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: Radioactive wastes are treated in a furnace which has electrodes for electric heating. The furnace has at the lower end an outlet for slag material as well as a gas discharge line. Its well is a self-supporting tubular body which is arranged detachably in a metal furnace housing. At the upper end of the well is a line for feeding water. Thereby, carbon-containing waste, possibly also carbon of a carbon bed, is reacted to form water gas (CO+H.sub.2), which is burned after purification in an exhaust gas plant. The outlet of the metal housing has a movable grate.

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: An apparatus and method for monitoring stored material is disclosed. Material to be stored and monitored is placed within the innermost container of a series of nested containers and monitoring fluids are circulated in a closed loop of fluid flow through the spaces between the nested containers. Monitoring devices are used to analyze said monitoring fluids to detect leakage of the stored material from the innermost nested container and to detect the migration of external fluids into the series of nested containers. A computer based monitoring system continually checks the values of various parameters of the monitoring fluids to immediately detect and report the presence of stored material or external fluid in the monitoring fluids. The stored material may then be immediately retrieved from storage to repair leaks in the series of nested containers. The invention is particularly suited for monitoring the storage of hazardous material such as radioactive waste material.

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: A system for disposing radioactive waste by solidifying the waste. The system has a lifting/lowering device for causing a relative vertical movement to bring a thin-walled container made of an inorganic material and a filling cap into contact with and away from each other. Supplying means are provided for supplying the container with the radioactive waste, solidifier and the post-filling solidifier, respectively, through the filling cap when the latter is held in contact with the container. The system further has a capping means for capping the container after filling with the radioactive waste and the solidifier. According to the invention, it is possible to conduct the essential steps such as the filling with the radioactive waste, filling with the solidifier, capping and the post-filling with minimal equipment and space.

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: The invention is directed to an apparatus vitrifying radioactive fission ducts 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: A method for decontaminating metal surfaces having radioactive oxide deposits thereon is disclosed which comprises preparing a decontamination solution having a pH of about 1.5 to about 4 comprising water, about 0.02 to about 0.5% of a water soluble organic acid which has an equilibrium constant in a complex with ferric ion of at least about 10.sup.9 and which is capable of producing a pH of about 2 to about 3 in water, and about 0.01 to about 0.4% of a chelate in free acid form which has an equilibrium constant in a complex with ferric ion of about 10.sup.15 to about 10.sup.19 and which is at least 0.4% soluble at 40.degree. C. in water having a pH of about 2 to about 3. An apparatus for performing the above method is disclosed.

Abstract: Method and means for solidifying nuclear waste for permanent disposal are disclosed. A storage container, in the preferred form of a drum or barrel, is charged with a predetermined amount of liquid polymer resin in an uncatalyzed state. Catalyst-containing frangible ampoules are also positioned in the drum with a rotatable mixer mechanism. At a waste filling station, the mixer is rotated to break the ampoules so as to mix the catalyst and the resin. The catalyzed resin is then mixed with added waste material to completely encapsulate the waste prior to solidification of the resin. Monitoring of the filling and mixing process is provided by continually sensing the torque force being applied to the rotating mixer mechanism. Where the waste is a dust-like, dry particulate material, dust control means and method are also provided.

Abstract: A heat treating apparatus using microwaves for continuously treating a substance containing nuclear materials with consideration of the criticality safety of the nuclear materials. The apparatus has a stationary outer cylinder and a rotatable inner cylinder to form therebetween an annular passage for the continuous heat treatment of the substance. The outer cylinder has inlet and outlet ports for the material and at least one microwave waveguide. The material supplied into the annular passage is heat treated and transferred to the outlet port during rotation of the inner cylinder.

Abstract: An apparatus for continuously concentrating and denitrating a radioactive nitrate solution by microwave includes a rotatably supported concentrating and denitrating vessel disposed within an oven into which microwave is applied through waveguides. The concentrating and denitrating vessel comprises a circular vessel body supported rotatably about its center and a plurality of partition plates positioned radially inside the vessel body so as to divide the interior of the vessel body into a plurality of compartments. The nitrate solution supplied into the vessel is heated, evaporated, concentrated and denitrated in sequence in each of the compartments during one rotation of the vessel to form a denitrated oxide powder. The denitrated powder produced in one of the compartments is transferred into a receiving pan positioned adjacent to the outer periphery of the vessel.

Abstract: A solidified radioactive waste manufacturing apparatus comprises a first system for producing radioactive waste powder from liquid radioactive waste and a second system connected to the first system for mixing the radioactive waste powder with a thermosetting resin and additives. The first system includes a liquid radioactive waste storage tank, a dryer for drying the liquid waste into powder, and a metering device for supplying a predetermined amount of the radioactive waste powder to the second system and the second system includes a mixer connected to the metering device for mixing the waste powder with the thermosetting resin and additives, a thermosetting resin storage tank, additive storage tanks, a cooler for cooling the mixer, and a container for receiving sludged mixture from the mixer. The additive storage tanks contain a polymerization initiator, a polymerization promotor, and a polymerization retarder, respectively.

Abstract: A large-area cell for reprocessing irradiated nuclear reactor fuel elements ontains racks in which process components and connecting conduits for the latter are arranged. The arrangement of the invention connects the conduits of a rack with a plurality of supply conduits outside of the cell which have end portions that penetrate the interior wall of the cell. When the racks are assembled and disassembled, the conduits leading to the process components contained in the rack have to be disconnected from the supply conduits. The conduits should be connected and disconnected rapidly and surely by means of remotely-controlled manipulating apparatus. For this purpose, the arrangement of the invention for interconnecting conduits includes two terminal blocks each having a plurality of passages formed therein. The two terminal blocks are connected to each other by conduit segments which communicate with corresponding ones of the passages in the blocks.

Abstract: Method and apparatus for minimizing diversion of radioactive samples from a nuclear fuel sampling system. The apparatus includes a sampler for drawing a radioactive sample from a remote vessel containing nuclear fuel. The sampler is located within a shielding enclosure that has solid walls for preventing direct physical access to the sampler. A tray is located in the wall of the enclosure and is used for translating a sample vessel in and out of the enclosure. The apparatus further includes a time lock escapement that periodically immobilizes the tray for a period of time sufficient to minimize diversion of the radioactive samples.

Abstract: A process and apparatus are disclosed for the treatment of a substance contained in a solution of a slurry.The solution or slurry is treated in a fluidized bed to give a fusible dried product by use of microwave radiation.The fusible dried product can be heated and fused by use of microwave radiation.

Abstract: An improvement in or relating to the fluidized bed-type heating reactor for introducing into the fluidized bed thereof a water-containing substance to be treated such as an uranyl nitrate solution and subjecting the substance to heat treatment. The reactor of the invention is provided with a microwave-generating means for applying microwaves to the fluidized bed and thereby heating the same.

Abstract: A method and apparatus for charging radioactive waste into a disposable steel drum having a plug type lid. The drum is sealed to a waste dispenser and the dispenser closure and lid are withdrawn into the dispenser in back-to-back manner. Before reclosing the dispenser the drum is urged closer to it so that on restoring the dispenser closure to the closed position the lid is pressed into the drum opening.

Abstract: A soft nonwoven web of entangled fibers or filaments having a pattern of fused bond areas and a stretched, loopy filament configuration outside of the patterned bond areas. The result is a soft web with high bulk that retains to a high degree the original bonded strength properties. In one embodiment, product may be obtained by pattern bonding a meltblown microfiber web under conditions of heat and pressure and then stretching the web under controlled conditions up to preferably about 140% of its original dimension in at least one direction. When relaxed, the stretched filaments bulk and loop except in the fused bond areas where they retain bonding properties. Preferred stretching conditions include room temperature and the use of draw rolls at speed differentials producing the desired stretch. Examples of thermoplastics polymers useful in accordance with the invention include polypropylene, polyethylene, polyesters and polyamides, as well as copolymers and polymer blends.

Abstract: A system for treating radioactive waste employing a rotary mechanism which contains in its rotational path of travel a number of stages for the treatment, i.e., a stage of condensing a slurry of radioactive waste, a stage for drying the condensed waste and a stage for storing dried waste temporarily for feeding to a melting furnace. The rotary mechanism employs a number of containers for transferring the radioactive waste to and from the respective stages along the rotational path of travel.

Abstract: An apparatus for continuously providing countercurrent liquid-solid contact. The preferred embodiment of the apparatus includes an Archimedes' screw in the form of a spiral and a distribution system which includes a central tube disposed along the axis of the spiral. The central tube includes a plurality of weirs and is in open communication with the spiral through a plurality of hollow spokes fixed at one end to the spiral and at the other end to the central tube.Dissolving solution is distributed by the distribution system to the spiral where it encounters nuclear material moving upward due to the pumping action of the spiral. The dissolved material moves counter current to the nuclear material and removed near the bottom of the apparatus.

Abstract: Apparatus for contacting particles with a fluid includes two tubes having different diameters and each including a straight lower section inclined relative to the horizontal and a straight, vertical upper section, the lower ends of the tubes being joined together. Fluid introduced into the lower ends of the tubes allows particles to drop slowly in the larger diameter tube and fluidizes the same particles in the smaller diameter tube.

Abstract: A cyclical and automatable process and apparatus for continuously removing undesired components from solid particles by means of a solvent, the process including maintaining an expanded bed of solid particles in a vertical column, supplying a suitable solvent to the bed to flow through the bed either upwardly or downwardly in a selectably alternating manner, supplying solid particles to the top of the column while the solvent flows upwardly therethrough and interrupting the supply of solid particles and removing a bottom portion of the bed by the solvent when it flows downwardly.

Abstract: A cyclical and automatable process and apparatus for continuously removing undesired components from solid particles by means of a solvent, the process including maintaining an expanded bed of solid particles in a vertical column, supplying a suitable solvent to the bed to flow through the bed either upwardly or downwardly in a selectably alternating manner, supplying solid particles to the top of the column while the solvent flows upwardly therethrough and interrupting the supply of solid particles and removing a bottom portion of the bed by the solvent when it flows downwardly.

Abstract: A device for pulverizing incombustible large solid radioactive wastes arising from atomic power plants or the like. The device comprises a furnace body provided with a vacant space for melting radioactive wastes, a gripper mounted on the furnace body to support the radioactive waste, plasma torches mounted on the furnace body to irradiate a plasma arc toward the lower end of the wastes, and a water vessel disposed below the vacant space.

Abstract: Dimensional stability of an electron discharge heating device having electrodes for focussing the discharge current is improved by providing one or more heat pipes for transferring heat from an electrode to cooling fins outside the vacuum chamber. In one embodiment, a second electrode is water-cooled. The improved cooling not only permits of use of a structure which takes a short time to reach thermally stable conditions due to the small heat capacity of the solid material but also permits of different parts of the gun assembly being operated at different temperatures.

Abstract: An improved method and system for chemically digesting low level radioactive, solid waste material having a high through-put. The solid waste material is added to an annular vessel (10) substantially filled with concentrated sulfuric acid. Concentrated nitric acid or nitrogen dioxide is added to the sulfuric acid within the annular vessel while the sulfuric acid is reacting with the solid waste. The solid waste is mixed within the sulfuric acid so that the solid waste is substantilly fully immersed during the reaction. The off gas from the reaction and the products slurry residue is removed from the vessel during the reaction.

Abstract: A submergible barge and process for submerging and storing radioactive waste material along a seabed. A submergible barge receives individual packages of radwaste within segregated cells. The cells are formed integrally within the barge, preferably surrounded by reinforced concrete. The cells are individually sealed by a concrete decking and by concrete hatch covers. Seawater may be vented into the cells for cooling, through an integral vent arrangement. The vent ducts may be attached to pumps when the barge is bouyant. The ducts are also arranged to promote passive ventilation of the cells when the barge is submerged. Packages of the radwaste are loaded into individual cells within the barge. The cells are then sealed and the barge is towed to the designated disposal-storage site. There, the individual cells are flooded and the barge will begin descent controlled by a powered submarine control device to the seabed storage site.

Abstract: A cyclical and automatable process and apparatus for continuously removing undesired components from solid particles by means of a solvent, the process including maintaining an expanded bed of solid particles in a vertical column, supplying a suitable solvent to the bed to flow through the bed either upwardly or downwardly in a selectably alternating manner, supplying solid particles to the top of the column while the solvent flows upwardly therethrough and interrupting the supply of solid particles and removing a bottom portion of the bed by the solvent when it flows downwardly.

Abstract: An isotope separation apparatus comprises a plurality of independent developing units, each comprising 2 to 20 adsorbent-packed columns forming a continuous developing circuit or passageway, and the developing units are connected to at least one common main pipe for supplying an isotope mixture solution, a regenerating agent solution, or an eluent solution. Also, in a further embodiment the developing units are connected to common liquid-discharge main pipes.The separation or concentration of isotopes such as uranium isotopes, nitrogen isotopes, boron isotopes, etc., is performed by continuously developing the isotope mixture solution passed through the individual adsorbent-packed columns successively in each developing units.

Abstract: Radioactive liquids are stored in coils placed in tanks containing circulating cooling medium. The liquid in the coil is circulated by a fluidic pump. In the event of a failure in the pumps circulating the cooling medium the decay heat will cause the cooling medium to boil. A reflux condensor fitted to the tank prevents loss of cooling medium during such periods of pump malfunction.

Abstract: Provided is a method of producing radio-active waste package. By evaporating and drying, the radio-active waste is reduced to a radio-active powder which is formed into pellets in order to ease its disposal. The pellets are received in a container and then impregnated therein with a thermoplastic composition so as to be integrally solidify in the container. The prior technical method cannot fully impregnate the pellets with the thermoplastic material. The present invention improves the prior art technical method of producing radio-active waste package thereby to eliminate the above disadvantage. The present invention also provides a device for carrying out the above method.

Abstract: A method of treating waste material, particularly radioactively contaminated waste such as ion exchange resins or molecular sieves incorporating .sup.137 Cs. The waste is one which is associated with water, e.g. the waste is wet, and is admixed with a synthetic resin composition which hardens on reaction with water. Also disclosed is an apparatus which may be used for producing the hardened waste/resin mixture in a protectively lined drum or other vessel for subsequent dumping, e.g. at sea.

Abstract: Irradiated tubular rectangular fuel channels from a nuclear reactor are temporarily stored under water. In order to dispose of these highly radioactive channels and to ship them to permanent burial grounds, the channels must be placed in specially designed shipping casks under water. In order to reduce the volume of the channel so as to economize on the use of the casks, the channels are cut along their longitudinal edges to form four plates which are then nested before being placed in the storage casks, thereby greatly increasing the number of channels which may be stored in each cask. The cutting is done under water by an apparatus having four roller cutters which are positioned along the outside of the four edges or corners of a channel and are moved longitudinally down the channel edges in a reciprocating motion until the four side plates of the channel are severed.

Abstract: A radioactive waste discharged from a radioactive substance handling equipment is dried and powdered, and the powder is pelletized. The resulting pellets are stored in an inner vessel of a store vessel having a double structure for a predetermined period to attenuate the radioactivity of the pellets. Then, the pellets are taken out from the store vessel and packed into a sealing vessel. A binder is injected into the sealing vessel to effect solidification.

Abstract: A method of and apparatus for separating krypton from radioactive waste gs which become free during the chemical dissolution of burnt-off fuel particles and contain krypton and xenon. Simultaneously with the core fuel particles conveyed to the chemical dissolution, such quantity of chemically inactive carrier gas intermixable with the waste gases is added to the substances bringing about the chemical dissolution that after purification of the waste gas mixture from gas components such as oxygen, carbon dioxide, nitrous oxide, hydrocarbons and water steam and after subsequent cooling of the waste gas mixture to the boiling temperature of the liquid nitrogen, the quantity of xenon contained in the waste gas mixture is quantitatively precipitated in solid form. Thereupon the waste gas mixture is by means of liquid nitrogen, while simultaneously increasing the pressure, cooled to such an extent that krypton is precipitated.

Abstract: A contaminating product is packaged within a leak-tight sheath and transferred through a lock-chamber which is rigidly fixed to a leak-tight partition-wall. The device comprises a sleeve having a central cavity for establishing a communication between the lock-chamber and the sheath while ensuring tightness against outleakage to the environment. A seal plug having a double wall is placed within the cavity for preventing said communication. The seal plug and the sleeve are cut simultaneously in order to close-off the lock-chamber and the sheath separately by means of each wall of the seal plug.

Abstract: Apparatus for transfer of toxic and radioactive materials between a work enclosure and a container for storing and transporting the materials. Materials are moved through a "double-cover" in which a port in the enclosure is closed by a first cover and the container is closed by a second cover. During transfer, the covers are connected together and the space between the covers is swept by an air stream to prevent ingress and deposition of toxic or radioactive material on the surfaces thereof which are exposed to the environment on separation of the covers.

Abstract: An inert carrier process for drying radioactive waste material and for incorporating the dry material into a binder from which the dried material will not be leached is disclosed. In this process, a hot inert liquid carrier is provided into which the solution to be dried is introduced under extremely turbulent conditions. The solvent flashes off leaving the dried particles dispersed in the inert carrier which carries these particles to a mixing station where a binder for the particles is injected under turbulent conditions. The binder preferentially wets the particles and the coated particles are carried to a separator section where the binder coated particles coalesce and separate from the carrier as a second phase. Thereafter a curing agent can be added to the binder.

Abstract: Worm extruder assembly includes an extruder worm, a steam dome formed as a cylindrical tube disposed transversely to the worm axis, a condenser surrounding the cylindrical tube, a steam outlet line extending from the steam dome to the condenser, and means defining an annular gap connecting the condenser to the cylindrical tube.

Abstract: In treatment of aqueous solutions and suspensions of radioactive waste through a step of drying and pulverizing the aqueous solutions and suspensions and a successive step of compressing and solidifying the resulting powders of radioactive waste, a step of measuring a water content of the powders is provided between the step of drying and pulverizing and the step of compressing and solidifying. When the measured water content of the powders fails to satisfy a predetermined water content, the powders are eliminated from a system of the treatment without passing through the step of compressing and solidifying.

Abstract: According to one embodiment of the present invention, the oxygen gas is introduced into a horizontal, unitary and totally-closed furnace shell, and nuclear fuel to be reprocessed is charged onto an oxidation and separation plate which is horizontally disposed for vibration within the furnace shell along the axis, so that the nuclear fuel may be reprocessed by oxidation in the oxygen atmosphere while the fuel is vibrated and transported on the oxidation and separation plate and the reprocessed nuclear fuel in the form of particles may be discharged. At the same time released volatile fission products from the pulverized fuel are isolated by means of a vacuum blower. According to another embodiment of the present invention, a reduction furnace which is substantially similar in construction to the oxidation furnace described above except that a reducing gas is supplied by an independent source.