Abstract: A nuclear fuel dissolution apparatus which comprises a perforated sloping ramp contained within a process chamber for containing solvent for the fuel, a pulsation member which in use creates pulses in solvent in the process chamber, the perforations being designed to direct pulses of solvent along and up the ramp, and a discharge point for fuel hulls disposed at an upper region of the ramp is characterised in that the ramp is made out of flat blades and the perforations of the ramp comprise inclined slits formed between the blades.

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: A method of producing multiple batches of a radiopharmaceutical, such as FDG. The method includes the steps of transferring the appropriate liquids to a production apparatus, processing the liquids to produce the radiopharmaceutical, delivering the radiopharmaceutical to a container, automatically cleaning the apparatus, and repeating the previous steps, as desired. The apparatus for multi-batch production of FDG includes a reagent delivery system, a reaction vessel, a filter assembly, and a control system. The combination of these components provides a method that is capable of producing multiple batches of a radiopharmaceutical with minimal operator intervention and, consequently, minimal radiation exposure.

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: The invention pertains to a process for examining chemical reactions in the presence of potentially catalytical substances, wherein reactions are triggered in miniaturized reactors with volumes of 0.001 cm3 to 1 cm3 arranged parallel to each other, and the nature and amount of the reaction mixture are analyzed during the reaction time.

Abstract: A device for improving waste vitrification in a disposable canister, the process for using the device, and the process for making the device. The disposable canister, also known as a module, has outer and inner containers with thermal insulation therebetween. The device includes an inner container of graphite having a layer of pyrographite on its external wall. The outer container is typically made of stainless steel. The inner container is heated, typically by induction, to melt the frit and waste. The melted mixture is then cooled to form a vitrified product in the module. The fabrication of the pyrographite coating on the inner container involves heating the container to about 1500 degrees centigrade in a methane atmosphere, then cooling the container to ambient temperature.

Abstract: A method for remediating non-homogeneous radioactive waste to significantly reduce the waste mass/volume and to convert such waste to products that meet federal regulatory compliance standards is disclosed. High level waste (HLW) stored in underground tanks is typically a multi component mixture. After removal of the waste from the tanks or other storage areas the waste is isolated in a thermal desorption-type reaction vessel where the waste is pyrolized at pre-determined and carefully controlled temperatures, pressures, and atmospheres. This process eliminates organics, volatile metals, moisture and other low boiling temperature/high vapor pressure components and converts non-volatile waste to more stable metal oxides. Off-gas treatment systems scrub, treat and dispose of all off-gas components. A thermal desorption-type apparatus especially well suited for performing the method of the present invention is also disclosed.

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: Apparatus for sewage purifying treatment having a suction nozzle member for supplying pressurized water, an intermediate nozzle member and an injection nozzle member, each having a water passage therein, each nozzle being connected to each other. An air introducing nozzle is formed between nozzle members. An outer casing is arranged in such a fashion that an air introducing chamber is formed at the outer circumference of the intermediate nozzle member, the air introducing chamber and the air introducing nozzle communicating with each other. A pressurized water supply pipe is connected to an end of the suction nozzle member and an air supply pipe is connected to the outer casing for supplying the air to the outer casing. A groove for micronizing coarse bubbles are formed at the downstream position of the air introducing nozzles.

Abstract: A device for improving waste vitrification in a disposable canister, the process for using the device, and the process for making the device. The disposable canister, also known as a module, has outer and inner containers with thermal insulation therebetween. The device includes an inner container of graphite having a layer of pyrographite on its external wall. The outer container is typically made of stainless steel. The inner container is heated, typically by induction, to melt the frit and waste. The melted mixture is then cooled to form a vitrified product in the module. The fabrication of the pyrographite coating on the inner container involves heating the container to about 1500 degrees centigrade in a methane atmosphere, then cooling the container to ambient temperature.

Abstract: The AVS invention provides for an apparatus and process for its practice involving the vitrification of waste materials, such as nuclear waste, inside a disposable canister. The preferred embodiment of the process includes a canister having outer and inner containers with thermal insulation therebetween. Solid frit sections are placed inside the inner container to create one or more regions for receiving waste. The waste is then loaded into the regions. The inner canister is heated to melt the frit and waste and mix them once molten. The melted mixture is then cooled to form a vitrified product in the module. In an alternative process, chunks of frit are mixed with waste and loaded into the empty canister. The mixture is then melted and cooled inside the disposal canister.

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: A process and a device for synthesizing labeled compounds. The process involves preparing a labeling agent, labeling a precursor with the labeling agent, where the precursor is a protected substrate, and deprotecting the labeled precursor to convert the labeled precursor to a labeled compound by passing the labeled precursor through a solid support in a column or a cartridge. The process may be used to convert labeled tetraacetylfluoroglucose (TAFg) to labeled fluoro-deoxy-glucose (FDG) for use in nuclear medical imaging. The process is more rapid than conventional methods and is performed at room temperature rather than high temperature for conventional technology.

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-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: A reaction chamber (20) is charged with a reactant metal (18) which is heated to a molten state by a suitable heating arrangement (21). A field generating arrangement (17) generates a unidirectional electromagnetic field through the molten reactant metal (18) and through at least one target area preferably within the molten reactant metal. The electromagnetic field directs beta particles toward the first target area. A radiation absorbing module (15, 16) is positioned in the first target area and includes at least one radiation absorbing material (75, 76). The radiation absorbing material (75, 76) in the modules (15, 16) absorb the beta radiation which has been directed to the target area by the electromagnetic field.

Abstract: The present invention discloses a method and an apparatus for high yield production of .sup.11 C-methyl iodide by selectively monohalogenating .sup.11 C-methane, whereby the method is comprising a first step of introducing .sup.11 CH.sub.4 into an apparatus containing a circulation system comprising a number of connected circulation members (1-7), and the circulation system is further comprising a number of valves (V114 V5) and at least one pump (8) for controlling the circulation. The method further comprises a second step of recirculation of .sup.11 CH.sub.4 and introduction of iodine vapor into the circulating gas stream passed through a heated reaction chamber (3) within the apparatus having the circulation system during a predefined time period during continuous removal of formed .sup.11 CH.sub.3 I by means of a second trap (7), and a third step of releasing after the predefined time period the produced .sup.

Abstract: A method and apparatus which enables a complete multi-stepped chemical treatment process to occur within a single, sealed-bladdered vessel 31. The entire chemical process occurs without interruption of the sealed-bladdered vessel 31 such as opening the sealed-bladdered vessel 31 between various steps of the process. The sealed-bladdered vessel 31 is loaded with a batch to be dissolved, treated, decanted, rinsed and/or dried. A pressure filtration step may also occur. The self-contained chemical processing apparatus 32 contains a sealed-bladder 32, a fluid pump 34, a reservoir 20, a compressed gas inlet, a vacuum pump 24, and a cold trap 23 as well as the associated piping 33, numerous valves 21,22,25,26,29,30,35,36 and other controls associated with such an apparatus. The claimed invention allows for dissolution and/or chemical treatment without the operator of the self-contained chemical processing apparatus 38 coming into contact with any of the process materials.

Abstract: A multicomponent fluid feed apparatus is disclosed that independently preheats and then mixes two or more fluid streams being introduced into a high temperature chemical reactor to promote more rigorous and complete reactions using assemblies of inert tubular elements and an integral mixing orifice plate. The design allows use of ceramic and speciality alloy materials for high temperature service with particularly corrosive halide feeds such as UF.sub.6 and HF. Radiant heat transfer to the tubular elements from external means gives the necessary system high temperatures without excessive temperatures to cause material failure. Preheating of the gaseous reactants in a separate step prior to mixing and injecting the gaseous reactants into a high temperature chemical reactor was found to provide an improved thermal conversion of UF.sub.6 to uranium oxides.

Abstract: An FDG synthesizer, which comprises: a labeling reaction resin column comprising a column filled with a polymer-supported phase-transfer catalyst resin for trapping an ?.sup.18 F! fluoride ion contained in a target water, and performing a labeling reaction between the thus trapped ?.sup.18 F! fluoride ion and triflate, on the one hand, and a hydrolysis reaction vessel for receiving a reaction intermediate product obtained from the labeling reaction, and performing a hydrolysis reaction by adding a strong acidic aqueous solution or a strong alkaline aqueous solution thereto, on the other hand. The above-mentioned hydrolysis reaction vessel may be replaced with a cation-exchange resin column having a heating device and a flow rate control device of the reaction intermediate product.

Abstract: A method and apparatus for treating toxic waste by the vitrification thereof are described, the method comprising the steps of providing said waste in the form of relatively small pieces; optionally adding vitrifiable material to said waste; bringing a high intensity light source to bear on said waste and said optional vitrifiable material; said high intensity light source being of sufficient power to cause melting and subsequent vitrification of said waste; and, cooling and storing said vitrified material.

Abstract: Apparatus for performing organic synthetic reactions, particularly no-carrier-added nucleophilic radiofluorination reactions for PET radiotracer production. The apparatus includes an optical reaction cell and a source of broadband infrared radiant energy, which permits direct coupling of the emitted radiant energy with the reaction medium to heat the reaction medium. Preferably, the apparatus includes means for focusing the emitted radiant energy into the reaction cell, and the reaction cell itself is preferably configured to reflect transmitted radiant energy back into the reaction medium to further improve the efficiency of the apparatus. The apparatus is well suited to the production of high-yield syntheses of 2-?.sup.18 F!fluoro-2-deoxy-D-glucose. Also provided is a method for performing organic synthetic reactions, including the manufacture of ?.sup.18 F!-labeled compounds useful as PET radiotracers, and particularly for the preparation of 2-?.sup.

Abstract: Plant for cleaning gases (1) from an incinerator (3) of lightly radioactive aste. The plant includes a cooler-condenser (6, 100) for cooling gases (1) to a temperature lower than the dew point, a heater (300) for raising the temperature of the gases as they are discharged from the cooler-condenser (6, 100), a filter (200) for recovering solid particles downstream of the heater before the gases are discharged into the atmosphere, a unit (3) for treating condensates, and capable of precipitating radioactive heavy metals for recovery of a radioactive precipitate and an aqueous solution, an a unit (36) for crystallizing salts and concentrating them to dryness in an aqueous solution and recovering water to be recycled in the plant (2).

Abstract: A process and apparatus for dissolving a mixed oxide or mixture of oxides of uranium and plutonium. The powder is added with nitric acid to a chamber to dissolve uranium oxide, and the solution is circulated through a circuit of the apparatus with a portion of the solution passing through a filter. At least a portion of the filtered solution containing dissolved uranium oxide is removed from the apparatus, while returning non-filtered circulating solution containing non-dissolved plutonium oxide to the chamber. The removal of solution is then terminated, a monovalent silver salt is added and divalent silver is generated in-situ by electrolysis, the divalent silver causing dissolution of the plutonium oxide.

Abstract: A method of purifying a UF.sub.6 gas stream which comprises irradiating the UF.sub.6 gas stream with laser radiation in a vessel in order to selectively convert fluoride impurities in the gas stream to involatile products, removing the purified UF.sub.6 gas stream from the vessel and separately removing the impurities from the vessel.

Abstract: Apparatus and method for performing a nucleic acid amplification reaction and preferably a polymerase chain reaction (PCR) in a reaction mixture in at least one capillary tube. Several different embodiments are disclosed. One embodiment cycles a sample through a capillary tube loop passing through two thermostatted fluid baths. Another embodiment has the capillary tube routed alternatingly between two heat exchangers to that the sample makes only one pass through the tube. Other embodiments maintain the heat exchangers stationary and translate the samples between them. Still further embodiments maintain the samples stationary and either automatically translate or rotate the heat exchangers past the samples contained within the capillary tubes to perform the thermal cycles necessary for the amplification reaction.

Abstract: An apparatus process is provided for the destruction of a toxic organic chlorine-containing compound, especially, a chlorine- and arsenic-containing compound. The apparatus includes a main reactor into which is introduced the chlorine-containing compound, e.g., a Lewisite as a mustard gas, an oxidizing agent and a pH controlling agent, the main reactor including a hot heat exchanger and a cold heat exchanger, a source of inert blanketing gas to provide an oxidation product of the organic original chlorine-containing compound. Preferably, after completion of the oxidizing reaction, any residual oxidizing agent is catalytically decomposed. Then, the oxidation product of the original organic chlorine-containing compound, is preferably decomposed in a catalyst containing vessel at an alkaline pH, e.g., to a maximum final pH of about 11 in a liquid knockout vessel which includes a lower liquid discharge and an upper gaseous discharge connected to a vented absorber vessel to provide an inorganic compound, e.g.

Abstract: A method and apparatus for the treatment of waste materials including nuclear contaminated materials is disclosed. The method of the invention includes the steps of: grinding the base material until the maximum grain size is 50 millimeters; drying the ground material to a relative humidity content below 30%; distilling the material at a core temperature of 100.degree.-1200.degree. C. on a negative pressure from 200 N/m.sup.2 to an over pressure of 300 kN/m.sup.2 in an oxygen free, reducing, indirect heated environment; burning or cooling the vapors arising; treating the remaining solid materials by combustion, mineralization, vitrification, or solidification; and pelletizing or granulating the remaining ash. The apparatus of the invention includes a dry distillation reactor that has a rotary, closed, horizontally arranged cylinder with hollow axes on the ends. The axes are separated from input and output houses by seals. The input house is provided with a loading opening and a gas exit branch.

Abstract: A method for the in-situ vitrification of waste materials in a disposable can that includes an inner container and an outer container is disclosed. The method includes the steps of adding frit and waste materials to the inner container, removing any excess water, heating the inner container such that the frit and waste materials melt and vitrify after cooling, while maintaining the outer container at a significantly lower temperature than the inner container. The disposable can is then cooled to ambient temperatures and stored. A device for the in-situ vitrification of waste material in a disposable can is also disclosed.

Abstract: An apparatus and method for producing a product, such as hydrogen halide gas or sulfuric acid, in a regenerator furnace subsystem from a waste containing a non-gasifiable impurity. The method of the invention includes directing a waste, containing a non-gasifiable impurity into a reaction zone, containing a molten metal bath, in a reactor maintained under conditions sufficient to dissociate the waste and to form a gasified feed component and a non-gasifiable impurity. The gasified feed component is then directed from the reactor to a regenerator furnace subsystem, maintained under conditions sufficient to convert the gasified feed component to the desired product.The apparatus of the invention includes a reactor having a waste inlet and a gaseous effluent, a reaction zone containing a molten-metal bath for dissociating the waste, containing a non-gasifiable impurity, and forming a gasified feed component, and a lance for injecting the waste into the reaction zone.

Abstract: Iodine-125 is produced by neutron irradiation of .sup.124 Xe gas to form .sup.125 Xe and permitting decay of .sup.125 Xe to form .sup.125 I. Irradiation of the xenon-124 is effected in a first chamber within an enclosure and decay is effected in a second chamber within the enclosure and free from neutron flux. The apparatus is submersible in a nuclear reactor pool so as to absorb any radiation escaping the apparatus during the process. Xenon can be caused to move between the chambers remotely, underwater. The second chamber is removable from said enclosure and is transported to a suitable location to recover the .sup.125 I from its interior. Such recovery is effected by admitting an aqueous wash solution into the second chamber, whereupon it is heated, causing water from the wash solution to reflux and cleanse the interior surfaces of the second chamber, thus creating an aqueous solution of .sup.125 I, which then is caused to drain into a suitable container.

Abstract: A rotary kiln, particularly for producing uranium dioxide from uranium hexafluoride, has an inlet arrangement and a heated rotatable barrel. Uranium hexafluoride and steam react together in the inlet arrangement to form uranyl fluoride which is fed into the barrel by the aid of a rotating scroll feed device. In the barrel, the uranyl fluoride reacts with a counterflow stream of steam and hydrogen to produce the uranium dioxide. A porous metal or ceramic filter closely surrounds the scroll feed device to remove particles from kiln-produced gases. The filter is maintained in a clean condition by the scraping action of a number of helical blades forming part of the scroll feed device. The uranium dioxide powder produced by the kiln may be processed to form nuclear fuel pellets.

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: The invention relates to a method of conveying liquid materials in closed systems without mutual contamination, comprising flushing the conduit with an inert gas between introduction of the materials into said conduit and using a peristaltic pump for introducing said materials, in which after each flushing operation for a moment said pump is made to rotate in the reverse direction.The invention further relates to a method for the automated elution of a radionuclide generator and delivery of a radiopharmaceutical liquid, in particular a Tc99m-pertechnetate solution, whereas said above method is used, and to a device for performing said method for elution and delivery of a radiopharmaceutical liquid.

Abstract: Ionene polymers having biologically-active organic and/or inorganic anions are described. Methods to prepare the ionene polymers, compositions containing them and their methods of use are also described.

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: A geographically distributed apparatus and process for detritiating heavy water is provided. The apparatus and process provide a remote site enrichment plant for producing an enriched stream of DT/D.sub.2 gas and a hydriding unit for forming a hydride of the DT/D.sub.2 gas for transportation. Pure tritium gas is produced at a local tritium extraction plant by reforming DT/D.sub.2 in a de-hydriding unit and passing the gas mixture through a chain of cryogenic distillation columns. The invention provides a safe and cost-effective method of detritiating heavy water.

Abstract: Process and device for decomposition of tritiated water and the recovery of elemental tritium (T.sub.2) in which a metal is used which oxidizes in the presence of water according to the formulaMe+xT.sub.2 O.fwdarw.MeO.sub.x +xT.sub.2.According to the invention, said metal is placed in an enclosure, a wall of which is selectively permeable to hydrogen and its isotopes; tritiated water is injected into the enclosure and the space behind said wall is made to communicate with an absorbing device for hydrogen and its isotopes. The injection of tritiated water and the communication with the absorbing device are stopped from time to time for the purpose of regenerating the metal by supplying hydrogen or deuterium to said space and by extracting water from the enclosure.

Abstract: A lance for submerged injection of a feed composition, such as a waste, into a molten metal bath includes a perforate refractory tube which extends substantially coaxially about an injection tube. The perforate refractory tube shields the injection tube from the molten metal bath during partial submersion of the lance into the molten metal bath. A perforate support liner extends between the injection tube and the perforate refractory tube and supports the perforate refractory tube. The perforate support liner and the injection tube define an annulus. The method includes conducting a coolant from a coolant source through the annulus to perforations defined by the perforate support liner and the perforate refractory tube, whereby coolant can be directed through the perforations and into the molten metal bath to cause a protective coating of metal to form on the lance.

Abstract: A system for vitrifying all kinds of waste, including toxic, industrial, household and radioactive wastes such as those generated by nuclear power plants, including dry active wastes, ion exchange resins and aqueous wastes wherein the wastes are conditioned, blended, mixed with glass formers and then fed into a heating chamber where organic constituents of the waste are burned and inorganic constituents are melted with the glass formers to form a waste glass. The aqueous waste may be conditioned by concentrating its solids content up to as much as 90% solids. The dry active waste is conditioned, and mixed to some extent by shredders. The conditioned waste may be blended to achieve a uniform heat energy content of the waste being fed into the heating chamber. The heating chamber has a larger combustion zone to handle the greater amount of organic waste than would be expected in conventional melters, and a melting zone having a replaceable crucible and liner.

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: The disclosure describes an apparatus for performing at least two successive chemical reactions in the same container. In order to successively carry out several chemical reactions in the same container (10), e.g. dosing uranium in the presence of plutonium and fission products, the container is placed in a working station above which issue tubes (16, 20) for supplying the products necessary for the reactions. When a product has to be introduced, a computer controls the descent of the corresponding tube. When the product may react inopportunely if it drops into the container (10) outside the time intended for this purpose, the lower end of the product supply tube (16) is automatically laterally displaced with respect to the container, when the tube is in the top position, e.g. by the cooperation of a pawl (102) with a slot (100) forming a cam.

Abstract: An apparatus is provided for processing toxic materials in a safe manner. Two access ports in the apparatus are used for introducing and withdrawing the materials. In the apparatus, two valves pass the materials through a vial for mixing with a stored toxic material and a column for processing.

Abstract: A system for containment of a supercritical water oxidation reactor in the event of a rupture of the reactor. The system includes a containment for housing the reaction vessel and a communicating chamber for holding a volume of coolant, such as water. The coolant is recirculated and sprayed to entrain and cool any reactants that might have escaped from the reaction vessel. Baffles at the entrance to the chamber prevent the sprayed coolant from contacting the reaction vessel. An impact-absorbing layer is positioned between the vessel and the containment to at least partially absorb momentum of any fragments propelled by the rupturing vessel. Remote, quick-disconnecting fittings exterior to the containment, in cooperation with shut-off valves, enable the vessel to be isolated and the system safely taken off-line. Normally-closed orifices throughout the containment and chamber enable decontamination of interior surfaces when necessary.

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: An apparatus for recovering hydrogen and separating its isotopes. The apparatus includes a housing bearing at least a fluid inlet and a fluid outlet. A baffle is disposed within the housing, attached thereto by a bracket. A hollow conduit is coiled about the baffle, in spaced relation to the baffle and the housing. The coiled conduit is at least partially filled with a hydride. The hydride can be heated to a high temperature and cooled to a low temperature quickly by circulating a heat transfer fluid in the housing. The spacing between the baffle and the housing maximizes the heat exchange rate between the fluid in the housing and the hydride in the conduit. The apparatus can be used to recover hydrogen isotopes (protium, deuterium and tritium) from gaseous mixtures, or to separate hydrogen isotopes from each other.

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.