Abstract: A system for the secure and rapid acquisition of a transmitted acquisition composite code composed from acquisition component codes. The acquisition composite code may, for example, be composed in accordance with a Boolean majority voting rule. Reference component codes that correlate respectively with the acquisition component codes are combined to provide a verification composite code that correlates with the acquisition composite code only when all of the reference component codes in the verification code are each in alignment with the corresponding acquisition component codes in the acquisition composite code. The verification code may, for example, be composed in accordance with a modulo-2 addition rule. Initially, the reference component codes are individually brought into alignment with the transmitted signal during the acquisition thereof.

Abstract: In the measurement of the phase difference (proportional to the elevation angle of a target) provided by the radar target signals that are received by each antenna of an antenna array, a comparison of the responses of the signal processing circuitry to the radar target signals and to two signals with an adjustable known phase difference, causes the known phase difference to change until the result of the comparison is a null. The known phase difference, at the time that the comparison provides a null, is equal to the phase difference provided by the radar target signals and is independent of phase errors introduced by the processing circuitry.

Abstract: A coupling is provided for holding and releasing a safety and a safety-and-control rod in a nuclear reactor which coupling comprises three pairs of electromagnets, said electromagnets being arranged in a circular row and act upon a single armature attached to the rod; the electromagnets of each pair being disposed at diametrically opposed position with respect the the rod axis. The signal from each sensor of a set of multiple sensors of each relevant parameter of the reactor operation is supplied to a meter of the parameter. The signals from one of each set of meters are conjointly supplied to a logic circuit which is connected to an amplifier. Finally the power from each amplifier is separately supplied to each pair of electromagnets for controlling the hold and release of the rod. The electromagnets of the coupling are arranged in a circular row and act upon a single armature attached to the rod.

Abstract: Vanadium carbide is present in the particles as supersaturated solid solution and the particles are coated with a thin porous layer of vanadium carbide.

Abstract: A nuclear reactor with a reactor core having a plurality of individual core elements is provided with a clamping device for at least some of the core elements, which clamping device includes a plurality of pawls pivotally mounted to the interior of each wall of the hexagonal outer wrapping tube for movement between a position within the wrapper tube and a position extending through an adjacent hole in the side wall of the wrapper tube, and an operating tube axially slidably mounted within the wrapper tube for moving the pawls between their two positions. When the pawls are extended by the operating tube, they will move outwardly a predetermined distance transversely of the core element to cooperatively engage other core elements and clamp the assembly. A lock mechanism is provided to lock the operating tube and wrapper tube in one position of the pawls, preferably the withdrawn position, to assist in inserting and removing the core element.

Abstract: An illustrative embodiment of the invention provides for a space between the two barriers that ordinarily form the emergency containment system for a nuclear reactor. Tracks set within this space, and a television camera bearing trolley adapted to move on these tracks enables the surface of the inner containment structure to be thoroughly inspected at low cost.

Abstract: A turbine follow system and method for Pressurized Water Reactors utilizing load bypass and/or atmospheric dump valves to provide a substitute load upon load rejection by bypassing excess steam to a condenser and/or to the atmosphere. The system generates a variable pressure setpoint as a function of load and applies an error signal to modulate the load bypass valves. The same signal which operates the bypass valves actuates a control rod automatic withdrawal prevent to insure against reactor overpower.

Abstract: A nuclear power plant installation includes a concrete biological shield forming a pit in which a reactor pressure vessel is positioned. A steam generator on the outside of the shield is connected with the pressure vessel via coolant pipe lines which extend through the shield, the coolant circulation being provided by a coolant pump which is also on the outside of the shield. To protect these components on the outside of the shield and which are of mainly or substantially cylindrical shape, semicylindrical concrete segments are interfitted around them to form complete outer cylinders which are retained against outward separation radially from the components, by rings of high tensile steel which may be interspaced so closely that they provide, in effect, an outer steel cylinder. The invention is particularly applicable to pressurized-water coolant reactor installations.