Abstract: A safety lock is disclosed for use with an automatic weapon such as a pistol. The automatic weapon has a hammer which is connected to a spring guide rod on which a striker spring is supported. This rod enters a removable insert during cocking of the hammer. A detent is arranged in the insert. The detent is preferably releasable and designed to prevent entry of the spring guide rod into the insert. The insert is replaceable with an ordinary insert and can accept a lock or a magazine safety or can be designed as an unreleasable detent.

Abstract: A blowdown manifold for a nuclear power plant includes a main conduit section, at least one coolant exhaust conduit, and at least one fluidic device. The main conduit section is connected to a pressure relief system in the nuclear power plant. The coolant exhaust conduit has a first end coupled to the main conduit section and a second end extending into a receptacle. The fluidic device is in fluid communication with the main conduit and exhibits a lower flow resistance to air than to water and steam.

Abstract: An apparatus for a firearm, the firearm having a user hand-gripable barrel portion. The apparatus has a U-shaped member with an outwardly extending cylindrical protuberance swivelably disposed thereto. An elongated handle is detachably secured to the cylindrical protuberance. An elevated contoured member is mountably disposed along the curved portion of the U-shaped member. The elevated contoured member is formed to receive a selected portion of the hand-gripable barrel of the firearm. An elongated strap is connectively disposed to the U-shaped member. The elongated strap traverses the hand-gripable barrel portion of the firearm thereby detachably securing the firearm to the U-shaped member. Whereby the user gripping the elongated handle enables swivelable firearm movement.

Abstract: Described are a process and an apparatus for the remote measurement of uranium or plutonium in radioactive materials. in which the sample of the material to be analyzed is to be handled as little as possible. To attain that object it is proposed that the laser beam of a laser is focussed by means of a focussing unit onto the sample to be analyzed, so that a light-emitting plasma is generated, an image of the emission spectrum of the plasma is formed in a spectrograph by means of an imaging unit, and finally it is analyzed by means of an analyzing unit.

Abstract: The cartridge ejector has a spring loaded ejector slide supported by the barrel pivot block for siding motion from a seated position to an eject position. The slide has a finger configured to engage the cartridge casing rim when the casing is seated at the breech end and the slide is at the seated position. Opposite the finger is a catch captured by a sear. In response to opening the breech the slide snaps to the eject position to eject and throw the cartridge casing from the breech.

Abstract: The control rod includes an upper absorber section and a lower velocity limiter comprised of a socket, a vane, a transition piece and a set of fins. To adjust the weight of the control rod, lighter and heavier sets of fins, as well as lighter and heavier transition pieces are provided. By suitable selection of the lighter and heavier sets of fins and the lighter and heavier transition pieces, the weight of the velocity limiter can be selectively adjusted in accordance with the weights of differently designed sections to obtain a predetermined control rod weight. Additionally, the heavier transition piece may have material removed therefrom to decrease its weight to provide an infinite adjustment of weight within a predetermined range of weights for the velocity limiter.

Abstract: The invention relates to an analyzer for the identification of explosives and/or chemical warfare agents, with a neutron source which causes the emission of characteristic &ggr; quanta, whereby the analysis system consists of a mobile frame to which a neutron source and a detector as well as a holder for the object are attached, with a neutron generator which contains deuterium as the target, generates neutron pulses by periodically repeated, pulsed bombardment of the target and is controlled so that short neutron pulses are emitted and repeated periodically, whereby the detector is controlled so that in cycles it detects &ggr; quanta promptly emitted from the object due to inelastic neutron scattering and neutron capture, within at least two consecutive temporal measurement windows, whereby the first measurement window at least partially overlaps temporally the neutron pulse and the subsequent second measurement window does not, whereby in the first measurement window &ggr; quanta are essentially detected du

Abstract: The present invention relates to a fuel assembly for a light-water reactor with a substantially square cross section wherein the fuel assembly comprises a plurality of fuel rods (4). The fuel rods (4) extend between a bottom tie plate (5) and a top tie plate (6) and a coolant is adapted to flow upwards through the fuel assembly. At least one of the top tie plates (6) or the bottom tie plates (5) comprises flow openings (22, 22a, 22b) for the passage of the coolant and side supports (17) for supporting the fuel rods (4) in the lateral direction. The side supports (17) are designed in one and the same sheet-metal piece as the flow openings (22, 22a, 22b) and the side supports (17) are folded substantially 90° in relation to the other structure of the top tie plate (6) or the bottom tie plate (5).

Abstract: A position verification apparatus comprising a movable member disposed within and movable with respect to a housing containing the movable member, a means for generating a magnetic field within the housing, a first magnetically responsive means for sensing the position of the movable member and outputting a signal indicative of the position of the movable member, a second magnetically responsive means for sensing the presence of the movable member and outputting a signal indicative of the position of the movable member and a means for comparing the signal output from the first magnetically responsive means and the signal output from the second magnetically responsive means.

Abstract: A clamp assembly prevents separation of a thermal sleeve penetrating a nuclear reactor pressure vessel wall and a jet pump riser elbow welded one to the other and lying within an annular space between the pressure vessel wall and core shroud. The clamp assembly includes a pair of heads having semi-cylindrical recesses. Pins project inwardly from each of the heads in the semi-cylindrical recesses and have axes which lie parallel to one another. By using actuators mounting multiple electrodes, holes may be formed in situ in the adjoining ends of the thermal sleeve and elbow. Once the holes are formed, the heads can be applied in situ with the pins being received through the holes and the heads clamped to one another. Thug, the pins in each of the sleeve and elbow prevent separating movement of the sleeve and elbow in the event of failure of the welded joint therebetween.

Abstract: A method for measuring the thickness of a layer of crud containing ferromagnetic material deposited on nuclear fuel rods using eddy current lift-off (coil-to-conductor spacing) measurement by exciting a probe coil at predetermined frequency which penetrates only into the layer of crud containing the ferromagnetic material.

Abstract: Apparatus for the determination of radiation induced growth due to burnup of a nuclear reactor fuel assembly in a reactor core.

Abstract: An ECP sensor includes a tubular ceramic probe having a closed tip at one end packed with a metal and metal oxide powder. A metal support tube receives an opposite end of the probe, and is joined thereto by a braze joint therewith. An electrical conductor extends through the support tube and probe, and has an end buried in the powder for electrical contact therewith. A ceramic band bridges the probe and tube at the joint for sealing thereof.

Abstract: A loading machine for simultaneously transferring fuel elements between a reactor core and a storage rack in a nuclear power station has a mast divided into individual mast parts. Each mast part has its own gripping and guiding devices for gripping and holding the individual fuel elements. The mast is provided on a trolley. At least one of the mast parts is movable horizontally on the trolley and is rotatable about its longitudinal axis. The individual fuel elements can be lifted out of the reactor core simultaneously, their position relative to each other can be changed, and the fuel elements can be set down on a storage rack or a workplace. A method for transferring fuel elements in a nuclear power station is also provided.

Abstract: A target grid assembly for employment in a target assembly used to produce radioisotopes by bombarding a target material contained in the target assembly with a particle beam. The target assembly includes the target grid assembly, the target window and a target body enclosed in a target housing. The target body defines a target reservoir for receiving the target material and the target window serves to seal the target reservoir. The target grid assembly includes a vacuum window and a target grid. The target grid defines a target grid portion, a helium input and a helium output. The target grid portion defines a plurality of target grid supports which are configured to form a plurality of target grid oblong openings. The vacuum window is supported against the upstream side of the target grid portion and the target window is supported between the downstream side and the target body.

Abstract: An apparatus for the recombination of hydrogen in a gas mixture, in particular for a nuclear power station, during the operation of which unintentional ignition of the gas mixture is avoided in a particularly reliable way. The apparatus contains a catalyst configuration that is disposed in a housing through which the gas mixture can flow by free convection in the operating situation and the catalyst configuration is assigned a flame retention device. In this case, a sediment trap is preferably integrated into the flame retention device, so that hot catalyst particles that become detached from the catalyst configuration are reliably prevented from flowing out counter to the direction of flow of the gas mixture.

Abstract: A heat removal system for the under reactor pressure vessel area of a boiling water nuclear reactor system that provides both protection of the containment boundary from attack by molten core debris and cools the molten core debris to prevent a breach of the containment boundary in the unlikely event of a severe accident where the molten core penetrates the lower head of the reactor vessel is described. The heat removal system includes a glass matrix slab positioned adjacent the floor of the containment and a plurality of heat tubes at least partially embedded in the glass matrix slab and extending into the area under the nuclear reactor pressure vessel. The cooling system also includes a passive containment cooling system, and fused vent pipes connecting the suppression pool with the drywell.

Abstract: A nuclear power plant comprising a casing which encloses a primary space, a reactor vessel arranged in the primary space, and a reactor core provided in the reactor vessel. The plant further comprises an upper space provided above the casing. The reactor core is separated from the upper space by means of an openable cover arrangement. The casing is designed in such a manner that the primary space is completely closed against the environment to at least the level corresponding to the most highly located part of the reactor core. The upper space is arranged to house a volume of a liquid sufficiently large to permit the filling of the primary space with the liquid to a level located above the most highly located part of the reactor core.

Abstract: A neutron spectrometer is provided by a series of substrates covered by a solid-state detector stacked on an absorbing layer. As many as 12 substrates that convert neutrons to protons are covered by a layer of absorbing material, acting as a proton absorber, with the detector placed within the layer to count protons passing through the absorbing layer. By using 12 detectors the range of neutron energies are covered. The preferred dodecahedron embodiment of the neutron spectrometer comprises a solid, polyethylene dodecahedron assembly with 12 surface facets covered by a solid-state detector stacked on an absorbing layer. In this arrangement, each of 12 surface pentagon-shaped facets provides a polyethylene substrate to convert neutrons to protons, covered by a layer of absorbing material, acting as a proton absorber, with the detector stacked on the absorbing layer to count protons passing through the absorbing layer.

Abstract: The container collects and spreads core melt in a nuclear power plant. The container has a structured bottom, particularly a cartridge-like bottom. The bottom has a material of good thermal conductivity, a plurality of geodetically highest points and a plurality of geodetically lowest points (5) and an outer wall. The outer wall extends with an upward slope between a geodetically lowest point and an adjacent geodetically highest point. A steam conduit which runs through the container interior is provided at each geodetically highest point. The container allows external cooling of core melt. As a result, the formation of radioactive aerosols, the occurrence of a steam explosion and the formation of hydrogen are avoided. In addition, the cooling is made particularly effective by the upward slope of the outer wall since the formation of a spatially fixed steam region, which is associated with a decrease in thermal conductivity, is prevented.