Abstract: Apparatus for heating an object such as a nuclear target bundle to release and recover hydrogen and contain the disposable residue for disposal. The apparatus comprises an inverted furnace, a sleeve/crucible assembly for holding and enclosing the bundle, conveying equipment for placing the sleeve onto the crucible and loading the bundle into the sleeve/crucible, a lift for raising the enclosed bundle into the furnace, and hydrogen recovery equipment including a trap and strippers, all housed in a containment having negative internal pressure. The crucible/sleeve assembly has an internal volume that is sufficient to enclose and hold the bundle before heating; the crucible's internal volume is sufficient by itself to hold and enclose the bundle's volume after heating. The crucible can then be covered and disposed of; the sleeve, on the other hand, can be reused.

Abstract: A continuous denitration apparatus by microwave heating comprises an oven into which microwaves are applied and a cylindrical rotary drum disposed horizontally and rotatably disposed inside the oven. The rotary drum has the outer peripheral surface composed of a honeycomb or porous sheet-like microwave dielectric member. Inside the oven are disposed a trough for storing a nitrate solution of a nuclear fuel material below the rotary drum so as to immerse a lower portion of the outer peripheral surface of the rotary drum in the solution stored inside the trough, a heater above the rotary drum so as to heat the outer peripheral surface of the rotary drum opposing the heater, and a scraper for scraping off a denitrated product formed on the outer peripheral surface of the roatray drum between the heater and the trough.

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: An apparatus for solvent extraction processes utilizing countercurrent flow of streams of an aqueous phase and an organic phase, such as the Purex process for uranium recovery. The invention comprises contouring the fluid passing orifices in the column phase dispersing perforated plates to impede droplet coalescence of the dispersed phase.

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 radioactive catalyst is disclosed which comprises a fine particle of semiconductor and a high radioactive platinum group element deposited on the particle of semiconductor. The radioactive catalyst serves as a source of radiation and also as a catalyst for oxidation-reduction reaction. By bringing the radioactive catalyst into contact with water, the water is decomposed by the oxidation-reduction reaction to produce hydrogen and oxygen.

Abstract: The invention concerns an installation for carrying out continuous measurements in real time of masses of metals in an acid solution and measuring the acidity of this solution.

Abstract: Hazardous radioactive waste is compacted and cast into safely handled monolithic castings having a radiation barrier wall completely enclosing the radioactive waste by centrifugal casting processes in which the barrier wall may be either a pre-formed shell transported to the jobsite or it may be formed by biaxial centrifugal casting and curing of the barrier wall in a mold. When a pre-formed shell is used, means are provided for thickening the radiation barrier if necessary by biaxial casting of additional barrier material inside of the shell. Castable radioactive material is cast inside the barrier wall before removal of the casting mold from the finished cast monolith. The cast monolith is supported for rotation as the mold is removed therefrom so that additional impact resisting and radiation barrier material can also easily be applied to the exterior surface monolith if radiation leakage exceeds tolerance levels.

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: An exhaust gas recombiner for restoring hydrogen and oxygen gases in gases extracted from a condenser of a steam engine into water by reaction of the hydrogen and oxygen gases includes a vertical cylinder vessel having an extracted gas inlet at its lower end and an outlet at its upper end. A diameter of the vessel is substantially the same as that of an outlet piping connected to the outlet of the vessel for introducing gases leaving the vessel into an exhaust gas condenser. The apparatus further includes a plurality of units in the vessel. Each unit has a honeycomb structure for flow-rectifying gases flowing into the vessel through the extracted gas inlet and a honeycomb catalyst gas carrying on its surfaces a catalyst being positioned on an upper side of the honeycomb structure.

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: The invention is directed to an apparatus for washing a solvent in the recessing of irradiated nuclear fuel. The solvent is washed with an aqueous solution in a mixer-settler having at least one stage which includes a mixing chamber and a settling chamber. The pH is measured by a sensor adjacent stirring means in the mixing chamber and is coupled to a controller controlling metering of the washing solution. The pH of the dispersion in the mixing chamber is measured and an amount of washing solution is added which influences the pH toward the desired operational value. Various recycling means and weir overflow means also influence pH control and the washing operation.

Abstract: Straight tubes and randomly oriented pieces of tubing having been employed in a photochemical mercury enrichment reactor and have been found to improve the enrichment factor (E) and utilization (U) compared to a non-packed reactor. One preferred embodiment of this system uses a moving bed (via gravity) for random packing.

Abstract: A method and means for continuous precipitation of granular uranium peroxide. The reaction vessel and agitation method practiced in it avoid filter plugging and caking problems.

Abstract: A rotary contactor (10) suitable for liquid/liquid extraction processes in a nuclear fuel reprocessing plant includes a rotor (14) with a contacting chamber (16) defined within it, the chamber being of annular shape with its radial width considerably less than its inner radius. Neutron absorbing material (22) inhibits neutron transmission between different parts of the contactor. Where the rotation axis is upright, liquids may be fed into the contactor via open-topped annular feed channels (30, 32) at the upper surface of the rotor (14). The chamber (16) includes a packing material (42) such as wire mesh, random or structured packing. The contactor also includes an arrangement to control the radial position of the liquid/liquid coalescing interface, or to control the radial position at which one of the liquids is taken off, which may be operated by gas pressure.

Abstract: An apparatus is disclosed for housing radioactively and biologically contaminated waste materials during treatment thereof to inactivate the biological contaminants and render the wastes more suitable for disposal in a solid landfill. The apparatus is nonporous and thermally resistant. Additionally, the apparatus features at least one opening within which is disposed a filter for entrapping any radioactive compounds contained in gases exiting the apparatus during the treatment. The apparatus is used in conjunction with an autoclaving procedure which inactivates the biological contaminants while preventing volatile radioactive compounds from escaping into the environment.

Abstract: An apparatus for housing radiation-emitting items to be incubated, such as radio-labeled cell cultures, in order to prevent contamination of the interior of an incubator and the surrounding environment. The apparatus is nonporous and preferably relatively thermally resistant. Additionally, the apparatus features a selectively sealable lid and has at least one opening within which is disposed a filter for entrapping any radioactive compounds contained in gases exiting the apparatus during incubation. The apparatus is used in conjunction with known incubation procedures of radiolabelled cell cultures or other items.

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: An apparatus is disclosed for housing radioactively and biologically contaminated waste materials during treatment thereof to inactivate the biological contaminants and render the wastes more suitable for disposal in a solid landfill. The apparatus is nonporous and thermally resistant. Additionally, the apparatus features at least one opening within which is disposed a filter for entrapping any radioactive compounds contained in gases exiting the apparatus during the treatment. The apparatus is used in conjunction with an autoclaving procedure which inactivates the biological contaminants while preventing volatile radioactive compounds from escaping into the environment.

Abstract: According to the invention there is provided an arrangement which can be used in particular in a media-mixing nozzle assembly intended for use with or to be incorporated in a contact reactor. The nozzle assembly enables a first medium to be mixed with a second medium. This medium mixture is used to clean a contaminated medium fed to the contact reactor, by bringing the contaminated medium into contact with the medium mixture, this mixture containing an absorbent which is capable of reacting with the contaminants in the contaminated medium. The first medium and the second medium are supplied under overpressure to a mixing chamber provided in the nozzle assembly and located upstream of the exit orifice of a nozzle.

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: An active metal bed provided with a filter unit of sintered metal having a wide surface in the horizontal direction, enclosing an active metal powder running a reversible hydrogenation reaction therein and, which is single or plural combined in series, a heater attached thereto and an airtight container housing them, and characterized by, at the time of absorbing hydrogen isotope gas, contacting or flowing the gas to the active metal through the filter, while preventing the scattering of active metal powder, to obtain a large hydrogen absorption velocity by a wide gas contacting area and a decreased pressure loss at the time of gas flowing, and characterized by, at the time of releasing hydrogen isotope gas, preventing the overheating of air tight container and the permeating of hydrogen thereby while heating only the filter unit by the heater.

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 waste melting apparatus includes a waste melting vessel placed in a furnace body made of nonmetallic material and an induction heating coil is provided around the furnace body. The waste melting vessel is made of conductive ceramic material such as C-SiC or C-Al.sub.2 O.sub.3 so that the vessel itself generates heat by induction heating to melt waste in the vessel effectively and safely even within a temperature range of 1,300.degree.-1,600.degree. C. The furnace body may be provided with a vertically movable bottom plate for openably closing the bottom of the furnace body permitting the waste to be melted and solidified in the waste melting vessel in a batch-type system. Alternatively, the waste melting vessel may be provided with a melt discharge pipe at the bottom thereof and the discharge pipe downwardly extends through the bottom plate of the furnace body and thereby the waste can be continuously melted and discharged from the melting vessel into a container placed under the discharge pipe.

Abstract: This invention is a transfer system for controlling and initiating the flow of metered amounts of materials. The aforementioned materials may be radioactive ash, radioactive calcined salts, cement, flour, or pharmaceuticals. The apparatus of this invention comprises: a vertical non-converging conduit which acts as a storage hopper; a stationary platform located at the downward end of the conduit to allow the radial outward flow of the material; a translatable hollow piston that acts externally but coaxially to the conduit and platform to interrupt the radial flow of material; a hopper located below the platform for accepting the material; and a housing that encloses and supports the hopper and platform and provides a dust tight seal around the apparatus of this invention.

Abstract: The invention relates to a method of and apparatus for the regregation of radioactive iodine isotopes from fluid samples. The method consists in leading the degassed and in certain cases also otherwise prepared sample into a column filled with an amorphous solid medium for binding quantitatively the cations, fluoride anions and contaminations of colloidal state, then the effluent flow continuously through an energy-selective gamma detector and continuously recording the signals generated in the detector by the radioactive iodine isotopes. The proposed apparatus comprises a sampling unit (MV), a degassing vessel (G), fluid transfer pumps (P1, P2), pipings, cocks (CS), a bubble removing cell (BC), a column (K) with amorphous material filling, an energy-selective detector system (GD) for measuring gamma radiation, and a signal processing and recording unit (JR).

Abstract: A process for purifying flue gases by conducting the hot gases through a dry purification stage, and then through a pebble bed evaporator containing pebbles and a liquid. The flue gases then exit the pebble bed evaporator and are washed in a wet washing step. Waste liquid containing dissolved material from the wet washing step is then used as the liquid in the pebble bed evaporator; as this liquid evaporates in the pebble bed evaporator, solid precipitate forms on the pebbles. This solid precipitate is removed from the evaporator and is stored. Vapor from the pebble bed evaporator is condensed and used in the wet washing step. The purified flue gases exiting the wet washing step pass through a filter stage and are discharged.

Abstract: This invention relates to a standard component .sup.99m TC elution generator useful for medical purposes and consisting of prefabricated component parts. The main generator column of the device may be used both as an irradiation container and an elution container, enabling the user to supply activated or nonactivated parts. The main generator column made from by neutrns little activable materials serves first as reactor irradiation ampoule and after having been activated in the reactor by neutrons and after a simple adjustment serves directly as the generator column. It is filled with water insoluable molybdates or polymolybdates (with the molybdenum content in the range 10-40%), easily releasing .sup.99m Tc generated by radioactive decay of the mother .sup.99 Mo formed in it by neutron activation. This column filling serves originally as target material for reactor irradiations and afterwards it is directly used as the generator elution matrix.

Abstract: An apparatus for recovering tritium from tritiated compounds is provided, including a preheater for heating tritiated water and other co-injected tritiated compounds to temperatures of about 600.degree. C. and a reactor charged with a mixture of uranium and uranium dioxide for receiving the preheated mixture. The reactor vessel is preferably stainless steel of sufficient mass so as to function as a heat sink preventing the reactor side walls from approaching high temperatures. A disposable copper liner extends between the reaction chamber and stainless steel outer vessel to prevent alloying of the uranium with the outer vessel. The uranium dioxide functions as an insulating material and heat sink preventing the reactor side walls from attaining reaction temperatures to thereby minimize tritium permeation rates. The uranium dioxide also functions as a diluent to allow for volumetric expansion of the uranium as it is converted to uranium dioxide.

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 process for the incremental enrichment of deuterium and/or tritium in a material which is suitable for the isotope exchange of deuterium and tritium with hydrogen, and an arrangement for the implementation of the process. The process and arrangement for the enrichment of deuterium and/or tritium in water which, in addition to a high transport speed for the molecules which participate in the isotope exchange, evidences a high enrichment factor for each enrichment stage and a high yield, so that at a relatively small number of stages and low energy consumption there is attainable an overall high degree of enrichment. For each enrichment stage, water containing deuterium and/or tritium is introduced into a carrier gas flow, reduced and set to a hydrogen (H.sub.2) partial pressure of maximally 100 mbar.

Abstract: The invention relates to a sieve-plate column for liquid-liquid counterflow extraction of two phases which are of different weights and which are not soluble one in the other. A mixing arrangement is disposed between two sieve plates. In order to further increase cross-mixing of the phases and thus the material exchange thereof with a good rate of through-put, a static mixing element is arranged between each two sieve plates. Static mixing elements generally have, over their entire cross-section, a plurality of open channels which are arranged adjacent to each other and which extend inclinedly with respect to the direction of flow, the upper opening and the lower opening of each channel thereby being displaced radially relative to each other.

Abstract: A nuclear waste packaging facility for receiving both contact and remote handled nuclear waste in portable shipping containers and encapsulating this waste into ground-disposable modules is disclosed herein. The facility generally comprises a separately shielded section for processing remote handled waste including various remotely-controlled winches and conveyors, as well as a second, separately shielded section for processing contact handled waste. A module transportation and loading section is disposed between the remote and contact handled waste sections of the facility, and places empty module containers in a loading position adjacent each of the two, separately shielded sections of the facility. Both the contact and remote handled waste sections include radiation and ultrasonic detectors for determining the radioactive level of the waste, and whether or not any of this waste is in liquid form.

Abstract: An arrangement for centering and manipulating conduits is disclosed. The angement is an aid for connecting flanges together by remote control and can be used to connect the end flange of a stationary conduit to an end flange of a removable conduit portion. The use of the centering and manipulating arrangement is in a process cell such as a large-area cell for reprocessing irradiated nuclear fuels. The interface plane of the two end flanges to be connected together is disposed perpendicularly. In order to permit rapid and secure coupling, with a low level of technical complexity, the end flange of the stationary conduit is provided with an upwardly open guide cradle at its peripheral edge. The guide cradle is arranged in parallel relationship to the rotational axis of the end flange and is mounted laterally thereon. In the rearward region which is towards the stationary conduit, the guide cradle includes a catch ring.

Abstract: A transfer system for controlling and initiating the flow of metered amounts of materials which may be radioactive ash, radioactive calcined salts, cement, flour, or pharmaceuticals comprising a vertical non-converging conduit which acts as a storage hopper; a stationary platform located at the downward end of the conduit to allow the radial outward flow of the material; a translatable hollow piston that acts externally but coaxially to the conduit and platform to interrupt the radial flow of material; a hopper located below the platform for accepting the material; and a housing that encloses and supports the hopper and platform and provides a dust tight seal around the apparatus of this invention.

Abstract: Suction molds used in the suction removal process must first be prepared ore they can receive vitrified radioactive waste materials. A method is disclosed for preparing the suction mold which includes a suction pipe welded into the base of the mold with a desired-break location whereat the suction pipe is broken off during the suction removal process. An evacuation stub is mounted in the mouth of the suction pipe and communicates with the interior of the mold. The method of the invention includes evacuating the mold through the evacuation stub and then heating the mold to remove moisture and organic impurities. The mold is then filled with a dry inert gas and the evacuation stub is cleaned. The mold is then evacuated to a predetermined residual pressure. Thereafter, the evacuation stub is cold-press welded so as to close off the interior of the mold from the ambient.

Abstract: Apparatus for use in processing radioactive waste materials for shipment and storage in solid form in a container is disclosed. The container includes a top, and an opening in the top which is smaller than the outer circumference of the container.The apparatus includes an enclosure into which the container is placed, solution feed apparatus for adding a solution containing radioactive waste materials into the container through the container opening, and at least one rotatable blade for blending the solution with a fixing agent such as cement or the like as the solution is added into the container.The blade is constructed so that it can pass through the opening in the top of the container. The rotational axis of the blade is displaced from the center of the blade so that after the blade passes through the opening, the blade and container can be adjusted so that one edge of the blade is adjacent the cylindrical wall of the container, to insure thorough mixing.

Abstract: A method, composition of matter, and apparatus for producing substantially pure Ag-109m for use in biomedical imaging techniques. Cd-109, which decays with a half-life of 453 days to Ag-109m is loaded onto an ion exchange column consisting of particulate tin phosphate. After secular equilibrium is reached in about ten minutes, Ag-109m may be selectively eluted from the column by means of a physiologically acceptable aqueous buffered eluent solution of sodium thiosulfate, and either ascorbic acid or dextrose. The breakthrough of toxic Cd-109 is on the order of 1.times.10.sup.-7, which is sufficiently low to permit administration of the Ag-109m-containing eluate, with but a minor pH adjustment, directly to a human patient within a matter of seconds.

Abstract: According to the method of this invention for fixation of incinerator ash, incinerator ash containing SiO.sub.2 and Al.sub.2 O.sub.3 is incorporated with NaOH or NaOH and an SiO.sub.2 -containing substance in such an amount that the resulting mixture contains 25 to 90 wt % of SiO.sub.2, 2 to 10 wt % of Na.sub.2 O, and more than 3 wt % of Al.sub.2 O.sub.3 which is less than the content of SiO.sub.2 in terms of mol %; 100 parts by weight of the mixture is mixed with more than 5 parts by weight of water; and the resulting mixture is subjected to hydrothermal reaction under a pressure of 70 kg/cm.sup.2 or above and at a temperature of 150.degree. C. and above, whereby the fixation is accomplished.

Abstract: The disclosure describes a method and a system for treating gaseous effluents to remove impurities therefrom, these gaseous effluents flowing out from a high temperature reactor, into which a particulate material is being fed. The method comprises directing the flow of gaseous effluents counter-currently through the particulate material which is fed into the reactor, and independently controlling the particulate material feed rate and the velocity of the gaseous effluents so that particles in the gas feed are substantially all trapped by the particulate feed material and are returned to the high temperature reactor. Volatile materials may also be condensed on the particulate feed material. The purified gaseous effluents are then allowed to exit. A system for carrying out this method is also disclosed.

Abstract: Apparatus for treating radioactive comminuted fuel elements with hot nitric acid comprising an endless conveyor which carries the fuel fragments through a U-shaped jacketed tube counter to the flow of acid. The conveyor travels in a conduit which connects to the ends of the U-shaped tube to form a continuous loop. Downstream of the U-shaped tube associated with the conduit is a washing unit, a drying unit, and a discharge unit. Upstream of the U-shaped tube is a feed unit which joins the conduit. A radioactive fission material sensor is located just ahead of the discharge unit and serves to actuate a switch to recycle treated fragments that may still be radioactive. Drive apparatus for the conveyor comprises permanent magnets mounted at spaced intervals on the conveyor and exciter windings surrounding said U-shaped tube to direct forward movement.

Abstract: Apparatus for the conditioning of radioactive wastes capable of ultimate storage, using a multicomponent binding agent, with a continuous-flow mixer, a filling station for the ultimate storage barrels, a receiver tank for liquid waste materials, a silo for a component of the binding agent, and several conveyors. A premixer for the one binding agent component and for flowable waste materials is provided. The premixer is connected via throughput measuring devices to the silo and to a container for flowable wastes. The premixer is connected via a dosing conveyor device to one end of the continuous-flow mixer. Thereafter, the receiver tank is connected to the continuous-flow mixer. A discharge conveyor device which feeds the ultimate storage barrels is mounted at the other end of the continuous-flow mixer.

Abstract: Apparatus for maintaining the level of an interface between separate phases in a solvent extraction column by regulating the flow from the base of the column. A steady controllable flow is achieved by passing the flow into a pressure vessel and the level in the vessel is controlled by having a plurality of vertically spaced apart apertures in the flow path within the vessel.

Abstract: Containers for the transportation and/or storage of radioactive wastes are filled by evacuating the containers and utilizing the vacuum thus generated to draw radioactive waste into the container. The radioactive waste is then dried in the container directly by continuing the vacuum and, if desired, heating the container with an electrical heater, the vapors thus produced being condensed before the withdrawn gas is filtered.

Abstract: A process and an apparatus are, herein, disclosed for producing microspheres of fissile and/or fertile materials with a high degree of sphericity from a feed solution starter containing at least one metal salt selected from among thorium, uranium and plutonium by using as a gelling medium an organic solvent that has a higher density and a greater interfacial tension with water than the feed solution and which is capable of dissolving ammonia.

Abstract: The invention is directed to a method vitrifying radioactive fission prods in liquid solution. The liquid solution is pumped in metered quantities from a feed container to a vitrifying oven. The offgas occurring during vitrification is scrubbed of entrained radioactive dust particles and the like by a scrubbing liquid in a scrubber. In order to obtain a simplified sequence of method steps for metering the liquid solution and for scrubbing the offgas, the radioactive fission product solution from the feed container itself is used as the scrubbing liquid. This fission product solution is taken from the feed container and conducted to the counterflow scrubber through which it is passed in a direction opposite to the flow of the offgas. The fission product solution used as a scrubbing liquid is returned to the feed container after passing through the counterflow scrubber.

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.