Abstract: A method and device for measuring the fluid level in a container. A column f fluid within the container is momentarily subjected to pressure, which causes the column of fluid to vibrate. The oscillation frequency is then measured. Since the frequency depends on the fluid level, the fluid level may be determined from the frequency of oscillation.

Abstract: A cutter for cutting, in stages, irradiated bundles of nuclear fuel rods, pecially from pressurized-water or boiling-water reactors. The cutter includes a feed channel associated with transverse and longitudinal feed devices for the rod bundle. A cutter housing is arranged at the mouth of the channel. A cutter carriage can be moved at right angles to the feed channel and is provided with a cutter blade; a fixed counter-blade cooperates with this cutter blade; a rod bundle clamping mechanism is located ahead of the cutting plane and is provided with two alternately actuatable clamping jaws. The cutter carriages, the cutting blade, the counter-blade, and the two clamping jaws can be removed and replaced. The transporting, clamping, and cutting devices are respectively provided with their own drive unit.

Abstract: A device is described for the production of glass drops from a glass melt ntained in a melting furnace and containing radioactive waste. The device comprises a horizontally extending pipe adapted at one end to be connected to the melting furnace so as to serve as glass melt overflow. The other end of the pipe is formed with a pocket-like extension, in the base of which the drip nozzles are arranged. The overflow tube, together with pocket-like extension, is surrounded by a heating device and by an insulated housing. The pipe is connected to a bore in the wall of the melting furnace, and the device is simple to manufacture and install.

Abstract: Remotely-controlled manipulator carrier systems are used in large-area hot ells such as a facility for reprocessing irradiated nuclear fuel materials. The system is used to perform manual-like operations on the process equipment in the hot cell which is disposed in racks along two longitudinally extending walls of the hot cell enclosure, the racks being filled with process equipment and defining a passageway in the direction of the longitudinal axis of the enclosure. The system includes a vertical guide column which is connected to the bridge beam of an overhead bridge crane. A support is mounted on the guide column for movement up and down the column. An extendible arm is cantilever-mounted on the support and has a manipulator or other remotely-controlled apparatus at its outer end. The extendible arm is to be subjected to a minimal bending moment when work is done in the racks containing the process equipment.

Abstract: The invention is directed to a concrete shielding housing for receiving and storing a fuel element container filled with spent nuclear reactor fuel elements. The container is suitable for transport and storage. The clear interior dimensions of the concrete shielding housing are somewhat larger than the outer dimensions of the fuel element container. The concrete shielding housing includes a pallet-type base and in the lower region of the housing there is provided at least one air inlet opening and in the upper region of the housing there is provided at least one air outlet opening. To prevent an uncontrolled conduction of moisture away from the interior of the housing to the ground or to the floor of a storage area or building, there is provided a collection pan arranged under the base plate of the pallet-like base. At least one axial bore extends clear through the base plate of the pallet-like base.

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 outer dimensions of the fuel element container are somewhat smaller than the clear interior dimensions of the concrete shielding housing. The concrete shielding housing includes a pallet-like base which can be moved about from one location to another with the aid of a suitable vehicle such as a fork-lift truck. The housing also includes the concrete shielding wall placeable upon the base, and a cover which can be placed atop the upper end of the concrete shielding wall. At least one air inlet opening is provided at the lower region of the concrete shielding housing and, at the upper region thereof, there is provided at least one air outlet opening.

Abstract: The invention is directed to a container for the long-term storage of radctive materials such as irradiated nuclear fuel elements. The container includes a vessel-shaped base body made of a material selected from the group including cast iron and cast steel. The base body has an outer surface and an opening through which the radioactive materials to be stored therein are passed. A plurality of ribs made of corrosion-resistant material are formed on the outer surface of the base-body to partition this surface into a plurality of surface segments. A protective layer covers each of the surface segments to protect the same against corrosion. A cover is adapted for sealing the opening of the vessel-shaped base body. The ribs and their arrangement on the surface of the base body of the vessel make it easier to apply the corrosion protective layer and make the layer less sensitive to differential expansion stresses of the contiguous materials.

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. At least one air inlet opening is provided at the lower region of the concrete shielding housing and, at the highest location of the housing, there is provided an air outlet opening. The air outlet opening is covered by means of a roof-like cover arranged in spaced relationship to the concrete shielding housing. The air outlet opening is surrounded by plates or metal strips or the like which are securely mounted to the housing and extend upwardly in the direction perpendicular to the housing. The upper edge of these plates terminate at a small distance from the roof-like cover.

Abstract: The invention is directed to a dry storage facility for storing radioactive materials such as irradiated nuclear reactor fuel elements. The radioactive materials release heat generated by the radioactive decay and are held in gas-tight storage containers. The dry storage facility includes several storage modules for receiving the storage containers. The storage modules are arranged in the enclosure of the dry storage facility which can be in the form of a secure building or an underground storage cavern. A transport passageway extends alongside of the storage modules and a transport apparatus is arranged so as to be movable along this passageway. The storage containers are cooled in the storage modules by natural convection which is direct or indirect.

Abstract: The invention relates to a device for holding, transporting and final storing burned-out reactor fuel elements comprising a hollow-cylindrical container that can be closed with a cover. On its sealing surface which is opposite the cover, the container is provided with projections which are of dovetail profile. The cover is cast onto the container around the dovetail projections by means of a casting mold whereby an intimate and firm connection between the container jacket and the cover can be produced. The cover can also be prefabricated with filler channels for directing metal casting material into recesses provided in the sealing surface of the cover. When the metal hardens in the recesses the cover is securely locked to the container. The container may have a shielding cover beneath the top cover.

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: The invention concerns a device for the receiving, moving and radiation-shielding of vessels filled with expended reactor fuel elements. The device consists of a protective container having a base, a cylindrical protective jacket and a cover made from concrete. At the lower rim of the jacket there are lateral air ducts which open into the annular space between protective jacket and fuel element vessel. In the area of the upper jacket edge, lateral air outlet ducts are provided. For facilitating the loading of the device with fuel element containers and its transportation, the base is constructed in the form of a separate movable pallet. The fuel element container can be placed on this pallet, and the protective jacket over it. The air outlet ducts in the area of the cover are arranged in an inclined or angular fashion. The base is provided with a raised center platform for supporting the fuel element vessel.

Abstract: A device for disposing of a contaminated suction tube connected to a storage container for glass-enclosed radioactive waste material by inserting the tube in the container for ultimate disposal with the container. The device consists of a metal sleeve that is mounted on the bottom wall of the container and extends upwardly into the container and an inner tube which slides in the sleeve. The suction tube is connected to the lower end of the inner tube. Detachable connecting means, such as solder, fixes the inner tube and hence the suction tube to the sleeve until the glass filling operation is over. At this point the solder melts and the suction tube and inner tube are free to be inserted into the container by sliding the inner tube upwardly in the sleeve.

Abstract: An apparatus for converting molten glass containing radioactive waste into molded pellets or spheres comprising means for generating a flowing stream of the molten glass and a rotating wheel disposed beneath the flowing stream. The wheel is preferably mounted for rotation about a horizontal axis and has a series of mold cavities formed in the circumferential wall of the wheel, into which cavities the stream is directed by gravity. The mold cavities have flared side walls so that when the stream strikes the inclined wall it is deflected toward the center of the cavity through a focal point. The side walls of adjacent mold cavities form a knife edge at the surface of the wheel to preclude the bridging of glass from one cavity to another.

Abstract: A method and apparatus for encapsulating or embedding highly radioactive waste in glass within an ultimate storage container in which molten glass is transferred from a melting furnace to the container by means of suction. The container is evacuated, and a sealed suction tube connecting to the container is immersed in the molten glass containing the waste, whereupon the seal is broken and the molten glass flows under the force of atmospheric pressure into the container. The operation may be carried out by remote controls.

Abstract: The invention covers a method as well as a device for controlling the discharge of molten material from a melter or an intermediate vessel containing such material, in which a primary outflow from the melter or intermediate vessel is fed to an overflow system the working level of which is regulated through the use of pneumatic pressure on a communicating chamber pertaining to the overflow system. Molten material may be led into a primary overflow through the use of a pneumatic lift.