Abstract: A typical embodiment of the invention detects leaking fuel rods by means of a radiation detector that measures the concentration of xenon-133 (Xe.sup.133) within each individual rod. A collimated detector that provides signals related to the energy of incident radiation is aligned with one of the ends of a fuel rod. A statistically significant sample of the gamma radiation (.gamma.-rays) that characterize Xe.sup.133 is accumulated through the detector. The data so accumulated indicates the presence of a concentration of Xe.sup.133 appropriate to a sound fuel rod, or a significantly different concentration that reflects a leaking fuel rod.BACKGROUND OF THE INVENTION1. Field of the InventionThis invention relates to inspection techniques, and more particularly, to a radiation detection method and apparatus for identifying leaking fuel rods within a nuclear reactor core, and the like.2.

Abstract: An illustrative embodiment of the invention provides a control rod system locking device adapted to engage an elongated extension shaft, releasably coupled at one end to the control rod assembly and releasably coupled at its other end to the control rod drive, to prevent rotation of the shaft about its longitudinal axis with respect to the control rod assembly.

Abstract: An apparatus for testing the similarity in cross section and the disposition of each relative to a common axis of a plurality of similar bores formed in a burner tip and distributed around the axis.

Abstract: A support system and method for supporting parallel tubes. A looped tube support clamp comprising a channel base with scalloped arcuate passages for tube support, the sides of the passages forming upright tabs containing a slotted hole suitable for the passage therethrough of a tapered forming tool causing a clamping action to result on the tubes adjacent the looped tab.

Abstract: An impeller comprising a pair of axially adjacent plate members. Each of the plate members is formed with a hub and a plurality of laterally spaced segments extending outwardly from the hub. The plate members are coaxially mounted on a burner nozzle guide tube, with the plate member nearest the nozzle outlet being fixed to the guide tube and the other plate member being rotatable about its central axis to regulate the free flow area between segments.

Abstract: A pneumatically buffered drive system is provided which quickly moves a movable member, such as a press safety curtain or press bolster, a predetermined length in three sequential speed stages to prevent maximum acceleration from occurring at the end of the predetermined length. The movable member is coupled to a differential pressure piston which is initially pressurized on only one side of the piston to initiate movement. After traversing approximately half the predetermined length both sides of the piston are pressurized to decelerate the piston during the member movement for approximately the next third of the predetermined length. The remaining length is traversed with the decelerating pressure being vented to positively finish the motion along the predetermined path. In vertical moving members having significant mass such as press safety curtains, a higher pressure is used to decelerate the piston than the pressure used to drive the piston.

Abstract: A composite transducer for the measurement of a physical condition such as, but not limited to, temperature, pressure, liquid level, rate of flow, concentration of a constituent gas in a mixture of gases, or neutron flux density; wherein the output signal of a prompt responding but relatively inaccurate sensor is combined with the output signal of a slow responding but relatively accurate sensor to generate a composite transducer output signal having a response time comparable to that of the fast responding sensor and an accuracy equal to that of the slow responding sensor.

Abstract: A flexible insulating blanket attached to a metal backing with adjustable panels about the backing is used to cover the opening of a carbon anode baking furnace to bring about sealing contact between the cover and the furnace walls so as to minimize thermal requirements and losses from the furnace.

Abstract: An upright conduit and disperser which provide the acceleration and uniformity of particle dispersion required for a smooth transition from dense to dilute phase in the pneumatic conveyance of gas entrained particles.

Abstract: A hydraulically balanced face type shaft seal is provided in which the opening and closing seal face areas retain concentricity with each other in the event of lateral shaft displacement. All of the areas affected by the hydraulic force balance are embodied either by the rotating or stationary seal member, and the radial width of the sealing face of a second seal member is sufficiently wider than that of the first member so as to preclude runoff at maximum lateral displacement of the shaft at the seal.

Abstract: A self contained nut assembly to allow self nut locking and unlocking for use with a support member. The nut assembly comprises an upper nut containing a pronged locking sleeve. The nut and locking sleeve fit onto a threaded element projecting through a support member. The prongs of the locking sleeve are fashioned with feet for engagement with the support member to restrain selective movement therebetween. Arcuate portions of the sleeve are flared to fill openings in the nut thus locking the assembly in place.

Abstract: A high temperature non-conducting inorganic refractory adhesive suitable for use in conjunction with a number of substances including conducting elements metallic in nature.

Abstract: A heat exchanger in which mutually reactive heat transfer fluids are utilized. Tubes are interposed coaxially with other tubes so as to form a limited volume, wherein these fluids can mix and react in a controlled manner, permitting detection of leakage across the boundaries separating the reactive fluids before a major chemical or physical reaction can occur.

Abstract: A control rod ejection retardation assembly is mounted to a control rod assembly of a nuclear reactor to retard the ejection of the control rod only during an undesired ejection of the control rod while allowing normal control rod movement and "scramming" operation to be drag free and unretarded. The ejection retardation assembly includes a piston assembly mounted to the control rod and having an opening thereto controlled by a ball valve. The piston assembly seals are made loose fitting to allow sufficient fluid flow through the seals to provide unhindered normal control rod movement even with the ball valve sealing the piston assembly opening. During undesired speedy ejection of the control rod, the ball valve seals the opening to prevent fluid flow to the piston assembly retarding piston movement and thereby controlling control rod movement.

Abstract: A system for the automatic repetitive transfer of rough workpieces from a conveyor to the machining position in a machine tool and the transfer of finished workpieces from the machining position to the conveyor.

Abstract: A nuclear reactor pressure vessel nozzle penetration device for fluid coolant delivery to the reactor core or to modular heat exchangers located within the vessel is described. The nozzle penetration device comprises a nozzle conduit having an annular double wall open at one end with thermal insulation therebetween, having the outer wall end attached to a portion of the reactor pressure vessel and disposed radially therefrom forming an air space therebetween.

Abstract: A steam and water drum internal arrangement which provides free access to the drum inner wall and facilitates the removal of the steam and water separators from within the drum by mounting the separators on a duct which extends centrally of the drum and communicates with extension conduits to receive a steam and water mixture from the steam generating tubes.

Abstract: A typical embodiment of the invention provides a means for restraining the fuel elements within a nuclear reactor core from movement during reactor operation. Illustratively, within one of the fuel element end fittings a rectangular grid of torsion bars is positioned with the ends of each of the bars anchored in opposing parallel sides of the end fitting. Individual torsion arms fastened to the midportion of each of the respective torsion bars protrude above the end fitting to bear against the adjacent grid pads and thereby restrain motion in the direction of coolant flow. In the opposite fuel element end fitting a tube that extends through the length of the fuel element is connected to the center of a convex spring. The two ends of the spring are hinged to respective locking bars that are cammed to move in a direction that is transverse to the axis of the tube. As the fuel element moves in the direction of coolant flow, the tube presses the convex spring flat.

Abstract: A typical embodiment of an integral pressurized water nuclear reactor and straight-tube steam generator combination in accordance with the invention includes a generally cylindrical pressure vessel that is assembled from three segments which are bolted together at transverse joints to form a fluid and pressure tight unit that encloses the steam generator and the reactor. This novel construction permits primary to secondary coolant heat exchange and improved control rod drive mechanisms which can be exposed for full service access during reactor core refueling, maintenance and inspection.

Abstract: The invention pertains to a device for accepting axial forces generated during the operation of a nuclear reactor by the flow of the cooling medium and the thermal expansion of the fuel assemblies consisting of rod-shaped fuel rods while the fuel assemblies are resting on a lower grid plate and at the upper end are elastically supported against an upper grid plate.