Abstract: An apparatus for treating ion-exchange resin includes a disk mill having a plurality of disks including corundum for comminuting the ion-exchange resin. Reliable temporary storage or final storage even of coarse-grained ion-exchange resin from a nuclear plant is made possible by reduction of the swelling capacity.

Abstract: In an aerosol filter having a number of coaxially disposed, approximately cylindrical filter areas, provision is made according to the invention for each filter area to have a metal gauze. Through the use of the metal gauze for the filter areas, the aerosol filter is simple to clean and is therefore reusable. In addition, such an aerosol filter is especially resistant to low and high temperatures and to corrosion.

Abstract: A medium is separated into a solids-containing component and a liquid component. The latter flows through a filter. Clogging of the filter is avoided in that the latter is moved relative to the medium perpendicularly to the flow direction of the liquid through the filter element. At the same time, the medium is agitated.

Abstract: A medium is separated into a solids-containing component and a liquid component. The latter flows through a filter. Clogging of the filter is avoided in that the latter is moved relative to the medium perpendicularly to the flow direction of the liquid through the filter element. At the same time, the medium is agitated.

Abstract: A method of reducing the volume of a mixture of filter fibers and a powder-form ion-exchange resin, produces a waste product that is particularly suitable for ultimate disposal. A solvent which dissolves the filter fibers is added to the mixture and a mixture which is thus formed is first dried and then given an additional heat treatment.

Abstract: A drying station with low energy consumption and short drying time for drying liquid or damp waste, especially contaminated waste from a nuclear power station, includes at least one heating mat for delivering heat of evaporation into a container in order to fully and reliably ensure the drying of material in the container. A retainer automatically produces a large-area mechanical contact between the heating mat and the container when the container is brought into a drying position.

Abstract: A process for treating radioactive waste in the form of contaminated powdery ionic exchange resin to make it suitable for final storage by reducing its volume as much as possible, includes mechanically dewatering the ion exchange resin. The dewatered ion exchange resin is mixed with a calcium compound. The mixture is dried at temperatures of up to 120.degree. C. and preferably about 50.degree. C. to 60.degree. C., and at a pressure of from 120 to 200 hPa, until a residual moisture content of less than 10% of the mass of the mixture is reached. The dry mixture is thermally treated at a pressure below atmospheric pressure by heating up to a temperature of from at least 120.degree. C. to at most 190.degree. C. The ion exchange resin thereby loses its water absorption and swelling capability. Ion exchange resins treated in this manner are processed with cement or bitumen to form blocks that are suitable for final storage.

Abstract: For bonding particularly radioactive wastes into a binder, a transporting and mixing device is used which transports the mixture to a storage tank prior to the hardening. The wastes are transported into the mixing zone by gravity and aided by the conveyor helix which also imparts additional wall cleaning action through the dry conveyor zone. A single or multi-component binder is concurrently transported in a direction lateral to the mixing tool to the mixing zone. The mixture is conducted in a straight-line extension of the transport and mixing direction to an outlet to which the storage tank is connected.

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: Method for producing casks capable of ultimate storage of radioactive wastes by filling the wastes to which cement has been added into containers taking radiation shielding into consideration. The casks are filled in at least two stages with partial quantities located concentrically to each other, the volume-specific activity of which increases from stage to stage from the outside in by at least a factor of 2.

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.