Abstract: Automated sampling and reaction systems and methods of using the same are provided. The automated sampling and reaction system has a microreactor in fluidic communication with an external sampling valve. The external sampling valve is connected to a priming valve and can be configured to draw sample from a reactor or a reactor stream. The microreactor is connected to a reagent valve and an injection valve. The reagent valve can be configured to draw reagent from a reagent reservoir and discharge reagent to the microreactor to react with sample. The priming valve can be configured to draw wash from a wash reservoir and discharge wash to the external sampling valve to move sample from the external sampling valve to the microreactor. The injection valve is in fluidic communication with a column or detector and discharges the secondary sample into a solvent composition stream.

Abstract: Methods and systems directed to the separation of tritium from an aqueous stream are described. The separation method is a multi-stage method that includes a first stage during which tritium of a tritium-contaminated aqueous stream is adsorbed onto a separation phase, a second stage during which the adsorbed tritium is exchanged with hydrogen in a gaseous stream to provide a gaseous stream with a high tritium concentration, and a third stage during which the tritium of the gaseous stream is separated from the gaseous stream as a gaseous tritium product.

Abstract: A method of performing a plurality of synthesis processes of preparing a radiopharmaceutical in series includes carrying out a first synthesis run including the steps of: a) providing water containing fluorine-18; b) trapping the fluorine-18 from the water provided in step a) on an anion exchange material; c) eluting the trapped fluorine-18 from the anion exchange material to a reaction vessel of first radiopharmaceutical synthesis cassette; d) preparing a radiopharmaceutical incorporating the eluted fluorine-18 using the first radiopharmaceutical synthesis cassette; where steps a)-d) are repeated in at least one subsequent run using another radiopharmaceutical synthesis cassette; and where the method includes a reconditioning step of the anion exchange material between two consecutive runs. A device for performing this method and a cassette for use in the device are also disclosed.

Abstract: The present invention relates to an automated radiosynthesis device adapted for the addition of multiple additional components. The automated radiosynthesis device of the invention enables a wider range of radiochemical synthetic processes to be carried out in an automated fashion.

Abstract: Microfluidic radiopharmaceutical production system and process for synthesizing per run approximately, but not less than, ten (10) unit doses of radiopharmaceutical biomarker for use in positron emission tomography (PET). A radioisotope from an accelerator or other radioisotope generator is introduced into a reaction vessel, along with organic and aqueous reagents, and the mixture heated to synthesize a solution of a pre-selected radiopharmaceutical. The solution is purified by passing through a combination of solid phase extraction purification components, trap and release components, and a filter. The synthesis process reduces waste and allows for production of biomarker radiopharmaceuticals on site and close to the location where the unit dose will be administered to the patient.

Abstract: A closed system chemical handling and delivery system includes an enclosure having a sealable opening accommodating the ingress and egress of chemical containers with an interior of the enclosure, a glove opening formed in the enclosure to which a glove is attached to and extends into the interior of the enclosure, a viewing window coupled to the enclosure providing a view into the interior of the enclosure, a chemical delivery drain in fluid communication with the interior of the enclosure, and a mixing valve in selective fluid communication with the chemical delivery drain.

Abstract: A method of using hydrogen- or lithium-containing manganese oxide having a spinel crystal structure as a tritium adsorbent to trap tritium from tritium-containing water makes it possible to inexpensively separate tritium from water.

Abstract: A system and process are disclosed for dissolution of solids and “difficult-to-dissolve” solids. A solid sample may be ablated in an ablation device to generate nanoscale particles. Nanoparticles may then swept into a coupled plasma device operating at atmospheric pressure where the solid nanoparticles are atomized. The plasma exhaust may be delivered directly into an aqueous fluid to form a solution containing the atomized and dissolved solids. The composition of the resulting solution reflects the composition of the original solid sample.

Abstract: A transportable and modular field-deployable hydrolysis system for neutralizing toxic chemical agents is described. The system comprises a transportable chemical process plant that is capable of operating in a remote location without significant site infrastructure. The system is also capable of operating in a maritime, shipboard environment. A flexible design allows processing of chemical agents in both batch and continuous flow modes, as well as collection and accumulation of agents from a variety of containers whose form and size may not be known until the system is on-site.

Abstract: A plasma array apparatus for processing starting materials is described and taught. The apparatus uses a plasma sheet(s) to heat starting materials in a chamber under low oxygen conditions. This results in a chemical dissociation of the starting materials rather than a burning of the contained materials. Elemental components, such as hydrogen, carbon, and molecules, such as residual hydrocarbons, of the dissociated starting materials can then be separated in such a way as to produce viable amounts of a synthetic gas primarily composed of hydrogen (h-syngas). This is accomplished with a minimal release of harmful byproducts such as carbon dioxide, a greenhouse gas. The apparatus may be used on a variety of starting materials including, but not limited to, natural gas, coal, liquid petroleum products, and a variety of biomass containing products such as biodiesel and bioethanol.

Abstract: A rotating vacuum heat treatment equipment, applicable for heat treatment of rare earth permanent magnetic devices, hydrogen pulverization of rare earth permanent magnetic alloy, and heat treatment of mechanical electronic components, mainly comprises: a vacuum unit, a gas cooling device, and a vacuum furnace, wherein an insulating layer is provided in the vacuum furnace, a heater is provided in the insulating layer, a rotating cylinder is provided in the heater, a nozzle, connected with pipelines of the gas cooling device, is provided on the insulating layer, and cooled gas is sprayed to the rotating cylinder via the nozzle.

Abstract: Method and apparatus for synthesizing an F-18 labeled radioactive pharmaceutical by labeling a precursor with an F-18 radioactive isotope, by reacting the labeled precursor to obtain a labeled pharmaceutical, by separating impurities from the labeled pharmaceutical to provide a purified labeled pharmaceutical, and by collecting the purified labeled pharmaceutical. The apparatus includes a labeling cartridge that contains the precursor, receives the isotope, and causes a labeling reaction to provide the labeled precursor; a synthesizing container that receives the labeled precursor, receives at least one reagent effective to hydrolyze the labeled precursor, and within which the labeled precursor undergoes a hydrolysis reaction to provide the labeled pharmaceutical; and a separation cartridge that receives the labeled pharmaceutical, and contains a polymer compound that separates impurities into polar compounds and nonpolar compounds to provide the purified labeled pharmaceutical.

Abstract: Disclosed herein are methods of performing microchemical reactions and electro-wetting-on-dielectric devices (EWOD devices) for use in performing those reactions. These devices and method are particularly suited for preparing radiochemical compounds, particularly compounds containing 18F.

Abstract: A method of stabilizing a fuel containing a reactive sodium metal may include puncturing a cladding of a fuel pin enclosing the fuel containing the reactive sodium metal to form an injection passage and an extraction passage. A reaction gas may be injected into the fuel pin through the injection passage to react with the reactive sodium metal to form a stable sodium compound. A ratio of a product gas and a remaining quantity of the reaction gas exiting the fuel pin through the extraction passage is subsequently measured, wherein the product gas is a reaction product of the reaction gas and the reactive sodium metal within the fuel pin. Once the measured ratio indicates that a reaction between the reaction gas and the reactive sodium metal is complete, the injection passage and the extraction passage are sealed so as to confine the stable sodium compound within the fuel pin.

Abstract: The present disclosure sets forth incorporating microfluidic chips Interfaces for use with digital microfluidic processes. Methods and devices according to the present disclosure utilize compact, integrated platforms that interface with a chip upstream and downstream of the reaction, as well as between intermediate reaction steps if needed. In some embodiments these interfaces are automated, including automation of a multiple reagent process. Various reagent delivery systems and methods are also disclosed.

Abstract: The present invention refers to a method and related plants for removing, by means of redox reactions, the 137Cs from polluted EAF dusts, with an initial average value of radioactivity concentration either higher or lower than 10,000 Bq/kg, the decontamination from the 137Cs initially present in the EAF dusts having a yield of 98%-100%; the present invention also refers to the use of chemical-physical destabilisation agents, by means of redox reactions, for obtaining EAF dusts decontaminated from 137Cs.

Abstract: The present invention relates to a method of purification of [18F]-fluciclatide via solid phase extraction (SPE). The method is amenable to automation, and is suitable for use in conjunction with automated synthesizer apparatus—especially cassette-based synthesizers. Also provided are cassettes for carrying out the purification method.

Abstract: A kit for producing a radiopharmaceutical, having: a cation exchange cartridge; a reaction vial having a marker precursor; a solution vial having a solvent; an elution vial having a sterile solution including common salt (NaCl) and hydrochloric acid (HCl); and a buffer salt. A method for producing a radiopharmaceutical is also disclosed.

Abstract: The invention relates to a device for the preparation of radiochemical compounds. It is provided that the device comprises at least a reaction module, a dosing module, and a storage module, wherein the reaction module has at least one reaction vessel having a closable opening through which substances needed for the preparation of a predetermined radiochemical compound can be introduced into the reaction vessel of the reaction module and through which the prepared radiochemical compound can be removed from the reaction vessel of the reaction module; the dosing module has at least one pipetting head which can be moved relative to the storage module and the reaction module and in x, y, and z directions and also has at least one dosing unit; and at least one reservoir for one of the substances needed for the preparation of the respective radiochemical compound is formed in the storage module.

Abstract: A set for producing a radiopharmaceutical, having a cation exchange cartridge; a reaction vial containing a precursor marker; a solution vial containing a solvent; an elution vial containing a sterile solution that includes sodium chloride (NaCl) and hydrochloric acid (HCl); a buffer salt. A method for producing a radiopharmaceutical is also disclosed.

Abstract: A set for producing a radiopharmaceutical, having a cation exchange cartridge; a reaction vial containing a precursor marker; a solution vial containing a solvent; an elution vial containing a sterile solution that includes sodium chloride (NaCl) and hydrochloric acid (HCl); a buffer salt. A method for producing a radiopharmaceutical is also disclosed.

Abstract: A set for producing a radiopharmaceutical, having: a cation exchange cartridge; a reaction vial containing a precursor marker; a solution vial containing a solvent; an elution vial containing a sterile solution that includes sodium chloride (NaCl) and hydrochloric acid (HCl); a buffer salt. A method for producing a radiopharmaceutical is also disclosed.

Abstract: A standalone radiopharmaceutical preparation hotcell for preparing a radiopharmaceutical includes a housing and a plurality of compartments defined within the housing. The plurality of compartments including at least a pharmaceutical synthesizing and dispensing compartment and a different second compartment, the synthesizing and dispensing compartment being maintained at a first pressure and the second compartment being maintained at a different second pressure using a compartment pressurization system.

Abstract: The invention relates to a compressed-air device for controlling valves comprising, in a longitudinal direction, a first vane-type rotary cylinder (1) having a front face (2) as well as a back face (4), said front face (2) being provided with a rotatable head (3), and a second vane-type rotary cylinder (10) having a front face (11) and a back face, said first (1) and second (10) cylinders each being supplied with compressed air by means of a compressed air valve connected to two ports (7, 8; 14, 15) on each of said first and second cylinders.

Abstract: The present invention relates to an apparatus for synthesizing F-18 labeled radioactive pharmaceutical. The apparatus for synthesizing F-18 labeled radioactive pharmaceutical includes an F-18 radioactive isotope supplier, a reagent supplier, a polymer precursor cartridge, a first heating unit, a polymer compound cartridge, a synthesizing container, a second heating unit, a water liquid container, a transmitting gas supplier, a cleansing liquid supplier, a connection tube, a plurality of control valves, and a controller.

Abstract: A system for extracting uranium from wet-process phosphoric acid (WPA), includes an ion exchange resin or solvent extractor for separating uranium from WPA to produce a loaded uranium solution stream and a uranium depleted WPA stream. An ion exchange resin is positioned to receive the loaded uranium solution stream and bind uranium species thereto. An anion solution stream is positioned to feed a solution comprising anions onto the ion exchange resin to form a loaded uranium eluant stream. The loaded uranium eluant stream may then be treated to provide a uranium containing product.

Abstract: A microreactor for preparing a radiolabeled complex or a biomolecule conjugate comprises a microchannel for fluid flow, where the microchannel comprises a mixing portion comprising one or more passive mixing elements, and a reservoir for incubating a mixed fluid. The reservoir is in fluid communication with the microchannel and is disposed downstream of the mixing portion. A method of preparing a radiolabeled complex includes flowing a radiometal solution comprising a metallic radionuclide through a downstream mixing portion of a microchannel, where the downstream mixing portion includes one or more passive mixing elements, and flowing a ligand solution comprising a bifunctional chelator through the downstream mixing portion. The ligand solution and the radiometal solution are passively mixed while in the downstream mixing portion to initiate a chelation reaction between the metallic radionuclide and the bifunctional chelator. The chelation reaction is completed to form a radiolabeled complex.

Abstract: The present invention relates to a disposable module (100) for use in a device (300) for synthesizing radiopharmaceutical products starting with chemical reagents, said disposable module (100) comprising: a supporting plate (101) comprising rigid connection means (114) to at least one flask of chemical reagents (102, 103, 104, 105) in solution in a solvent, and a reactor (106); interface means (115) with a fixed module of said synthesis device (300), in contact with or integrated into said supporting plate (101), said interface means comprising at least one valve (V1-V8) and/or at least one fluid inlet (E1, E2) and/or at least one fluid outlet (O1, O2, O3); at least one conduit (1-20) connected to said at least one valve (V1-V8) or to said at least one fluid inlet (E1, E2) or to said at least one fluid outlet (O1, O2, O3), characterized in that at least one of said conduits (1-20) is integrated into the body of the disposable module (100).

Abstract: The present invention relates to an automatic system for synthesizing iodine-123 meta-iodobenzylguanidine (123I-MIBG), which comprises a first reactor for subjecting radioactive iodine-containing sodium iodide and meta-iodobenzylguanidine (MIBG) sulfate to an iodine-iodine exchange reaction to obtain radioactive iodine labeled MIBG; a purification unit for purifying the iodine labeled MIBG; and a second reactor for substituting a solvent used in purification with a phosphate buffer to obtain a phosphate solution containing 123I-MIBG. The present invention also relates to an automatic device for dispensing 123I-MIBG, which comprises the automatic system for synthesizing 123I-MIBG, a radioactivity measuring unit, and a dispensing and packing unit.

Abstract: A modular chemical production system includes multiple modules for performing a chemical reaction, particularly of radiochemical compounds, from a remote location. One embodiment comprises a reaction vessel including a moveable heat source with the position thereof relative to the reaction vessel being controllable from a remote position. Alternatively the heat source may be fixed in location and the reaction vial is moveable into and out of the heat source. The reaction vessel has one or more sealing plugs, the positioning of which in relationship to the reaction vessel is controllable from a remote position. Also the one or more reaction vessel sealing plugs can include one or more conduits there through for delivery of reactants, gases at atmospheric or an elevated pressure, inert gases, drawing a vacuum and removal of reaction end products to and from the reaction vial, the reaction vial with sealing plug in position being operable at elevated pressures.

Abstract: An apparatus and method for the granulation of radioactive waste in which a preprocessing method for the vitrification of radioactive waste is simplified to conform to onsite conditions of a nuclear power plant, additives are improved, and pellets suitable for vitrification are manufactured. The apparatus for the granulation of radioactive waste includes: a body frame having an inlet and an outlet; a hopper supplying the radioactive waste to be transferred and fed through the inlet; a feeder transferring/supplying the radioactive waste supplied to a specific position and in a certain quantity; a stirrer pulverizing/mixing lumps of the radioactive waste supplied; an additive supply part supplying a lubricant to the radioactive waste fed into the stirrer; and a pellet press pressing the radioactive waste fed through the feeder into a pellet shape and discharging the pellet through the outlet.

Abstract: Disclosed is a method for treating a radioactive organic waste, the radioactive organic waste including a cation exchange resin adsorbing radionuclide ions, the method including the step of bringing the radioactive organic waste into contact with an organic acid salt aqueous solution containing an organic acid salt and whereby desorbing the radionuclide ions from the cation exchange resin, in which the organic acid salt contained in the organic acid salt aqueous solution includes a cation that is more readily adsorbable by the cation exchange resin than hydrogen ion is. This enables reduction in concentration of a radioactive substance in the radioactive organic waste and reduction in amount of a high-dose radioactive waste.

Abstract: An automated synthesis device to produce Re-188-BMEDA solution including: a plurality of reagent vials, three-way solenoid valves, gel filtration columns and micro pumps, and a reaction vial, a product vial, a temporary storage vial, a filter membrane, and a waste vial, wherein the plurality of reagent vials include first reagent vial and second reagent vials being connected to the reaction vial through first micro pump, the third reagent vial and fourth reagent vial being connected to the reaction vial through second micro pump, fifth reagent vial being connected to the reaction vial through third micro pump, and sixth reagent vial being connected to the temporary storage vial through fourth micro pump, wherein the reaction vial is connected to the plurality of gel filtration columns through the micro-pump, respectively. The automated synthesis device is operable with program to upgrade yield and avoid contamination.

Abstract: There are provided an apparatus and method for separating radioactive nuclides from a waste salt and recovering a refined salt, which are able to maximize process efficiency and operating efficiency of a process of regenerating a waste salt produced during a pyrochemical process of used nuclear fuel by converting the waste salt into a thermally stable form and distilling the waste salt under a reduced pressure using a single apparatus having two top covers which are mountable to replace radioactive nuclides included in the waste salt, and highly improve applicability and utility in a remote operation facility for disposal of a radioactive waste by further simplifying operation/handling compared with conventional processes.

Abstract: The invention provides an automatic synthesizer apparatus and method for producing radiopharmaceutical tumor imaging agent Gallium-68-DOTATATE with one button control process to effectively isolate the medication in vials from the contamination of environment and manual operations, saving the costs of investment in production with alleviation of the critical standard required for the environmental equipments to be used for production.

Abstract: The present invention provides a simple and inexpensive method for removing metal and other impurities in a radioisotope solution. The invention further includes the development of a new parent/daughter generator system for collecting the daughter isotope in a concentrated solution.

Abstract: This invention relates to the miniaturisation of radiosyntheses onto microfabricated devices, and in particular to use of microfabricated devices for radiosynthesis, isolation, and analysis of radiotracers for use in Positron Emission Tomography (PET).

Abstract: A stacked reactor vessel provides two separate reaction vessel compartments for performing chemical reactions and is particularly suited to multi-step chemical reactions and for incorporation into a cassette for automated operation.

Abstract: A process for extracting Cs-137 from i) an acidic solution obtained by dissolving an irradiated solid target comprising uranium, ii) an acidic solution comprising uranium which has previously been irradiated in a nuclear reactor, or iii) an acidic solution comprising uranium which has been used as reactor fuel in a homogeneous reactor, the acidic solution i), ii) or iii) having been treated to harvest Mo-99, wherein the process comprises contacting the treated acidic solution with an adsorbent comprising ammonium molybdophosphate (AMP). In an embodiment, the AMP is combined with an organic or inorganic polymeric support, for example AMP synthesised within hollow aluminosilicate microspheres (AMP-C).

Abstract: A process for manufacturing magnetic and/or radioactive metal nanoparticles, the process comprising: preparing an electrolyte solution including metal ions and a stabilizer; generating a plasma at an interface of the electrolyte solution at atmospheric pressure; and recovering magnetic and/or radioactive metal nanoparticles. The magnetic metal nanoparticles can comprise magnetoradioactive nanoparticles. The magnetic metal nanoparticles can be used as MRI contrast agents and the magnetoradioactive nanoparticles can also be used as contrast agents and for dual PET/MRI applications. It also relates to a multi-plasma apparatus for synthesizing nanoparticles.

Abstract: A vol-oxidizer for spent nuclear fuel is provided. The vol-oxidizer includes a reactor module in which the spent nuclear fuel is put and oxidized; a heating module to heat the reactor module to a high temperature; a utility module to control an inner state of the reactor module, being connected with the reactor module; a support module to support the heating module and the reactor module; a drive module to supply a driving force for transferring the spent nuclear fuel within the reactor module; a valve module to control discharge of the spent nuclear fuel being oxidized in the reactor module; and a collecting container module to collect the spent nuclear fuel being oxidized and discharged from the reactor module. The respective modules are assembled and disassembled with respect to one another.

Abstract: The invention is related a novel structure for Ga-68 radionuclide generator. It allows two washing solutions to pass through two Ge-68 absorbents to wash out different chemical forms of Ga-68 nuclide. The invention comprises the first method that will withdraw hydrochloric acid solution from the washing bottle and pass it through inorganic resin absorbing column to produce the radioisotope solution of Ga-68 gallium chloride, and the second method that will allow the radioisotope solution of Ga-68 gallium citrate to pass the organic resin absorbing column and then the silica-gel cartridge, and be washed by the hydrochloric acid solution to obtain the radioisotope solution of Ga-68 gallium chloride.

Abstract: The present invention relates to 18F radio-chemistry and in particular to a method for synthesising radiofluorinated amides and amines. The method of the invention has particular application in the radiosynthesis of a variety of 18F-labelled positron emission tomography (PET) tracers.

Abstract: A process for chemical stabilization of a uranium carbide compound having formula: UCx+yC with x?1 or 2 and y>0, x and y being true numbers, placed in a stabilization chamber, comprises: a rise in chamber internal temperature for “oxidation” of the compound based on uranium carbide between approximately 380° C. and 550° C., the chamber being fed with a neutral gas; isothermal oxidative treatment at the oxidation temperature, the chamber being placed under O2 partial pressure; controlling completion of stabilization of the compound, comprising monitoring the amount of molecular oxygen consumed and/or carbon dioxide or carbon dioxide and carbon monoxide given off, until achievement of an input set-point value for the amount of molecular oxygen, of a minimum threshold value for the amount of carbon dioxide or minimum threshold values for the carbon dioxide and carbon monoxide. A device implements the process.

Abstract: A method is provided for the decontamination of radioactive carbonaceous material, such as graphite, in which an injection of steam is planned into the material, concurrent with a first roasting thermal treatment of the material at a temperature between 1200° C. and 1500° C. Advantageously, the first treatment may be followed by a second treatment at a lower temperature with an injection of carbon oxide for oxidation according to the Boudouard reaction.

Abstract: An automated synthesis system for iodine-123-IBZM nuclear medicine includes a control/display means, a reactant supply means connecting to the control/display means; an adsorption means connecting to the control/display means and to the reactant supply means, an oxidation means connecting the control/display means, the reactant supply means and the adsorption means, a product collection means connecting to the control/display means, the reactant supply means, the adsorption means and the oxidation means; a waste liquid collection means connecting to the control/display means, the adsorption means and the product collection means, and a gas filtration means connecting the control/display means, the oxidation means and the product collection means.

Abstract: The Centrifugal Fluid Ring Reactor employs a centrifugal impeller and a fluid barrier to mix multi-phase fluids and repeatedly move the mixture through a reaction zone, where the mixture contacts catalysts and/or is subjected to electromagnetic, mechanical, nuclear, or sonic energy to create ions, free radicals or activated molecules, which initiate or promote a desired reaction. It can be used to convert carbon dioxide, methane and other gaseous carbon sources into liquid fuel at ambient temperature and pressure.

Abstract: The invention relates to a detritiation device comprising i) a furnace (1) for melting tritiated waste, said furnace comprising a hearth for receiving tritiated waste and a bubbling device for introducing a hydrogenated bubbling gas into the hearth during the melting and treatment of the tritiated waste in the furnace (1), and ii) a catalytic reactor with a quadrupole membrane (2) for treating the gas resulting from the melting and treatment of the tritiated waste in the furnace (1), said reactor comprising a membrane (20) for separating two flows of gas, the membrane (20) being permeable to the hydrogen isotopes. The invention also relates to an associated detritiation method.

Abstract: The present invention provides a method for the preparation of a radiolabeled guanidine derivative, in particular wherein the radiolabeled guanidine derivative is a positron emission tomography (PET) tracer. Certain intermediates useful in said method are also provided, as well as means for carrying out said method in an automated fashion. The method of the invention provides advantages over known methods for the preparation of radiolabeled guanidine derivatives.

Abstract: Provided by the present invention is a novel method for obtaining an 18F-labelled compound wherein said compound comprises an 18F-labelled pyridyl ring. The method of the invention is advantageous over the prior art methods as it provides these compounds in higher radiochemical yields than have been possible with previous methods. Also provided by the present invention is an 18F-labelled synthon useful in the method of the invention.