Abstract: The static pressure within an air-supported structure is monitored and controlled in accordance with monitored environmental conditions. The static pressure is kept at the minimum value required to maintain the structures's integrity, thereby using a minimum amount of energy. As outside wind velocity incrementally increases, the static pressure is increased incrementally. Under certain weather conditions such as high winds and frozen precipitation, the static pressure is increased to a maximum limit. As a safety feature, a secondary inflation device is activated to assist a primary inflation device to quickly increase pressure in the structure in response to a sudden loss in pressure.

Abstract: The static pressure within an air-supported structure is monitored and controlled in accordance with monitored environmental conditions. The static pressure is kept at the minimum value required to maintain the structure's integrity, thereby using a minimum amount of energy. As outside wind velocity incrementally increases, the static pressure is increased incrementally. Under certain weather conditions such as high winds and frozen precipitation, the static pressure is increased to a maximum limit. As a safety feature, a secondary inflation device is activated to assist a primary inflation device to quickly increase pressure in the structure in response to a sudden loss in pressure.

Abstract: An apparatus for loading nuclear fuel rods through spacer grid cells of a fuel bundle includes a handle having at least one elongate clip joined thereto, and a flexible tubular sleeve joined to the clip. The clip rigidly supports the sleeve along its longitudinal axis while allowing the sleeve to unfurl perpendicularly thereto for disassembly from a fuel rod. In several embodiments of the invention, the clip may include a slot for bridging adjacent grid cells during assembly, or the clip may be removably fixedly joined to the handle for allowing easy replacement of the sleeves.

Abstract: A method and apparatus measure squareness of an end of a rod relative to a longitudinal centerline axis thereof without requiring rotation of the rod. The apparatus includes a flat plate mounted substantially perpendicularly to the rod centerline axis. The method positions the plate in abutting contact with the rod end, and a tilt angle of the plate in abutting contact with the rod end is measured for determining squareness of the rod end.

Abstract: A nuclear fuel pellet loading system includes pellet handling apparatus and cladding tube handling apparatus functionally interfaced by a bushing assembly. Pellet rows of varying zone lengths are alternately built up on two tracks, measured for zone length, weighed and then loaded by separate pusher carriages through separate bushing assembly passageways into a pair of empty cladding tubes indexed into loading positions by the tube handling apparatus. Separate zone interface tapes affixed to the pusher carriages indicate to an operator the length each pellet zone is to be built to. The tube handling apparatus accommodates cladding tubes of varying lengths and is equipped to automatically read a serial number imprinted on each tube endplug.

Abstract: To measure the gaps between fuel rods in a fuel assembly, a feeler gauge is provided with a pair of resilient arms having elongated electrical resistance strips carried by their confronting surfaces and extending from terminations adjacent the free ends of the arms through a contact point of electrical inter-engagement. The strip terminations are wired into a metering circuit including a current source and an ammeter. When the arm free ends are positioned in a rod gap, the position of the contact point relative to the strip terminations determines the magnitude of resistance included in the metering circuit, and the meter registers the gap dimension.

Abstract: The disclosed invention comprises a method for assembling fuel bundles for service in nuclear reactors which minimizes damage to the assembled components of a nature that renders the components susceptible to destructive corrosion in service, and the enhanced product of the improved method. The invention includes the utilization of a temporary protective barrier, such as water soluble sodium silicate or gelatin, intermediate the components during assembly.

Abstract: To measure the dimensional characteristics of elongated flow channels for nuclear fuel rod assemblies at the manufacturing site, an upender is utilized to swing a flow channel from a horizontal loading orientation to an upright pre-measurement position and then to shift the flow channel laterally into a measurement position where it is engaged and held by reciprocatingly mounted upper and lower endplugs while its dimensional characteristics are acquired by a measurement carrige mounted for vertical scanning movement along the entire flow channel length.

Abstract: To qualify the heights of inwardly projecting nuclear fuel rod-positioning stops formed in the sidewall of tubular ferrules 12 utilized in fuel bundle spacers, an automated gauging apparatus, seen in FIG. 6, is provided to handle successive ferrules on an automated basis. The apparatus includes an orienting station 32 for longitudinally reorienting each ferrule, if necessary, and angularly orienting each ferrule in a pickup position. A mechanism 68 picks each ferrule from its pickup position and places it on an arbor 84 with the rod-positioning stop surfaces bearing against arbor reference surfaces. A plurality of eddy current probes 96 (FIG. 8) are positioned to measure the proximity of ferrule peripheral surface sites adjacent the stops and thus provide output gauging signals indicative of the heights of the various stops.

Abstract: To form longitudinally spaced pairs of angularly spaced stops in the walls of fuel rod-positioning ferrules utilized in nuclear fuel bundle spacers, the ferrules, cut from tubular stock, are longitudinal oriented in a first station and angularly oriented in a second station using a reference notch cut in one ferrule edge. Successive ferrules are picked from the second station and placed in a die of a punch press. Ferrule exterior surface back-up is provided by the die upon closure, and interior surface back-up is provided by a mandrel inserted in the ferrule bore as the punches converge into stop-forming engagement with the ferrule wall. Formed ferrule discharge is induced by placement of the next ferrule in the die.

Abstract: To assemble nuclear fuel bundle spacers comprised of a multiplicity of rod-positioning ferrules, automated apparatus is provided comprising an indexing table mounting a plurality of identical, angularly spaced ferrule fixtures which are successively positioned at a first station for receipt of a pair of properly oriented ferrules. The table is indexed to present the ferrule pairs in turn to a second station where a spring is loaded in pre-assembly relation thereto. At the next table index position, a third station manipulates the successive fixture-mounted ferrule pairs to interlock the spring with each ferrule pair as a subasssembly which is then indexed in turn to a fourth station for assembly into a spacer fixture.