Abstract: A high-energy TE laser system, includes an excitation circuit, a laser head having an optical axis, a laser chamber with a gas space formed therein, at least two laser electrodes being disposed opposite each other and spaced apart in the laser chamber parallel to the optical axis of the laser head for producing an arc-free capacitor discharge between the electrodes being as homogenous as possible in the gas space for excitation, at least one rapid high-voltage switch, a pulse-forming network connected to the rapid high-voltage switch for producing high-voltage pulses at the laser electrodes with the rapid high-voltage switch, the pulse-forming network including first and second strip conductor capacitors respectively associated with the rapid high-voltage switch and with the laser head, the strip conductor capacitors including plates and dielectric layers disposed between the plates extended substantially normal to the optical axis of the laser head, forming a capacitor stack stacked substantially parallel to

Abstract: Pressurized water reactor with a primary circuit including therein a reactor pressure vessel, a steam generator and a main coolant pump, and with an auxiliary system having high pressure pumps for feeding water into the primary circuit, including a line extending from an upper side of the pressure vessel and having at least one shut-off valve therein, the line connecting the reactor pressure vessel and a part of the auxiliary system wherein a lower pressure prevails than in the reactor pressure vessel.

Abstract: Method for manufacturing sintered oxidic nuclear fuel bodies by molding uranium oxide starting powder, a mixture of uranium oxide and plutonium oxide starting powder or of uranium-plutonium oxide mixed-crystal starting powder to form blanks and by a heat treatment of these blanks with a U.sub.4 O.sub.9 or (U, Pu).sub.4 O.sub.9 crystal phase developed in them to a degree which can be crystallographically detected at a sintering temperature in the range of 1000.degree. to 1400.degree. C. in an oxidizing and subsequently in a reducing gas atmosphere. The starting powder and/or the blanks are preroasted at a roasting temperature below the sintering temperature in a roasting gas atmosphere with oxidizing action and with an oxygen potential in which the U.sub.4 O.sub.9 (U, Pu).sub.4 O.sub.9 crystal phase is developed and cooled down subsequently to a starting temperature below the roasting temperature in an inert or oxidizing cooling-down gas atmosphere.

Abstract: Method for sintering blanks into fuel pellets, in which the blanks are moved through the muffle of a tunnel furnace by pushing the blanks through the muffle on a guiding device which goes through the muffle and protrudes therefrom at least on the input side, in the form of a single-layer column of abutting blanks.

Abstract: A rotating piston compressor includes a cylinder having inlet and outlet openings formed therein, a piston rotating in a given direction in the cylinder, a shaft supporting the piston and rotating in the given direction, a casing connected to the cylinder and having slits formed therein, a control device for controlling flow through the inlet and outlet openings in the form of a rotary slide disposed outside the cylinder in the casing, the rotary slide being connected to the shaft for a steady, synchronized rotational movement, and the relative position of the rotary slide and the casing being adjustable.

Abstract: Device for flushing out a lance-housing tube in a reactor pressure vessel of a boiling-water reactor and for aligning therein a dry LVD lance which partly protrudes with a pressure-tight lance passthrough from an end flange on the lance-housing tube of the reactor pressure vessel, includes a tubular housing surrounding from below a part of the lance protruding from the reactor pressure vessel and sealed by a lance protection tube, the tubular housing being fastenable to the end flange; and a piston arranged in the tubular housing underneath the sealed lance, the piston being vertically displaceable and rotatable.

Abstract: Liquid-cooled nuclear reactor having a reactor pressure vessel and a reactor core of fuel assemblies received therein, the fuel assemblies being grouped into core cells each having a control rod containing absorber material and connected to a drive mechanism, including a sheetmetal shaft associated with the core cells, respectively, and extending beyond the length of the reactor core by a length at least equal to that of the respective control rod and having a cross section substantially equal to that of the respective core cell, the sheetmetal shaft being formed with longitudinal channels through which the fuel assemblies are loadable and unloadable.

Abstract: A method for the inspection of screws with an eddy current test probe including an insulating material body having a linear contact surface and at least one coil disposed in the body, includes orienting the coil transverse to threads of a reactor pressure vessel setscrew to be inspected, feeding high-frequency alternative current through the at least one coil, generating a coil field covering at least two threads, and guiding the linear contact surface along the threads, and a device for carrying out the method.

Abstract: An apparatus for the mechanical decoupling of a piping system including a pipe line having at least one connecting pipe section with a connecting point and straight pipe line sections connected to and protruding in different directions from the connecting point, includes first holders in the form of commercially available pipe clams firmly connected to a building and distributed at given equal spacings depending on the load-carrying capacity of the pipes exclusively for supporting the pipe lines of the piping system; second fixed-point holders in the form of commercially available pipe clamps disposed in the vicinity of the connecting pipe section including second fixed-point holders directly adjacent the connecting point, at least one of the second fixed-point holders being disposed at each of the respective pipe line sections and three of the second fixed-point holders each being disposed at a respective corner of a triangle for immovably holding the pipe lines and enabling vibrations of the piping system t

Abstract: A nuclear reactor fuel assembly includes an elongated fuel channel with a square cross section and channel walls, the fuel channel having an imaginary lattice disposed therein with a box-shaped cross section having mesh openings and sides parallel to the channel walls, fuel rods containing nuclear fuel being mutually spaced apart in the mesh openings, and a prismatic water pipe spaced apart from the fuel channel by a given spacing and having a cross section spanning more than one of the mesh openings of the imaginary lattice, the given spacing being completely filled with the mesh openings of the imaginary lattice and the fuel rods disposed therein.

Abstract: A nuclear reactor fuel assembly for accommodating mutually parallel rods disposed side by side therein includes a spacer formed of two mutually parallel grid sections, each of the grid sections including outer straps flatly facing the rods, each of the grid sections including main sleeves being positioned like positions of the same color in rows and columns disposed at right angles on a chess board leaving a free intermediate position between each two occupied positions, the main sleeves dividing the grid sections into grid mesh openings at the positions each able to receive a respective rod therein, each main sleeve in one of the grid sections being aligned with a main sleeve in the other grid section forming pairs of main sleeves, connecting straps each interconnecting the main sleeves of a pair of main sleeves forming contact springs for rods, each of the connecting straps having a width being smaller than the circumference of one of the main sleeves, and spacer sleeves each being disposed between and rest

Abstract: Mixing device for embedding biologically harmful wastes in a solidifying binder, includes a tubular housing, an assembly of a pre-mixer, a pass-through mixer and a discharge pump having rotatingly movable parts disposed along a common rotational axis and in substantially vertical direction within the tubular housing, and a drive motor mounted at the upper end of the assembly for rotating the movable parts in common, the movable part of the pre-mixer being centrically disposed in the housing, and the movable part of the discharge pump being eccentrically disposed with play in the housing.

Abstract: Coupling unit for the operational monitoring of the high-voltage winding (SW) and the connected electric output lines in electric high-voltage machines and apparatus, particularly of three-phase stator windings in turbo-generators including their generator output lines (5.1, 5.2, 5.3) and/or in transformers and converters by means of determining partial discharges and measurement of the breaking spark in the high-frequency range, where the above-mentioned machines and apparatus are connected via generator output leads or other connecting line to each other and are connected to ground potential via network protection capacitors. The respective coupling unit (AE1, AE2, AE3) is coupled to one each of the three legs (5.1, 5.2, 5.3) of the generator output lead (5), and the network protection capacitor (C.sub.1, C.sub.2, C.sub.3) of each phase are connected to ground potential (B) via a measuring impedance. Furthermore, the shielded measuring lines (4.1, 4.2, 4.

Abstract: A method for the corrosion protection of steam generators having a housing containing feed water and enclosing a tube bundle with tubes conducting a heat carrier includes continuously determining the redox potential of the feed water during operation of the steam generator, continuously determining the corrosion potential of at least one tube of the tube bundle during operation of the steam generator, and negatively shifting the redox and corrosion potentials by changing the chemical conditioning of the feed water if the potentials indicate the danger of corrosion, and a device for carrying out the method.

Abstract: A sintered nuclear fuel compact of UO.sub.2 or the mixed oxides (U, Pu)O.sub.2 and (U, Th)O.sub.2, with which reactivity losses in a nuclear reactor having relatively long fuel element cycles are avoided, has in its sintered matrix neutron poison in the chemical compound form UB.sub.x with x=2; 4 and/or 12 and/or B.sub.4 C. A sintered nuclear fuel compact of this kind is produced by sintering from a compact comprising a mixture of at least one of the mixture components UO.sub.2, PuO.sub.2, (U, Pu)O.sub.2 and (U, Th)O.sub.2 powder with UB.sub.x powder, where x=2; 4 and/or 12 and/or B.sub.4 C powder.

Abstract: A valve for shutting off a flow having a housing wherein a plug member is movable between "on" and "off" terminal positions by means of a thread; a rotary drive which is switchable off with time delay in the "off" terminal position of the valve; a resilient member for limiting an increase in torque generated by kinetic energy of the rotary drive in the "off" terminal position; and a torque control for the rotary drive includes means defining a range of rotation of the rotary drive in both directions of travel thereof, the entire range of rotation corresponding to a stroke of the plug member and being subdivided into a starting range beginning at one terminal position and ending before a new terminal position is reached as well as into the remaining range; the rotary drive having an available starting torque (break-away torque), taking into consideration the tolerance limit of the power supply in the starting range downwardly, which is at least 10% higher than the largest torque applicable by the rotary drive,

Abstract: A disassembleable and reassembleable sealing device for pipelines, includes a cylindrical sealing insert being insertable into a pipeline in a given direction, the sealing insert having a front cup part with a closed cross section and a rear ring part, as seen in the given insertion direction, the cup and ring parts being annular, coaxial and slideable into each other in axial direction of the sealing insert, the cup and ring parts having corresponding peripheral surfaces and ring shoulder surfaces at the outer periphery of the cup and ring parts defining at least one ring seat, at least one sealing ring inserted into the ring seat between the cup and ring parts, the sealing ring being bulged outward by deformation forces exerted on the sealing ring by the ring seat when the cup and ring parts slide toward each other, increasing the diameter of the sealing ring for pressing the sealing ring against the ring seat and forming a ring bead on the sealing ring resting against the inner periphery of the pipeline fo

Abstract: A combustion chamber with a fluidized bed furnace having a nozzle plate, a fuel feed above the nozzle plate, a primary air feed below the nozzle plate, an exhaust gas channel at an upper end of the combustion chamber, and heat-exchanging heating surfaces includes a cylindrical combustion chamber wall disposed vertically upright and having, in an upper region thereof, a plurality of secondary air nozzles disposed tangentially as well as downwardly inclined to the cylindrical wall for separating and returning unspent solid particles into a lower region of the fluidized bed, a device for directing a flow of gas and particles vertically upwardly in a central region of the combustion chamber and spirally downwardly along the cylindrical wall, and a device for impressing an upwardly increasing rotary flow about an axis of symmetry of the combustion chamber upon the gas flow.

Abstract: A method for measuring the filling level of a liquid in a pressure vessel of a boiling-water reactor, includes measuring the pressure difference between a lower subspace and a reference column, determining steam density in an upper subspace from the measured pressure, determining liquid density in the lower subspace, determining the liquid density in the column, subsequently determining the level in the vessel from the liquid densities in the lower subspace and column, from the steam density in the upper subspace and from the pressure difference and from taking into account time-dependent transient alterations of the values of the densities by measuring the pressure change over time in the upper subspace, the power output and the temperature of the liquid in the vessel, determining therefrom the liquid density in the lower subspace and the steam density in the upper subspace with the measured pressure in the steam space and with known dimensions and quantities, and measuring ambient temperature in the vicinit

Abstract: A method of monitoring fatigue of a stressed component part such as in nuclear power plants or aircraft, with sensors attached to the outside of the component part to be monitored, includes feeding values measured by the sensors at the component parts to be monitored at a given timing cycle to a process computer. The process computer contains a first arithmetic unit (LCID) which determines weighting factors for addressing mechanical unit load cases and/or directly comparing stresses specific to a load case, from the measured values with the aid of a stress file (LCL) of specified unit load cases, and storing them in a working memory. They are assigned in a second arithmetic unit (HSP VSP), in accordance with the comparison stresses determined by the first arithmetic unit (LCID) and/or on the basis of measured data stored in the working memory (FIFO II), after they are resolved in accordingly weighted unit values, utilizing a first memory including two unit load case libraries (TLL, MLL).