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 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: 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 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 typical embodiment of the invention provides a combination feedwater and "cooldown" water spray head that is centrally disposed in the lower portion of a nuclear power plant steam drum. This structure not only discharges the feedwater in the hottest part of the steam drum, but also increases the time required for the feedwater to reach the steam drum shell, thereby further increasing the feedwater temperature before it contacts the shell surface, thus reducing thermal shock to the steam drum structure.

Abstract: In an illustrative embodiment of the invention, a nuclear reactor pressure vessel, having an internal hoop from which the heated coolant emerges from the reactor core and passes through to the reactor outlet nozzles, is provided with annular sealing members operatively disposed between the outlet nozzle and the hoop and partly within a retaining annulus formed in the hoop. The sealing members are biased against the pressure vessel and the hoop and one of the sealing members is provided with a piston type pressure ring sealing member which effectively closes the path between the inlet and outlet coolants in the region about the outlet nozzle establishing a leak-proof condition. Furthermore, the flexible responsiveness of the seal assures that the seal will not structurally couple the hoop to the pressure vessel.

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 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: 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.

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 co-ordinated control system for a nuclear power producing unit having a pressurized water reactor, a plurality of once through steam generators through which the coolant from the reactor is circulated in parallel, and a turbine generator supplied steam from the steam generators for the production of electric power.

Abstract: A fluidic device having a sensing nozzle remotely mounted from an emitter assembly and communicating with it through a connecting tube. An adjustable nozzle assembly, located within the emitter assembly, is movable with respect to an outlet and aligned orifice to provide a zero level output signal from the outlet for various lengths of connecting tube. The nozzle assembly is also adjustable to provide a range independent zero level output signal for different pressure level sensitivities. A test jack communicates with the outlet to monitor the output signal and provide for adjusting the zero level output signal.

Abstract: A typical embodiment of the invention is a steam drying device that has a frame with two recessed slipways spaced from each other. A first array of longitudinally disposed bars within the frame are spaced transversely from each other. The ends of the bars in this first array, moreover, are received within respective slipway recesses. There also is a second array of longitudinal bars, the ends of which are received in respective slipways, the bars in both arrays being transversely spaced from each other to enable the bars to remove water droplets from the steam.

Abstract: In an illustrative embodiment of the invention, a nuclear reactor pressure vessel, having an internal hoop from which the heated coolant emerges from the reactor core and passes through to the reactor outlet nozzles, is provided with sealing members operatively disposed between the outlet nozzle and the hoop. The sealing members are biased against the pressure vessel and the hoop and are connected by a leak restraining member establishing a leak-proof condition between the inlet and outlet coolants in the region about the outlet nozzle. Furthermore, the flexible responsiveness of the seal assures that the seal will not structurally couple the hoop to the pressure vessel.

Abstract: An illustrative embodiment of the invention is directed to a thermally insulated exhaust duct structure. In this regard, a typical duct comprises an inner stainless steel conduit and one or more sheets of highly-reflective material that are spirally wrapped around and spaced outwardly from the outer surface of the conduit. The adjacent layers of the sheet material, moreover, are spaced from each other a predetermined distance through corrugated strips that are fastened to one side of the sheet material. Thus, when wound about the conduit in an overlaying relationship, the corrugation peaks bear against the sheet of material that is immediately below and thereby estabish a spacing between adjacent layers that is at least equal to the depth of the corrugations. Other features of the inventon include an outer protective stainless steel casing that fits over the spirally wrapped insulating sheet and a roof penetration for the duct structure.

Abstract: A pulsed flow process for the reduction of UF.sub.6 where the process may be continuous or batch starting without a seed bed. The initial amplitude and frequency of the pulsed flow is altered as a bed of particle-form material is formed and thereafter the particle-form product of the reaction is removed from the reaction zone.

Abstract: A coal slurry drier which comprises a pulverizer having a housing enclosing a pulverizing zone including horizontally disposed upper and lower grinding rings. A circular row of rotatable grinding elements is positioned between the upper and lower rings. Heated carrier air is passed through the pulverizing zone. A conduit delivers the coal slurry to the pulverizer for drying and pulverization. The conduit includes an insulated portion extending through the housing and has its outlet located within the pulverizing zone.

Abstract: The invention relates to a hydrotest plug useful in testing the structural integrity of pressure tube arrangements, piping and the like as well as a method for using the same. The hydrostatic test plug comprises a conventional plug with internal passages providing conduit means for injection of a fluid adhesive, air escape means and centering means.

Abstract: A typical embodiment has an end fitting for a nuclear reactor fuel element that is joined to the control rod guide tubes by means of a nut plate assembly. The nut plate assembly has an array of nuts, each engaging the respective threaded end of the control rod guide tubes. The nuts, moreover, are retained on the plate during handling and before fuel element assembly by means of hollow cylindrical locking cups that are brazed to the plate and loosely circumscribe the individual enclosed nuts. After the nuts are threaded onto the respective guide tube ends, the locking cups are partially deformed to prevent one or more of the nuts from working loose during reactor operation. The locking cups also prevent loose or broken end fitting parts from becoming entrained in the reactor coolant.

Abstract: Illustrative embodiments of the invention disclose fuel pellets for nuclear reactors in which the pellets have a controlled and relatively homogeneous porosity that accommodates fuel swelling and permits fission gases to escape from these pellets. Typically, small low density spheres, that may be formed from highly volatile material, are blended with a nuclear fuel powder, and are pressed and sintered into pellets of appropriately low density to produce an improved product.