Abstract: Disclosed is apparatus and method which, in cooperation with an electrical system, analyzes signals generated by detectors placed in a flux field of gamma rays and neutrons. A first detector with a first sensor is coupled to the electrical system. A second detector with a second sensor is coupled to the first sensor and the electrical system. A fissile material is housed in the first detector, and is heatable by gamma ray and neutron capture to in turn heat the first sensor, which generates a first signal which is delivered to the electrical system. A non-fissile material is housed in the second detector, and is heatable by gamma ray capture to in turn heat the second sensor, which generates a second signal. The first and second signals are analyzed in the electrical system to determine the power level, neutron flux, and gamma ray flux within the flux field. Also provided is a microtechnology apparatus and method for measuring neutron flux.

Abstract: The present invention described a signal conditioner. A thermocouple produces a signal that is present at a summing node input of a conditioning amplifier. The conditioning amplifier has a plurality of selectable gain values by which amplifier sensitivity may be varied to complement that of the thermocouple. Provision is made at the summing node input of the summing amplifier for thermocouple cold junction compensation and range offset. The present invention finds application in monitoring thermal conditions in an industrial process, such as a nuclear reactor. The high degree of precision and reliability required in such processes is maintained by including a test circuit which provides a selectable test pulse to the summing node input of the conditioning amplifier. One aspect of the present invention is the provision for testing during actual circuit operation in a process and irrespective of selected conditioning amplifier sensitivity.

Abstract: In a fuel assembly for a nuclear reactor a fuel element spacer formed of an array of laterally positioned cojoined tubular ferrules each providing a passage for one of the fuel elements, the elements being laterally supported in the ferrules between slender spring members and laterally oriented rigid stops.

Abstract: A rhodium self-powered detector, a fission chamber, and appropriate electronic circuitry for combining the output of the self-powered detector and the fission chamber are disclosed in combination wherein the combined output of the self-powered detector and the fission chamber is always proportional to the local reactor power level or neutron flux density in a nuclear reactor.

Abstract: A method for fabricating a thermocouple unit for service in and about nuclear reactors and other radioactive environments. The method provides a thermocouple encapsulated within a sphere of fissile material.

Abstract: An electronic circuit provides various accurate counts of detected neutrons to enable the assaying of fissile material in a neutron emitting radioactive source. The circuit develops a time correlated window associated with each detected neutron, and delays these windows to develop uncorrelated windows. These windows are used to develop separate detected neutron counts which distinguish between time correlated fission neutron detections and time uncorrelated singular neutron detections. The circuit also develops a count of all detected neutrons.

Abstract: There is provided a nuclear fuel element having a zirconium alloy cladding tube with improved corrosion resistance. The cladding tube comprises a metallurgical gradient across the width of the tube wall wherein the tube has a more corrosion-resistant metallurgical condition at the outer circumference and a less corrosion-resistant metallurgical condition at the inner circumference. The metallurgical gradient can be generated by heating an outer circumferential portion of the tube to the high alpha or mixed alpha plus beta range while maintaining the inner surface at a lower temperature, followed by cooling of the tube.

Abstract: An improved method for compression molding of typically brittle ceramic materials comprising uranium dioxide which enhances their compacting and cohering properties in the manufacture of nuclear fuel products. The uranium dioxide is mixed with a fugitive binder comprising a high molecular weight acrylic acid polymer and ammonium bicarbonate. The mixture is then pressed and sintered to expel the binder and to give a fissionable nuclear fuel pellet.

Abstract: A method of replacing a defective circumferential butt joint in a metal pipe is disclosed. An annular metal bridge ring, having a smaller wall thickness than the pipe but the same inside diameter, is positioned coaxial with the pipe in the relatively wide gap created by the removal of the defective joint. The ring becomes an integral part of the weld by being welded in place, thereby partially filling the gap between the edge surfaces of the pipe exposed by the removal of the defective joint. Subsequent layers of fusible material are weld deposited in place on top of the ring until the gap is filled to the exterior pipe surface. Use of the ring in the gap enables replacement of the defective joint with a single weld.

Abstract: A universal logic card is disclosed which contains both pre-programmed functional circuitry for actuating channel logic and dedicated test circuitry for system controller test and for constant and looping interrogation of the pre-programmed channel logic in absence of self-test system controller test. The disclosed card resides as a channel in a self-test system for a nuclear power plant supplementing the nuclear reaction protection system. The card is pre-programmed in digital logic to act equivalent to an analog circuit during actual plant operation. Additionally, the card responds to system controlled surveillance of the nuclear protection system. In system controlled surveillance, a central microprocessor serially addresses system circuit cards such as the one disclosed and loads these cards at predetermined input points with test commands. The addressed cards are thereafter simultaneously activated by a system-wide command.

Abstract: In a fuel assembly for a nuclear reactor a fuel element spacer formed of an array of laterally positioned cojoined tubular ferrules each providing a passage for one of the fuel elements, the elements being laterally supported in the ferrules between laterally oriented spring members and oppositely positioned rigid stops, the wall thickness of the ferrules being relatively large and the height of the ferrules being relatively small to reduce hydride concentration in the ferrule material while maintaining relatively low flow resistance.

Abstract: A method and system for quality control of nuclear fuel materials, said system including amplifier/integrator circuitry, signal processors, and drift control feedback circuitry. The invention permits the qualitative and quantitative measurement of paramagnetic additives such as gadolinium for example in a paramagnetic base nuclear fuel material including ferromagnetic impurities. Drift problems relating to temperature and other effects are solved electrically and mechanically. Analysis can be conducted irrespective of the form or composition of the nuclear fuel.

Abstract: In a nuclear fuel assembly spacer providing passages for fuel rods or other elongated elements, a spring component of H-shape including a pair of spaced spring members of hairpin-like configuration connected by a retaining strap wherein an arched side of one of the spring members projects into one of the passages and the arched side of the other of the spring members projects into an adjacent one of the passages for resilient engagement with the fuel rods or other elongated elements extending through the passages.

Abstract: An ultrasonic transducer for use in a high temperature environment and method for fabricating the same. A disk-shaped piezoelectric crystal is weakened in at least one surface in accordance with a predetermined line pattern relative to a first direction in that surface. The crystal is bonded to a thin lens material with a coefficient of thermal expansion dissimilar in this first direction. The predetermined line pattern is adapted to relieve stress in this first direction created by unequal rates of expansion or contraction of the crystal and the lens.

Abstract: Transport apparatus is disclosed for moving a stream of objects along a substantially continuous path between a source and a collection station and past a viewing station. A stream of successive, spatially separated objects is moved into end-to-end abutment to form successive stacks of objects. Each stack is spiraled past the viewing station with minimal vibration to expose the complete surface of each object to inspection. Subsequently each stack is rearranged into spatially separated objects which are rapidly sorted by diverting those objects from the continuous path which do not conform to predetermined criteria upon inspection. The transport apparatus achieves high throughput without compromising the accuracy of the inspection process.

Abstract: Method for precipitating and removing soluble metal compounds from solutions of phosphoric acid. The method is useful in the disposal of metal-containing phosphoric acid waste from electrolytic operations, including such acid solutions contaminated with uranium compounds.

Abstract: A method of controlling the bowing action of fuel channels used in nuclear reactor cores is disclosed. Each channel is heat treated and mounted in its control rod module with an orientation dependent on its prior heat treatment. Upon exposure to radiation, the channels will bow in a desired direction away from the control rod.

Abstract: Apparatus for remotely controlled examination of the control rod drive penetration stub tubes in the wall of a nuclear reactor pressure vessel including a rotatable carriage on which is mounted a reciprocable shaft to which is attached an inspection instrument for scanning the stub tubes.

Abstract: A stopper apparatus for use in blocking the unvalved nozzle of a cooling fluid filled nuclear reactor pressure vessel includes a plug, typically in the shape of a frusto-conical member having inflatable gaskets for sealing against a seat of generally unknown surface characteristics and means for positioning and urging the plug into position to seal the nozzle. The plug is typically positioned by suspension cables whereby the apparatus can be temporarily inserted and removed from the pressure vessel. The urging means is generally a two-way hydraulically driven jack controlled by remotely-actuated hydarulic lines. The apparatus is a tool which permits temporary sealing of a submerged outlet in a reactor vessel to permit maintenance on a fluid recirculation loop.

Abstract: A spacer for use in a fuel assembly of a nuclear reactor having thin, full-height divider members, slender spring members and laterally oriented rigid stops and wherein the total amount of spacer material, the amount of high neutron cross section material, the projected area of the spacer structure and changes in cross section area of the spacer structure are minimized whereby neutron absorption by the spacer and coolant flow resistance through the spacer are minimized.