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

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: 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 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: 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: 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.

Abstract: In a nucler reactor containment structure, a fuel transfer arrangement including a bridge, trolley, and grapple, each of the latter having a position sensor mounted thereon, and control means for determining the position of bridge, trolley, and grapple in response to signals from said position sensors, whereby fuel assemblies may be transferred between locations in the containment structure.

Abstract: In a nuclear fuel assembly having a coolant conducting or water tube which also retains the spacers in axial position, the fuel rods experience greater axial growth with exposure than the water tube creating a risk that the water tube might become disengaged from the supporting tie plates. An arrangement for preventing such disengagement is described including lengthened end plug shanks for the water tube, a protective boss surrounding the lower end plug shank to protect it from flow induced vibration, a conical seat for the lower end plug and an arrangement for limiting upward movement of the water tube.

Abstract: An amphibious end plug gauging device and method for determining the axial location of nuclear fuel element end plugs within or without the upper tie plate of a fuel bundle. The gauging device is maneuvered toward an underwater fuel bundle in a reactor service pool and its tip inserted in a preselected tie plate shank hole to engage the end of a fuel element in the bundle. The position of the fuel element relative the upper surface of the tie plate is registered on a dial indicator.

Abstract: A method and apparatus for the introduction of second cohesive powders into an improved fluidized bed blender containing UO.sub.2 powder, and for blending such second cohesive powders with the UO.sub.2 powder in the fluidized bed blender. The apparatus comprises an eductor, an improved pressurized vortec mill, a pneumatic conveying system that operates in turbulent flow, and an improved fluidized bed blender. The method and apparatus provide for injection and uniform dispersion of a second cohesive powdered ingredient or ingredients having hydrophobic, hydrophilic or hygroscopic properties in the fluid bed blender adjacent the bottom of the fluidized bed therein during the blending operation, thereby minimizing entrainment of the second powder mixture and providing a homogeneous blend of powders.

Abstract: An improved nuclear fuel element is disclosed for use in the core of nuclear reactors. The improved nuclear fuel element has a composite cladding of an outer portion forming a substrate having on the inside surface a metal layer selected from the group consisting of copper, nickel, iron and alloys of the foregoing with a gap between the composite cladding and the core of nuclear fuel. The nuclear fuel element comprises a container of the elongated composite cladding, a central core of a body of nuclear fuel material disposed in and partially filling the container and forming an internal cavity in the container, an enclosure integrally secured and sealed at each end of said container and a nuclear fuel material retaining means positioned in the cavity. The metal layer of the composite cladding prevents perforations or failures in the cladding substrate from stress corrosion cracking or from fuel pellet-cladding interaction or both.

Abstract: A process for treating water containing chemicals comprising ammonium nitrate, fluorides, hydrogen peroxide and uranium compounds, wherein valuable and/or hazardous components of the chemicals-containing water are separated therefrom and concentrated for recovery. The process includes an ion exchange operation in addition to manipulations of chemical components and pH conditions of the water by means of the application of reagents and adsorbents.

Abstract: The grain size of particulate uranium oxides is increased and adjusted by the application thereto of hydrogen peroxide. The procedure is useful in the manufacture of nuclear reactor fuel from powdered fissionable materials.

Abstract: Pumping and measuring apparatus for fluid metals comprising an electromagnetic pump which operates in two modes; first, an idling mode in which the pump operates at one rate of flow and continually circulates fluid metal out of a reservoir, through an opening in a conduit and back to the reservoir; second, a delivery mode in which the pump operates at a higher rate of flow and circulates fluid as in the idling mode, and further raises the fluid metal to a higher opening in the conduit for delivery therethrough. A timing control for selectively adjusting the durations of each mode as well as the time intervals between modes allows high accuracy of measurements of quantities of fluid metal delivered.

Abstract: An ultrasonic transducer apparatus and method for examining nuclear reactor jet pump beams for cracking. Examination is conducted in situ. An operator lowers a carriage portion of the apparatus into the reactor vessel with a pole. Ultrasonic signals are transmitted through suitable wiring from an external source to the transducer apparatus, which may employ a pitch-catch or pulse-echo mode of ultrasonic examination to test the beams. The carriage holds oppositely disposed pairs of ultrasonic transducers and positions them suitably near the beam to be examined in a proper orientation thereto. The mode of examination is selected by a switching mechanism. The apparatus includes a signal generator, receiver, and visual display.