The fixed blade has a descending slope with respect to a swirling direction in swirling and rising. This dissolving apparatus effectively prevents the non-dissolved particles from overflowing, thereby providing improvement in the speed with which spent nuclear fuel is reprocessed and in the ability to carry out the nuclear fuel cycle process.