Abstract: A hollow tapered tubular shaft formed of layers of carbonaceous fibers embedded in a resinous binder wherein each layer is oriented in different angles relative to an adjoining layer to provide a preferred physical characteristic to the tubular shaft.

Abstract: A grid or lattice structure for a nuclear reactor fuel element support in accordance with the invention includes two components that are successively joined by electron beam welding. Extruded cruciform bars which provide the lattice nodes and flat plates which interconnect these nodes, are for example, typical components. Electron beam welding these components together avoids the need for a filler metal, and the welding sequence avoids distortion, thereby obviating the need for post machining operations. Consequently, the plates and bars can be provided with machined positioning or fastening fittings before the lattice is assembled. Illustratively, studs on the cruciform bars are used to join these bars to the elementary plates that form the individual components of a reactor coolant flow distribution plate.

Abstract: An illustrative embodiment of the invention has a feedwater inlet conduit disposed withn a steam discharge nozzle for use in a power reactor system. Typically, the conduit and nozzle combination penetrate the wall of a reactor pressure vessel and support a heat exchanger within the pressure vessel structure.

Abstract: A nuclear reactor core stabilizing arrangement wherein a plurality of actuators, disposed in a pattern laterally surrounding a group of elongated fuel assemblies, press against respective contiguous fuel assemblies on the periphery of the group to reduce the clearance between adjacent fuel assemblies thereby forming a more compacted, vibration resistant core structure.

Abstract: A typical embodiment of the invention permits defective fuel rods to be identified with the fuel rods arrayed in a fuel element. A bell jacket is placed over the submerged plenum ends of the fuel rods in the fuel element and gas pressure is admitted to the jacket interior to expel water from the enclosed volume and expose the plenum ends of the fuel rods to the gas stream. The cooling effect of the flowing gas on steam rising within the interior of a defective fuel rod causes the steam to condense within the plenum and increase the temperature of the exposed end of the defective rod relative to the ends of the sound rods. An infra red or other suitable temperature detector identifies the higher temperature end of the defective rod for individual removal from the fuel element and replacement, as appropriate.

Abstract: A typical embodiment of the invention provides a means for selectively inserting and withdrawing one or more fuel rods from a fuel element cellular grid structure. The transverse stubs on one side of a long, thin bar are turned through 90.degree. to extend across the gap between mutually perpendicular grid structure plates. The extreme ends of these stubs engage the adjacent portions of the associated plates that form part of the grid cells. Pressing the stubs against the plate portions through the application of appropriate force in a longitudinal direction relative to the bar deflects the engaged plates through a sufficient distance to enable fuel rods to be inserted into, or withdrawn from, respective cells. After rod insertion, the force applied to the bar is released to enable the plates to relax and engage the fuel rods. The bars are rotated once more through 90.degree. and withdrawn from the grid structure. A similar procedure is employed to withdraw fuel rods from the grid structure.

Abstract: A process for treating the aqueous effluents that are produced in converting gaseous UF.sub.6 (uranium hexafluoride) into solid UO.sub.2 (uranium dioxide) by way of an intermediate (NH.sub.4).sub.4 UO.sub.2 (CO.sub.3) .sub.3 ("AUC" Compound) is disclosed. These effluents, which contain large amounts of NH.sub. 4.sup.+ (ammonium), CO.sub.3.sup.-.sup.- (carbonate), F.sup.- (fluoride), and a small amount of U (uranium), are mixed with H.sub.2 SO.sub.4 (sulfuric acid) in order to expel CO.sub.2 (carbon dioxide) and thereby reduce the carbonate concentration. The uranium is precipitated through treatment with H.sub.2 O.sub.2 (hydrogen peroxide) and the fluoride is easily recovered in the form of CaF.sub.2 (calcium fluoride) by contacting the process liquid with CaO (calcium oxide). The presence of SO.sub.4.sup.-.sup.- (sulfate) in the process liquid during CaO contacting seems to prevent the development of a difficult-to-filter colloid. The process also provides for NH.sub.3 (ammonia) recovery and recycling.

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: This invention relates to an improved system of providing power having a unique generating means of the nuclear reactor variety adapted with a plurality of steam generators in the form of replaceable modular units of the expendable type for the attainment of the optimum in effective and efficient vaporization of fluid during the process of generating power.

Abstract: A grid structure for holding a plurality of nuclear fuel rods. The grid structure is of the type having wall means, including rigidly interconnected generally rectangular metal strips, forming a plurality of passageways and adapted to support nuclear fuel rods within some of the passageways. The improvement comprises providing elongated slots intermediate and normal to the longitudinal edges of each of the strips at each intersection of the strips whereby the slots form openings in each corner of each passageway.

Abstract: A typical embodiment of the invention provides an efficient aid in positioning fuel elements in a nuclear reactor core. The corner edges of the peripheral band that binds the fuel element grid structure together, as well as the ends of the individual grid plates that protrude beyond the last marginal rows of fuel rods in each of the fuel elements are chamfered or bevelled. Thus, when fuel elements are being inserted, relocated or withdrawn from a reactor core the sloping edges of the grid structures in adjacent elements slide past without locking together or otherwise undesirably engaging each other.

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.