Abstract: A fluid collecting apparatus includes a housing, a gripping member, an inlet, and an outlet. The housing includes a chamber. The gripping member is movable within the chamber, extendable toward or retractable away from a tank, and is configured to hold a computing device. The inlet is communicable with the chamber and configured to deliver a gas into the chamber. The outlet is communicable with the chamber and configured to discharge the gas out of the chamber. A method of operating a cooling system includes receiving the tank, a coolant held by the tank, and a computing device immersed in the coolant, disposing the fluid collecting apparatus over the tank, moving the computing device into the chamber by the gripping member; supplying a gas from the inlet to be blown against the computing device; and discharging the gas and a vaporized coolant out of the chamber through the outlet.

Abstract: A nuclear fuel storage cask includes an outer shell having a length extending from a first end to a second end of the outer shell, the outer shell defining an inner cavity circumscribed by the outer shell, an outer perimeter extending around the outer shell, an inner perimeter positioned inward from the outer perimeter, and a cooling circuit extending along the length of the outer shell, the cooling circuit including an inner passage, and an outer passage, a coolant positioned within the cooling circuit, where the coolant is configured to move through the inner passage, absorbing heat from the inner cavity of the outer shell, and the coolant is configured to move through the outer passage, dissipating heat through the outer perimeter of the outer shell, and a lid coupled the outer shell, where the lid covers the inner cavity of the outer shell.

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: 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: Macro- and microfluidic devices and related technologies, and chemical processes using such devices. More specifically, the devices may be used for a fully automated synthesis of radioactive compounds for imaging, such as by positron emission tomography (PET), in an efficient, compact and safe to the operator manner. In particular, embodiments of the present invention relate to an automated, multi-run, microfluidic instrument for the multi-step synthesis of radiopharmaceuticals, such as PET probes, comprising a remote shielded mini-cell containing radiation-handing components.

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: Disclosed herein is provided an evaporator/calciner in which hazardous materials, such as radioactive liquids, are converted into chemically stable, solid forms by evaporating, drying and calcination within a single vessel, that can then be sealed and used for long term storage.

Abstract: An apparatus and system for separating remaining powder of hulls includes a first remaining powder separating unit to be supplied with hulls of a spent nuclear fuel subjected to a high-temperature oxidation, and to include a first brush for separating remaining powder of the hulls; a hull alignment unit to be supplied with the hulls from the first remaining powder separating unit, and to align the hulls; a second remaining powder separating unit to be supplied with the aligned hulls from the hull alignment unit, and to include a second brush for separating remaining powder adhered on an inner peripheral surface of the hulls; and a third remaining powder separating unit to be supplied with the hulls from the second remaining powder separating unit, and to separate the remaining powder remaining on the inner/outer peripheral surface of the hulls by using air.

Abstract: Disclosed herein is provided an evaporator/calciner in which hazardous materials, such as radioactive liquids, are converted into chemically stable, solid forms by evaporating, drying and calcination within a single vessel, that can then be sealed and used for long term storage.

Abstract: A system for chemically decontaminating radioactive material.

Abstract: The invention relates to a manufacturing facility comprising a building structure which encloses working space of the manufacturing facility, the building structure being designed to house a cyclotron and to be transportable by truck or rail to a destination site, wherein the manufacturing facility, except for lacking a cyclotron during transport, is substantially equipped during transport to produce and package a radiopharmaceutical. The invention also relates to a method of providing a manufacturing facility for producing a radioactive material, the method comprising the steps of designing the manufacturing facility to receive a cyclotron; equipping the manufacturing facility with a synthesis unit which is designed to receive a first radioactive material from the cyclotron and to produce a second radioactive material; transporting the manufacturing facility to a site; transporting the cyclotron to the site; and enclosing the cyclotron inside the manufacturing facility.

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: 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: 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 device for preparing a radioactive water solution to be infused in a patient includes a reaction chamber (13) in which radioactive water vapour is formed by the catalysed reaction of oxygen gas containing oxygen-15 and hydrogen gas. A diffusion chamber (14) is provided which allows the radioactive water to penetrate, but which prevents the penetration of gasses. Tubes (26) and valves (16, 18) direct a sterile saline solution to the diffusion chamber (14), and then direct the saline solution containing radioactive water out from the diffusion chamber to a patient, or to a decay coil (22) being a part of the device. A measuring instrument is provided for measuring the radioactivity of the radioactive solution. The device is characterized in that the diffusion chamber (14), the tubes (26) the valves (16, 18), the radioactivity measuring instrument (17), and preferably also the reaction chamber 913), are mounted in the same frame 50, whereby they form a separate unit i.e.

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 method and apparatus are provided for automatically separating radionuclides using a chromatographic separation process. The method includes the steps of displaying a first flow diagram on a display depicting flow of the radionuclides through a first set of separation elements of the plurality of separation processing elements, but only during a first step of the chromatographic separation process and displaying a second flow diagram on the display depicting flow of the radionuclides through a second set of separation elements of the plurality of separation processing elements, but only during a second step of the chromatographic separation process.

Abstract: The invention relates to a manufacturing facility comprising a building structure which encloses working space of the manufacturing facility, the building structure being designed to house a cyclotron and to be transportable by truck or rail to a destination site, wherein the manufacturing facility, except for lacking a cyclotron during transport, is substantially equipped during transport to produce and package a radiopharmaceutical. The invention also relates to a method of providing a manufacturing facility for producing a radioactive material, the method comprising the steps of designing the manufacturing facility to receive a cyclotron; equipping the manufacturing facility with a synthesis unit which is designed to receive a first radioactive material from the cyclotron and to produce a second radioactive material; transporting the manufacturing facility to a site; transporting the cyclotron to the site; and enclosing the cyclotron inside the manufacturing facility.

Abstract: A target material (60) to be treated in a liquid reactant metal is loaded into a containment area defined within a liquid reactant metal treatment vessel (11). The containment area is then placed below the level (L) of the liquid reactant metal in the treatment vessel (11). This places the target material (60) in contact with the liquid reactant metal and allows the desired reactions to occur. Reaction products are then removed from the treatment vessel (11). Placing the containment area below the level (L) of liquid reactant metal in the treatment vessel (11) may be accomplished by pivoting the vessel from a loading position to a treating position to shift the level of liquid reactant metal in the vessel.

Abstract: Spent fuel rods are stored in a container. In order to improve the retention capacity of the barriers for radioactive emitters (radionuclides), the spent fuel rods are embedded in a bulk fill of zeolite and/or activated charcoal.

Abstract: The present invention relates to apparatuses for processing homogeneous/heterogeneous radioactive wastes comprising ion-exchange resins. A cooled discharge unit comprises a discharge pipe, a cooling jacket having a U-shap d form in cross section, a collector for feeding a coolant into the jacket, a discharge gate comprising a pipe, on one end of which a cone-shaped tip is positioned, on the other end a lid with an aperture. A cooled induction melter comprises a housing, side walls and bottom of which are made of metal pipes disposed with a gap therebetween and combined by a collector for supplying and discharging the coolant, an inductor positioned adaptable for displacement along the longitudinal axis of the melter and concentrically encompassing the side walls of the housing, the gaps between the pipes of which ensure transparency of the housing for an electromagnetic field of the inductor.

Abstract: The present invention relates to apparatuses for processing homogeneous/heterogeneous radioactive wastes comprising ion-exchange reisns. A cooled discharge unit comprises 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 comprising a pipe, on one end of which a cone-shaped tip is positioned, on the other end a lid with an aperture. A cooled induction melter comprises a housing, side walls and bottom of which are made of metal pipes disposed with a gap therebetween and combined by a collector for supplying and discharging the coolant, an inductor positioned adaptable for displacement along the longitudinal axis of the melter and concentrically encompassing the side walls of the housing, the gaps between the pipes of which ensure transparency of the housing for an electromagnetic field of the inductor.

Abstract: The present invention relates to a method of transforming plutonium oxalate into plutonium oxide by drying and then calcining. In said method, in a characteristic manner, the operations of drying and calcining are implemented continuously, in the presence of oxygen and with gas extraction, in two adjacent zones of a single apparatus, e.g. of the screw oven type, that is maintained at negative pressure. The present invention also provides apparatus suitable for implementing said method.

Abstract: A main steam pressure disturbance preventing apparatus of a nuclear power plant including, one of a pressure detector and a water level detector provided in one of a steam system from a reactor of the nuclear power plant and a drain system connected to the steam system, an instrumentation pipe connected between one of the pressure detector and the water level detector and one of the steam system and the drain system, and catalyst installed in one of the pressure detector, the water level detector and the instrumentation pipe for recombining hydrogen and oxygen.

Abstract: Wear resistance and oxidation resistance of polymer material or a polymer component for bioimplantation are improved by packaging a polymer object in a sealed gas impermeable package substantially free of oxygen, irradiating the package with penetrating radiation to an extent sufficient to effect a desired substantial level of cross-linking within the polymer, and warming the packaged object while maintaining an elevated hydrostatic pressure to cause gases released during irradiation to recombine, stabilizing the material against subsequent oxidative change. The pressure stabilization terminates active sites, substantially eliminating free radicals. When applied to finished parts, the process simultaneously hardens and sterilizes the parts without degrading mechanical properties or dimensions. When applied to bulk material or unfinished parts, the part may be subsequent machined or otherwise finished, and sterilized by any conventional means.

Abstract: A nonwoven web laminate having improved particulate barrier properties, and particularly improved particulate barrier properties for particles in the size range of between 0.19 microns and 0.5 microns, is provided. The particulate barrier properties are improved by subjecting one or more of the layers forming the nonwoven web laminate to corona discharge. The improved particulate barrier properties are further achieved without substantially altering or increasing the amount of surface charge on the nonwoven web laminate.

Abstract: Apparatus and process for non-pyrogenously preparing a radioisotope-labeled reagent that includes a plurality of raw material-holding containers, reaction vessels, and columns connected to each other by transfer tubes that are hermetically sealed such that the raw materials can be introduced into the appropriate reaction vessels in the appropriate order through the transfer tubes using a force fed inert gas.

Abstract: In a boiling water reactor having two extraction systems, one in use and the other held as a backup, a method and apparatus for extracting condenser exhaust gases of the reactor include a preheater for heating condenser gases which are then used for heating a recombiner of the extraction system. Auxiliary steam from the turbine is directed to the preheater for heating the condenser gases. A bypass line bypasses a valve in the auxiliary steam pipeline from the turbine to the preheater. The operating extraction system receives heating steam through the auxiliary pipeline, while the backup extraction system has the valve in the auxiliary steam pipeline closed. The recombiner of the backup extraction system is kept heated by guiding steam through the bypass line to the preheater, where the steam expands and is thereby heated, and directing the expanded steam through a vent line to the recombiner.

Abstract: A continuous denitration apparatus capable of ensuring mass processing of a nitrate solution of a nuclear fuel and a continuous stable operation. By a rotation of screws, uranium nitrate solution supplied from a liquid feed inlet is continuously conveyed. A trough is divided into a concentration zone, a denitration zone and a drying zone. Microwaves emitted from a microwave incident inlet pass through a microwave permeable part provided in a critical shield plate for covering the upper part of the trough and are applied to the uranium nitrate solution of high concentration and high viscosity, conveyed by the screws. The uranium nitrate solution is denitrated to prepare a denitrated product (uranium trioxide). This denitrated product is dried in the drying zone to obtain powder to be discharged from an outlet.

Abstract: A process for in-drum drying of liquid radioactive waste includes sealing a shielded container by placing a plug in a central opening formed in a lid of the container. The plug is removed from the opening and a filling adapter having an outside diameter that fits the opening is inserted into the opening. Liquid radioactive waste is poured into the sealed container and vapors are vented from the container, through the filling adapter. The liquid radioactive waste is heated in the container with a heater. A filling adapter for in-drum drying of liquid radioactive waste includes a rectilinear, preferably cylindrical steel casing with end regions, an outer periphery, a flange protruding past the outer periphery at one of the end regions, at least two connection points at another of the end regions, and a filling line extending from one of the connection points through the steel casing.

Abstract: An apparatus for the manufacture of radiopharmaceuticals includes a lead chamber (6) and a loading device (5) on which a chemical system is mounted in the form of a disposable kit (5). The apparatus includes a first suspension device (9) which functions to move the loading device in a radiation-safe manner between a loading position externally of the lead chamber and a working position within the lead chamber. A second suspension device is provided for releasing a consumed disposable kit from the loading device, such as to enable the consumed kit to fall down into a bottom section (8) of the lead chamber, this bottom section serving as a waste chamber.

Abstract: A process for in-drum drying of liquid radioactive waste includes sealing a shielded container by placing a plug in a central opening formed in a lid of the container. The plug is removed from the opening and a filling adapter having an outside diameter that fits the opening is inserted into the opening. To measure the fill level a sensor is inserted into the filling adapter and protrudes from a free end of the filling adapter into the interior of the container. Liquid radioactive waste is poured into the sealed container and vapors are vented from the container, through the filling adapter. The liquid radioactive waste is heated in the container with a heater.

Abstract: A microwave applicator for processing of radioactive waste slurry uses a waveguide network which splits an input microwave of TE.sub.10 rectangular mode to TE.sub.01 circular mode. A cylindrical body has four openings, each receiving 1/4 of the power input. The waveguide network includes a plurality of splitters to effect the 1/4 divisions of power.

Abstract: Materials are labelled with a radioisotope by passing them through a column packed with (a) beads coated with an oxidizing reagent for coupling the radioisotopes to the materials, (b) as anion resin, and (c) a material for trapping elemental isotope, and flowing a mixture of the radioisotope and a solution of the material to be labelled through the column.

Abstract: In a nuclear fuel reprocessing plant for processing a used nuclear fuel by a nitric acid solution, the present invention provides a nuclear fuel reprocessing plant characterized by including electrolytic reduction means for reducing the valence of oxidizing metal ions consisting of the nuclear fuel and dissolved in the nitric acid solution while they are kept under the ionic state. In a processing method of a nuclear fuel reprocessing plant for processing a used nuclear fuel by a nitric acid solution, the present invention provides also a corrosion-proofing method of a nuclear fuel reprocessing plant characterized in that electrolytic reduction is carried out so that the valence of oxidizing metal ions consisting of the nuclear fuel and dissolved in the nitric acid solution is reduced while the metal ions are kept under the ionic state and NOx gas is also generated.

Abstract: A vessel for solidifying radioactive waste pellets includes a vessel body, an inner lid mounted within the vessel body and fixedly secured to an upper portion of the vessel body, and a device for preventing the pellets from floating fixedly secured one end thereof to the inner lid. The inner lid has an opening formed at a generally central portion thereof, and the pellet float prevention device is extended into the opening of the inner lid to define gaps therebetween allowing the passage of a solidifying material in the state of a liquid or a slurry therethrough but preventing the passage of the radioctive waste pellets therethrough. The pellet prevention device, when receiving a downward urging force, is bent downward to enlarge the gaps therebetween for allowing the radioactive waste pellets to pass therethrough. The pellet float prevention device is returned by a resilient restoring force to its initial position when the downward urging force is released.

Abstract: In an apparatus for treating aggressive, explosive, radioactive or toxic material or solid suspensions within a container and having a rotatable shaft supported in a housing and having one end projecting into the container and another end acted upon by a drive element, an arrangement for sealing the support and the drive element of the shaft includes a mechanical seal arranged between the shaft and the housing in the area of the container, and a static, hermetically closing sealing element arranged in the area of the drive element between the shaft and the drive element, on the one hand, and the housing, on the other hand. The interior space of the housing is filled with a lubricant which is maintained at a pressure corresponding or exceeding the pressure in the container.

Abstract: A method of yielding selectively a desired enrichment in a specific isotope including the steps of inputting into a spinning chamber a gas from which a scavenger, radiating the gas with a wave length or frequency characteristic of the absorption of a particular isotope of the atomic or molecular gas, thereby inducing a photochemical reaction between the scavenger, and collecting the specific isotope-containing chemical by using a recombination surface or by a scooping apparatus.

Abstract: Waste material is passed from a cell 10 through a port 12 into drum 48 which has a mouth 49 with a removable lid 54. A port door 28 includes an electromagnet 54a to hold the lid to the door 28 and both are moved into the cell to allow loading of the drum and after re-closure of door and lid swaging tools 34 operate to deform the lid to form one or more lips which engage under the margin around mouth 49 to resist separation of the lid from the drum.Seals 30, 32, 52 are provided.

Abstract: The invention relates to a process and an installation for the treatment of tritium-contaminated, solid organic waste. The waste is contacted with the steam in enclosure (1) for extracting the tritium in the steam and the steam is then condensed at (11 and 13) to recover the tritium from the waste in the form of tritiated water.

Abstract: A solidification processing apparatus for radioactive waste materials comprises a tank for a solidifying agent for solidifying the radioactive waste materials, a waste material vessel connected to the tank for the radioactive waste materials, a pouring control unit for controlling pouring of the solidifying agent into the vessel, and a heating and curing chamber for heating the vessel by an indirect heating unit after pouring the solidifying agent onto the waste materials in the vessel to polymerize and set the solidifying agent, thereby solidifying the radioactive waste materials. With this arrangement, the solidifying agent superior in impregnation is poured into a vessel filled with radioactive waste materials, whose poured amount is controlled by the pouring control unit. After pouring the solidifying agent into the vessel, the vessel is heated indirectly by an indirect heating unit in order to avoid deflagration if the solidifying agent is combustible.

Abstract: The pH of low level radioactive waste liquid is adjusted to be substantially neutral and the liquid is passed to apparatus comprising an atomizer (11) having a turbine (15), air being heated by an electric heater (16) to the atomizer (11) to provide low level radioactive waste particles which may be encapsulated, e.g. in a resin. The apparatus may be transportable, and is claimed per se.

Abstract: A continuous dissolution apparatus for spent nuclear fuel in which a container (2) for holding a dissolution processing solution (1) is continuously supplied with nitric acid from a feed port (3), while the processing solution is continuously drawn out from an outlet (4). Baskets (71-74) in the container are packed with spent-fuel chops (6), which are continuously dissolved by the processing solution. The container is provided with a solution reserving section (4) for lowering the concentration of radioiodine contained in the dissolution processing solution, and a partition wall (10) is formed between the solution reserving section and a container body. The dissolution processing solution having overflowed from the upper edge of the partition wall flows into the solution reserving portion (14) through a perforated plate column (11).

Abstract: A compression apparatus for reducing solid waste in volume, including: a base; an axial compression mechanism for axially compressing a columnar container containing the solid waste, the axial compression mechanism including a punching mechanism having first teeth projecting radially outwards from an outer periphery thereof at equal angular intervals about an axis thereof, a bottom mold mechanism mounted on the base, and a drive mechanism for driving the punching mechanism toward the bottom mold mechanism for axial compression; and a mold adapted to be placed on the bottom mold mechanism to be concentric with the punching mechanism and having a cavity wall for coaxially receiving the container, the cavity wall including a plurality of mold projections projecting radially inwards therefrom and extending axially at equal angular intervals about the axis, each mold projection including an inclined inner face inclined to the axis and in contact with a conical plane tapering toward both the axis and the bottom mol

Abstract: There is described an apparatus for the corrosion protection of containers for the long time storage of radioactive materials, especially of spent fuel elements, in suitable geological formations which avoid corrosion of the container even with unexpected occurrence of water, or at least delay and minimize the corrosion. The apparatus consists essentially of sacrificial anodes 2 which are conductively joined to the containers 1 via connections 3.

Abstract: The invention relates to a process for recovering heat in an isotopic exchange installation between a liquid and a gas and to an installation for performing this process. The liquid and gas are present in co-current in at least one isotopic exchange reactor, the liquid being vaporized at the inlet of each reactor and condensed during the cooling of the vapor and gaseous phases at the outlet of each reactor. This process is characterized by the recovery of the heat extracted from the vapor and gaseous phases during the cooling at the outlet of each isotopic exchange reactor and by using the thus recovered heat for contributing to the vaporization of the liquid and to the preheating of the gas at the inlet of another isotopic exchange reactor of the installation. The invention applies to a tritium extraction and/or production installation, as well as to the extraction of a isotope from hydrogen.

Abstract: In a process for injecting a radioactive sample of a substance into a reaction vessel, the sample is first enclosed in a first container in which it is irradiated, and then the first container with sample is placed in a second container which is separated from the reaction vessel by way of a closed valve. The second container is heated, and the sample is then conveyed out of the containers into the reaction vessel through the valve which is opened. The sample is enclosed within the first container by plugs or is frozen therein for which purpose the first container may possibly by put into intermediate storage in a storage container. An apparatus comprises the first container for receiving the sample, to be arranged and fixed within the second heatable pressure-resistant container which can be communicated with the reaction vessel through a valve.

Abstract: An apparatus is disclosed for producing a vitric solid solution comprising mainly the solid content of a radioactive waste solution of sodium borate discharged from a pressurized water reactor, the apparatus comprising a waste solution feed tank equipped with a hopper for stabilizing agent in water, a thin film evaporator, a heating type dehydrator, a powder drier connected with a microwave generator through a microwave guide tube and equipped with a stirrer, and a melting furnace connected with a microwave generator through a microwave guide tube, the above units being combined by pipes or a powder-transferring means.

Abstract: A radon free containment environment for either short or long term storage of radon gas detectors can be provided as active, passive, or combined active and passive embodiments. A passive embodiment includes a resealable vessel containing a basket capable of holding and storing detectors and an activated charcoal adsorbing liner between the basket and the containment vessel wall. An active embodiment includes the resealable vessel of the passive embodiment, and also includes an external activated charcoal filter that circulates the gas inside the vessel through the activated charcoal filter. An embodiment combining the active and passive embodiments is also provided.

Abstract: Apparatus is provided for supporting one or more contactor stages used to remove radioactive materials from aqueous solutions. The contactor stages include a housing having an internal rotor, a motor secured to the top of the housing for rotating the rotor, and a drain in the bottom of the housing. The support apparatus includes two or more vertical members each secured to a ground support that is horizontal and perpendicular to the frame member, and a horizontally disposed frame member. The frame member may be any suitable shape, but is preferably a rectangular tube having substantially flat, spaced top and bottom surfaces separated by substantially vertical side surfaces. The top and bottom surfaces each have an opening through which the contactor housing is secured so that the motor is above the frame and the drain is below the frame during use.