Abstract: The invention is directed to a method for making a glass block containing dioactive fission products in a metal vessel. The method includes the steps of placing the radioactive glass melt in the metal vessel and cooling the same therein. To minimize the formation of fissures in the glass block which is formed, the inner wall surfaces of the metal vessel are coated with a carbon material. The metal vessel is then placed in a thermally-insulating receptacle. The metal vessel is then filled with a radioactive glass melt emanating from a glass melting furnace and, after the filling step, is cooled slowly in the heat insulating receptacle. A container assembly for use in performing the method of the invention is also disclosed.

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: The invention is directed to a remotely-controlled remote handling arrangnt for use in large-area radioactively-charged cells of a facility for reprocessing irradiated nuclear fuel materials. The remote handling means includes a travelling bridge crane and a manipulator carrying apparatus arranged in a plane below the bridge beam of the crane. To improve the self servicing and internal maintenance thereof, the arrangement is made up of various assemblies. The movable assemblies can be separated from their travelling chassis frames. The drive units for driving the chassis frames stay with assemblies when the latter are removed. Accordingly, chassis frames are left on the bridge beam or guide member without their drive units.

Abstract: The invention is directed to an apparatus for remote-controlled connection nd disconnection of threaded bolts in a flange joint located in a radioactively-ladened cell. The apparatus includes a remotely controllable impact wrench carrying an extension shaft which is driven by the output shaft of the wrench. As a means of pulling the threaded bolts out of the through bores passing through the rear flange when a flange joint is being disconnected, a magnetic coil is arranged around the extension shaft. A voltage is applied to the coil thereby developing a magnetic force for holding the threaded bolts in the socket thereby permitting the threaded bolts to be moved away from the flange with the impact wrench.

Abstract: The invention is directed to a device for performing remotely-manipulated intenance work with a motor-driven tool such as an impact wrench or the like on conduits and process components arranged in a shielded, radioactively-ladened cell. The device includes an impact wrench mounted in a carrier frame. The impact wrench can be remotely-controlled in a vertical or a horizontal working position and is movable on the cable hoist of a remotely-controlled crane. The carrier frame is provided with motor-driven retractable and extendable torque bracing spindles on its longitudinally extending sides to prevent twisting of the impact wrench and carrier frame in the vertical working position about the cable of the cable hoist.

Abstract: A transport and storage container for low and medium level radioactive wa is sealed with an external cover after being charged with a receptacle insert. The receptacle insert has a cup-like configuration and is arranged in the storage container and adapted directly to receive the radioactive waste. The storage vessel and the receptacle insert conjointly define an annular space therebetween. The storage container must be appropriate for remotely-controlled handling and must have the greatest possible capacity per drum. For this purpose the top of the receptacle insert has a radially extending centering ring at the edge of its opening with segment-like recesses disposed in spaced relationship to each other around its periphery. The wall of the insert tapers downwardly toward the base thereof.

Abstract: The invention is directed to a method of performing remotely-manipulated ntenance work on upwardly extending conduits in a radioactively-ladened cell such as a large-area cell of a nuclear facility for reprocessing irradiated nuclear fuel. A conduit segment is sawn out of a vertical conduit and a new conduit segment welded into place. The removal of cutting chips from the lower vertical end portion of the conduit after the conduit segment has been sawn out is achieved by freezing the liquid medium in the conduit to form frost plugs above and below the tube portion to be removed. A third frost plug is formed in the lower portion of the vertical conduit above the frost plug which has already been produced therein. Thereafter, the tube portion to be removed is cut and separated from the conduit. Then an anchor member is lowered into the lower end portion of the conduit onto the third frost plug.

Abstract: The invention is directed to an arrangement for interconnecting a first pality of conduits with a second plurality of conduits such as conduits of the kind utilized in nuclear facilities. Maintenance work in large-area hot cells subjected to radioactivity is conducted with remotely-controlled apparatus that is movable within the hot cell. The conduits must be disconnected and connected again with remotely-controlled apparatus. The connection should be completed quickly and effectively. For this purpose, conduit end portions of the conduits which are to be connected are arranged on a fixed supporting bracket. The two sets of conduit end portions which are to be interconnected curve continuously away from the bracket to define an angle of ninety degrees so that the open terminations of the one set of conduits are spaced from the open terminations of the other set of conduits and the axes of the conduit end portions are mutually parallel.

Abstract: The invention is directed to a container for storing radioactive materials hich includes a closing cover tightly secured to the outer layer of the container vessel by a continuous weld seam. The container includes an annular body which is attached to the outer layer of the vessel. The annular body has an inwardly directed flange overlapping the weld seam for protecting the latter against external blows which could occur, for example, during transport of the container. The container also includes two narrow slots formed in the annular body with U-shaped guides disposed therebeneath for receiving transport elements in engagement therewith. The annular ring therefore also serves as a transport ring for facilitating transport of the container. Since the container is held at the ring, tension forces are directed to the outer layer of the vessel and away from the weld seam.

Abstract: The invention relates to a radiation-shielding closure arrangement wherein closure body closes off an opening in a wall between two mutually adjacent large-area cells of a nuclear facility. When the closure body is in the closed position, the cell adjacent the cell wherein radiation is present is shielded against the radiation. If one of the cells contains a cell crane and is at the same time a prohibited area because of radiation present therein, the adjacent cell is configured to be an access cell so that maintenance work on the cell crane can be conducted there. The opening in the partition wall between the two cells must be closed during the time that the maintenance work on the crane is performed. For this reason the closure body is mounted on a horizontal rail track for movement therealong. The outer profile of the closure body fits snugly in the inner profile of the wall opening or overlaps the wall opening completely.

Abstract: The invention is directed to a manipulating device for remotely-controlled anipulation of tools such as an impact wrench or the like. The device includes a support structure for the tool and suspension means for engaging a load hook of a crane pulley or a power manipulator. The support structure includes two side pieces arranged parallel with one another and fixed laterally to the tool. The side pieces contain longitudinally extending slots which connect the end locations which correspond to the horizontal and vertical working positions of the composite assembly made up of the tool and support. The suspension means includes a carrying yoke which can be displaced relative to the support structure. The yoke is guided at its lower end in the longitudinally extending slots. The manipulating device can be moved between its horizontal and vertical working positions without the need for any additional mechanical holding or moving components.

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 device for evacuating, filling and closing final storage containers for dioactive materials mixed with molten glass, comprising a suction pipe connected to the container, a meltable closure for said pipe and a closable evacuation connection fitting mounting in said meltable closure. The container is evacuated through the fitting whereupon the fitting is sealed closed to preserve the vacuum. When the suction pipe is dipped into the molten glass to fill the container, the closure melts and with the glass is sucked into the container.In another form the device also includes a protective sleeve surrounding the fitting, closed at its outer end with a meltable plate which also serves as a heat radiation shield. The shield prevents premature melting of the meltable closure, i.e. melting from the heat in the glass furnace prior to immersion of the suction pipe in the molten glass.

Abstract: A method for disposing of radioactive krypton by embedding it with radioactive palladium or molybdenum on the inner surface of a steel cylindrical container. The embedding is effected by sputtering from a glow discharge krypton plasma disposed in the annular space between a sputtering electrode arranged concentrically with the side wall of said cylindrical container which serves as the embedding electrode. The sputtering electrode is coated with radioactive palladium, molybdenum, or other metal, by electrolytically depositing said metal from a radioactive fission solution. After sputtering, the container is sealed and put in final storage. The method disposes of the radioactive metal deposited on the sputtering electrode as well as the krypton.

Abstract: The invention is directed to a coupling arrangement for pipe conduits thrh which a medium containing radioactive or toxic substances is conveyed. The coupling arrangement includes a first coupling unit mounted on the end of a first one of the pipe conduits. A conduit engaging assembly is mounted at the end of the second one of the pipe conduits and includes an inner conduit segment tightly connected to and aligned with the second pipe conduit. A tubular member is arranged in surrounding relationship to the inner conduit segment so as to be coaxial therewith. The tubular member has a forward free end facing toward the first coupling unit and a second coupling unit is mounted on the forward free end of the tubular member and is joinable to the first coupling unit.

Abstract: The invention is directed to a container for the interim and long-term stge of radioactive material such as irradiated nuclear reactor fuel elements. The container includes a vessel and a cover. The vessel has a base and a wall extending upwardly from the base. The wall terminates in an upper end portion defining the opening of the vessel for receiving the radioactive material to be stored therein. A sealing cover tightly closes the vessel. The vessel is a double-walled body made up of two metal layers defining the outer and inner walls of the vessel. The inner wall constitutes a base structure made of an inexpensive and mechanically stable material; whereas, the outer wall is made of a corrosion-resistant material.

Abstract: The invention is directed to a container for storing radioactive materials such as irradiated nuclear reactor fuel elements and the like. The vessel of the container is configured to have a plurality of wall layers. The inner wall layer of the vessel consists of a mechanically stable inexpensive metal material which is surrounded by a corrosion-protective wall layer made of high-alloy austenitic castable material with nodular graphite. The receiving opening of the vessel is closed by a sealing cover welded to the corrosion-protective layer. The container serves not only as a container for the final storage, it also can be utilized for a long-term storage at a surface location as well as for transport of the irradiated fuel elements. The amount of material needed for the corrosion-protective layer is held as low as possible. This is achieved by casting a wall layer of cast iron containing nodular graphite in surrounding relationship to the corrosion-resistant wall layer.

Abstract: The invention is directed to a container for transporting and/or storing irradiated nuclear fuel elements. The container includes a holding vessel made of cast iron containing nodular graphite and having an opening at one of its ends for receiving the materials to be stored therein and a cover for sealing the opening so as to be gas-tight with respect to the ambient. In order to weld a cover to the vessel without the necessity of conducting a follow-up heat treatment operation, an end ring made of cold-weldable material is mounted on the vessel at its opening. The end ring includes a connecting extension which is fused with the vessel when the latter is made by casting. After the vessel is filled, a cover made of a material having a structure similar to that of the end ring can be welded to the latter. In this way, a subsequent heat treatment of the vessel which would otherwise be necessary is avoided.

Abstract: Apparatus is described for remotely positioning, connecting, and generally andling components in a hot cell of a reprocessing plant for spent nuclear fuels. The apparatus includes a housing mounting a first stationary clamp for holding one end of a pipe and a second movable clamp for holding the end of a second pipe to be welded to the first. By adjusting the movable clamp, the pipe therein can be aligned with the pipe in the stationary clamp. The movable clamp can be moved longitudinally to press the pipe ends together, upwardly to compensate for pipe out of round, and can be tilted where pipes are to be joined at an angle. The adjustment permits accurate alignment of the parts. A tool support is rotatably mounted on said stationary clamp to permit welding or other processing through 360.degree..

Abstract: The invention is directed to a concrete shielding housing for receiving and storing a transportable fuel element container which is suitable for storage and filled with spent nuclear reactor fuel elements. The clear interior dimensions of the concrete shielding housing are somewhat larger than the outer dimensions of the container. During its temporary storage the fuel element container must be monitored with suitable measuring instruments. In order to make the monitoring as simple as possible, measuring probes are arranged on the inner wall surface of the shielding wall of the concrete shielding housing. The measuring probes are embedded in the concrete and are already in place and ready for use before the fuel element container is loaded into the concrete shielding housing.