Abstract: A method is disclosed for the compaction of control rod blades and fuel channels of a boiling water reactor. Upper and lower portions of a control rod blade are removed from a cruciform shaped main blade structure. Each elongate tubular fuel channel of substantially square cross section is sectioned into four substantially congruent panels. A plurality of panels are stacked into each quadrant of the main blade structure substantially parallel to the long axis thereof.

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: An apparatus for underwater separation of a jet pump beam from the inlet mixer of a jet pump in a nuclear reactor system. The apparatus underwater cuts a retaining piece coupling the beam with the inlet mixer.

Abstract: A testable physically isolated control circuit includes a first unit 10, a second unit 40, and an optical coupler 30 to couple units 10 and 40 together. The functional portion 10a of the first unit includes an input terminal 11 and an oscillator 12 for controlling a first transmitter 17. Signals from the first transmitter are received by a receiver 44 in unit 40 to control the relay 48. Each unit 10 and 40 also includes a testing portion 10b and 40b for monitoring the condition of the functional portions. The testing portion 40b detects the state of the receiver 44 and the relay 48 and transmits this information via transmitter 65 to a receiver 22 in first unit 10. This receiver 22 controls input terminals 29 and 15 to provide control information concerning the proper functioning of the circuit.

Abstract: A pressure sensitive, toroidal magnetostrictive core wound with primary and secondary coils providing inputs to self-checking circuitry for analyzing operability status and providing redundant pressure measurement options is described. Pressure sensing assemblies are presented which are useful for measuring hydrostatic pressure or concentrated loads.

Abstract: A testable physically isolated control circuit includes a first unit 10, a second unit 40, and an optical coupler 30 to couple units 10 and 40 together. The functional portion 10a of the first unit includes an input terminal 11 and an oscillator 12 for controlling a first transmitter 17. Signals from the first transmitter are received by a receiver 44 in unit 40 to control the relay 48. Each unit 10 and 40 also includes a testing portion 10b and 40b for monitoring the condition of the functional portions. The testing portion 40b detects the state of the receiver 44 and the relay 48 and transmits this information via transmitter 65 to a receiver 22 in first unit 10. This receiver 22 controls input terminals 29 and 15 to provide control information concerning the proper functioning of the circuit.

Abstract: An apparatus is disclosed which measures forces resisting the movement of pistons in a control rod drive mechanism in a nuclear reactor and which includes pressure sensing means and further includes hydraulic circuitry to divert pressurized fluid from a normal operating conduit to a selected shunt conduit containing a valve having a particular fluid control characteristic, said shunt conduit directing the fluid to a selected piston to move said piston and said pressure sensing means measuring the pressure of the fluid during the motion of said piston to give an indication of the force needed to achieve such motion.

Abstract: A testable load driving circuit apparatus includes a solid-state load driver for controlling AC current loads coupled in series with a winding of a saturable core reactor used for sensing the presence or absence of load current through a load current monitor which is coupled to another winding in the reactor. The load driving circuitry may be tested during circuit operation by injecting a signal of insufficient duration to substantially affect the load circuit.

Abstract: A jet pump plug for a multi-nozzle jet pump is disclosed wherein the nozzles are accessible through a relatively small opening in the pump structure. The plug comprises a plurality of sections, each including a closure plate and a lever coupled thereto. Each plug section is constructed so as to allow that section to be separately introduced into the opening to the vicinity of the nozzles from a location which may be remote from the pump. The closure plates are manipulated through their attached levers from a remote location to the end of sealing the nozzles with them. The first plug section introduced through the opening includes means for alignment relative to the jet pump structure so as to orient its closure plate with respect to the nozzles. The remaining plug section is supported by the first plug section upon being introduced into the opening.

Abstract: A method and apparatus for loading nuclear fuel pellets in levels onto a horizontally and vertically indexing tray string-by-string. The apparatus includes a belt feeder assembling each string at a location on pivotal blades over the tray. Arrival is optically noted and a pusher delivers the string to a drop site, completely loading the string onto the blades for delivery to the indexing tray.

Abstract: A method and apparatus for analyzing combined secondary and primary materials by directing primary radiation onto said material whereby secondary radiation is generated. A detector senses the secondary radiation as a transport carries the materials into the vicinity of primary radiation and produces signals to be resolved into secondary and primary material source components, establishing a secondary to primary material ratio and indicating the composition of the material.

Abstract: A pump system wherein a pressure drop exists across a throttle bushing surrounds a rotating shaft. The throttle bushing comprises an internal annular debris-collecting groove disposed inwardly from the higher pressure end of the bushing and in communication with an internal helical groove extending across the bushing to the opposite low pressure end thereof. The outer wall of the annular debris-collecting groove, the higher pressure end of the bushing, and the internal annular surface of the bushing therebetween all cooperate in defining a lip which deters oversized debris from entering between the lip of the shaft surface. The lip, helical groove and annular debris-collecting groove cooperate to purge the bushing of debris and thus enhance the efficiency and wear life of the bushing.

Abstract: A method for controlling hydrogen charging of hydride forming metals through a window of a superimposed layer of a non-hydriding metal overlying the portion of the hydride forming metals to be charged.

Abstract: An improved method for producing nuclear fuel containers of a composite construction having components providing therein a barrier system for resisting destructive action by volatile fission products or impurities and also interdiffusion of metal constituents, and the product thereof. The composite nuclear fuel containers of the method comprise a casing of zirconium or alloy thereof with a layer of copper overlying an oxidized surface portion of the zirconium or alloy thereof.

Abstract: The multistage injection of water into the pressure vessel of a nuclear reactor including the steam-driven injection of water using steam generated by the reactor, the stages of injection subject to the cooling of water heated by the steam, whereby the pressure level of the water injected is boosted in stages.

Abstract: Means for discriminating the corrosion susceptibility of alloys of zirconium in an environment of a water cooled, nuclear fission reactor.

Abstract: Solutions or slurries of waste material in water are dewatered and encapsulated within a polymer for disposal, comprising the operations of removing water therefrom with azeotropic mixture evaporation and encasing the dewatered waste residue in an organic polymer. The method and system disclosed are especially useful for the safe disposal of radioactive waste.

Abstract: A process for recovering soluble uranium with an anion exchange system from carbonate-containing water. The process includes means for overcoming the deleterious effects upon the ion exchange system of carbon dioxide gas resulting from the carbonate-contents of the water in the presence of an acidic elutriate.

Abstract: A method for improving the physical properties of pressed bodies or pellets formed of particulate nuclear fuel material containing uranium dioxide. The green or unfired pressed bodies comprise a fugitive binder dispersed through the particulate fuel material.

Abstract: An arrangement for crimping a malleable sleeve over a hole in a punctured nuclear fuel rod in order to prevent the escape of fission gases into the external environment. The arrangement operates underwater and includes jaws for crimping the sleeve onto the fuel rod, which are operated by a hydraulic cylinder. The jaws crimp circumferential sealing ridges onto the inner surface of the sleeve, which bear against the fuel rod.