Abstract: In a method for the adaptive automatic control of position-adjustable drives, optimized parameters are determined from the drive motion, wherein the optimized parameters are stored with corrected parameters entered into data memory storage. In order to avoid in a method of this kind, involving a reduction of the cycle times, an overshooting in the target position, even in case of non-cyclical positioning sequences, a drive distance, determinant for an operational course, is determined between its stop points and is subdivided into calculated, consecutively numbered distance zones or angle zones and these numbers of system zones or numbers of angle zones are stored in a data memory storage. With the aid of the thus determined distance zones or angle zones, the values describing the drive motions are determined and are sub-divided in each case into a consecutively numbered zone system and are stored in a data memory storage.

Abstract: To provide an electrical apparatus for vaporizing active substances, perfumes or the like volatile substances, consisting of a housing having an electrical heating means and a container for liquid to be vaporized connectable to the housing, in the container a wick or the like being mounted by means of which the liquid is supplied to the heating means, and the wick passes through the heating means at a through passage adapted to the wick, the heating means further consisting of a ceramic heating body with electrical heating coil let into said body, said coil having a high functional reliability and long life with simple production, it is proposed that the heating body (2) comprises a recess (8) which extends tangentially to its through passage (5) and which is made rectilinear and into which the heating coil (7) is inserted, and which is filled with potting composition, the electrical leads (9) of the heating coil (7) being led out of the heating body (2) substantially coaxially to the heating coil (7).

Abstract: For electrodeposition of metal from an electrolyte with a vibrator conveyor the bulk material is transported in a conveying trough which is connected as cathode. According to the invention, the conveying trough (18) is provided with supporting stringpieces (22 to 29) which are intended for the mechanical attachment of the conveying trough (18) on the central pipe (2) as well as for current transmission to the cathode and furthermore serve as electric lead-through through the sidewall (5) of the central pipe (2). The supporting stringpieces (22 to 29) comprise an electrically conducting contact shaft (52) which is electrically insulated from the electrolyte (12) and the central pipe (2). For the attachment of the conveying trough (18) on the stringpieces (22 to 29) contact bolts (56 to 58) are provided which serve at the same time for current transmission from the contact shaft (52) to the bulk material (20). In this form realization one obtains a simple current supply to the cathode.

Abstract: Fiber-reinforced materials are produced by impregnating continuous filaments with a melt of a polyarylene sulfide ketone, preferably one having a reduced viscosity .eta..sub.red of from 0.1 to 0.5 [dl.g.sup.-1 ], shaping the resulting semi-finished product to give a finished article and heating the latter for not less than 15 minutes at above the crystallite melting point of the polyarylene sulfide ketone, the latter undergoing crosslinking and its glass transition temperature Tg increasing by not less than 5.degree. C.

Abstract: Radioactive waste water containing boric acid is concentrated in an evaporator to which an alkali is added to maintain a substantially neutral pH. The boric acid is sedimented out by cooling the solution and an acid is added to the latter to increase the solids recovery by lowering the pH. The solid sediment is vacuum distilled to yield a moist powder.

Abstract: A method of and an apparatus for the treatment of radioactive waste water from a nuclear electricity-generating power plant. The radioactive waste water containing soluble solids, usually boric acid, is concentrated by evaporation according to the invention to a solids concentration above that which will form a saturated solution at room temperature, whereupon the resulting concentrate is introduced into a storage vessel and cooled therein to room temperature. Solids precipitate and sediment in this vessel and water is decanted from the sediment and recycled to the evaporator where the process is repeated. The process allows the amount of waste in terms of the original material treated which must be stored for a given prolonged period, say between one half and three quarters of a year, for radioactive decay prior to packaging of the waste to be significantly reduced by comparison with earlier systems.

Abstract: A container for the transport, storage and disposal of radioactive wastes or other materials, such as irradiated fuel elements of a nuclear reactor capable of neutron emission, which comprises a cast receptacle, e.g. of cast iron, a cover and, in passages spaced apart in the cast wall of the vessel, a neutron moderating or absorbing material. According to the invention, the passages are of circular cross section with a spacing at least equal to twice the diameter, and the total cross-sectional area of the passages in any plane transversely through the vessel corresponds to the cross section in the same plane of a continuous theoretical layer disposed along the periphery of a vessel of corresponding thickness and size or is greater than the area of the theoretical layer in this plane in so far as neutron absorption or moderation effect is concerned.

Abstract: A transport and storage vessel for radioactive materials, especially irradiated nuclear-reactor fuel elements, comprises a one-piece hollow body having lateral walls and a base formed unitarily with one another and open at an upper end which is provided with a removable cover. The walls of the body have an outer layer, an intermediate layer and an inner layer, the outer and intermediate layers being cast unitarily from a carbon-containing ferrous metal or a copper alloy while the intermediate layer consists of a cast matrix phase in which heavy metal particles having a melting point above 800.degree. C. are embedded to absorb radiation. The inner layer can be a lining of stainless steel which surrounds the chamber receiving the radioactive material.