Abstract: A method for sputter coating the inside surface (30) of a fuel assembly tubular component (10) such as a control rod guide tube (200) with wear or corrosion resistant material. The steps include supporting the component tube in a fixture (12,14) and supporting a source tube (100,300) of e.g., wear resistant material, coaxially within the component tube, thereby defining a cylindrical annulus (24) between the tubes. The annular space is evacuated and backfilled with an inert working gas (26) such as argon, to a pressure sufficient to sustain a plasma discharge. The component tube is positively biased (36) as an anode, and the source tube is negatively biased (34) as a cathode, such that a plasma of the working gas is established in the annular space. A circumferential magnetic field is generated around the source tube to confine and shape the plasma whereby the source tube is bombarded with ions from the plasma substantially uniformly over the length of the source tube.

Abstract: A fuel assembly supporting structure for a nuclear reactor fuel assembly which comprises a two-way shape-memory alloy. A shape-memory alloy is selected which has an overall transition temperature range substantially above atmospheric temperature and substantially below a temperature experienced by the shape-memory alloy under reactor operating conditions. By using a shape-memory alloy in the design, the support structure assumes a first configuration for securely supporting one or a plurality of nuclear reactor components at a temperature above the overall transition temperature range and assumes a second configuration for loosely engaging the reactor components below the transition temperature range.

Abstract: A steam line plug support tool for maintaining steam line plugs in steam line nozzles during the local leak rate test of boiling water reactors which includes an elongated beam with a support piece attached at a location to coincide with the steam line plug. The steam line plug support tool may optionally have a steam line plug attached to the support plate so that the support tool may be used for both installation and support.

Abstract: A device for sealing a penetration in a pressurizer of a nuclear steam supply system includes a hollow cylinder adapted to be inserted into the heater sleeve, in place of the heater. The cylinder includes a nose portion formed with a number of axially extending slots defining therein a number of radially displaceable segments, each of which has an outwardly extending flange, proximate its distal end, which is engageable with the heater sleeve to resist blowout. A rod, inserted into the cylinder, seals the passage therethrough while locking the displaceable nose portion segments in their sleeve-engaging position. An annular soft nickel band on the outside of the cylinder engages the inner surface of the heater sleeve to provide an effective seal therebetween.

Abstract: Apparatus (100) for pulling a projecting tube (14) from a tube sheet (12), along the tube axis (18), comprising a base (200) for engaging the tube sheet and a jacking assembly (300) mounted on the base and actuable by a first fluid pressure variation between extended and retracted positions (302) away from and toward the base respectively. A substantially annular gripper assembly (400) is connected to the jacking assembly for extended and retracted movement therewith and adapted to coaxially receive the tube. The gripper assembly includes a housing (404) having a gripper piston chamber (410) in which a second fluid pressure variation can be introduced into the gripper piston chamber. A gripper piston 420 is situated for movement in the gripper piston chamber in response to the second fluid pressure in the chamber.

Abstract: The invention provides integration of the automatic semiautomatic and manual modes on a single man-machine interface device (200,400), with the master control of a system parameter such as pressurizer level, which is responsive to at least two system components (charging pumps, letdown valves), each of which can adjust a different system variable. The setpoint for automatic master control, is selected and displayed (216) on the device, along with the current value (212) of the setpoint parameter (pressurizer level). In the semiautomatic master mode selectable by the operator on the device, either a setpoint (272) or an output demand (282) can be specified for one of the components (206), and the master controller will then adjust the other component (204) accordingly. When all subgroup controls are in the manual mode, the master controller is completely overridden by operator control of each component or subgroup.

Abstract: An auxiliary platform has a one-ton hoist which may be used in conjunction with a rigid pole handling system. The positioning of the one-ton hoist, as well as the positioning of a trolley on which the hoist is mounted and the positioning of the platform, is centrally controlled at a control panel. In one embodiment, a new set of tracks are provided on either side of a refueling pool. A pair of cavity platforms are installed over the edges of the reactor cavity to receive the new set of tracks and to thereby allow the auxiliary platform to travel over the reactor cavity. In another embodiment, the existing tracks are extended and a single new track is provided between the equipment pool and the reactor pressure vessel head pedestal and spent fuel cask washdown area. The auxiliary platform is made extendable so that it can travel over the width of the existing tracks and also over width defined by the new track and one of the existing tracks.

Abstract: An advanced control room complex for a nuclear power plant, including a discrete indicator and alarm system (72) which is nuclear qualified for rapid response to changes in plant parameters and a component control system (64) which together provide a discrete monitoring and control capability at a panel (14-22, 26, 28) in the control room (10). A separate data processing system (70), which need not be nuclear qualified, provides integrated and overview information to the control room and to each panel, through CRTs (84) and a large, overhead integrated process status overview board (24). The discrete indicator and alarm system (72) and the data processing system (70) receive inputs from common plant sensors and validate the sensor outputs to arrive at a representative value of the parameter for use by the operator during both normal and accident conditions, thereby avoiding the need for him to assimilate data from each sensor individually.

Abstract: A black liquor gasification system intended for use as a replacement for a Tomlinson cycle, Chemical Recovery Unit, and which operates at a temperature below the ash melting temperature thereby removing the potential for smelt-water reactions and explosions. The subject black liquor gasification system is based on the use of a circulating fluidized bed operating at atmospheric pressure that produces dry, recoverable salts as well as low calorific gases to be used within the paper-making process.

Abstract: A flow deflector grid (10) for a nuclear fuel assembly, comprising a plurality of metal strips (12,14) which intersect in a regular array to form an egg-crate type lattice, which defines a plurality of coolant flow channels (16). Each channel has sidewalls (42,44) defined by the strips, a height dimension defined by the height of the strips, a plurality of corners (46) defined by the strip intersections (26), a channel central axis parallel to the height dimension, and a flow cross section normal to the channel axis for coaxially receiving a fuel rod (18) spaced within the channel sidewalls. A unitary flow deflector member (30) is attached to and situated in the corner of each channel so as to be cradled between first and second sidewalls.

Abstract: A tube stop for cooperation with a tube and fin furnace wall and a horizontal buckstay which includes first and second generally parallel generally planar spaced plates, apparatus for attachment of the first and second generally parallel generally planar spaced plates to the associated tube wall. A U-shaped plate has first and second opposed generally planar generally parallel space side walls, the first and second side walls being respectively disposed in spaced relation generally parallel relationship to the first and second generally parallel generally planar spaced plates, apparatus for coupling the first and second walls of the U-shaped member respectively to the first and second generally parallel generally planar spaced plates, and apparatus for rigidly coupling the U-shaped plate to the to the associated horizontal buckstay.

Abstract: A low pressure drop easy load fuel assembly rod end cap 40 for pressurized water reactor fuel assembly rods 10 has a solid Zircaloy radiused tip 42. The tip 42 blends into a longitudinal profile defined by a smooth convex curve 44,46 which blends into a substantially cylindrical surface portion 48 of a diameter substantially equal to the diameter of the fuel cladding tube or other shank 50.

Abstract: A liquid level measuring system for the steam drum of a steam generator employs a plurality of bubblers spaced along the length of the drum to obtain a level profile. The steam pressure to the bubblers is supplied by tubes connected to the steam/water inlet space which has a pressure significantly higher than the steam space in the drum. Horizontal pressure taps on each bubbler transmit the pressure to pressure cells external to the drum where the bubbler pressure is compared to the pressure in the steam space. These reading can then be converted to liquid level readings.

Abstract: A fuel rod for a nuclear reactor is described. The fuel rod contains a zirconium alloy cladding tube, with a thin coating of a burnable poison which has been plasmaarc sprayed on the inside diameter of the cladding tube. Also described is a plasma-arc spraying device and a method for applying a coating to the inside of a small-diameter metal tube.

Abstract: A stabilized alpha metal matrix provides an improved ductility, creep strength, and corrosion resistance against irradiation in a zirconium alloy containing on a weight percentage basis tin in a range of 0.4 to 1.0 percent and typically 0.5; iron in a range of 0.3 to 0.6 percent, and typically 0.46 percent; chromium in a range of 0.2 to 0.4 percent, and typically 0.23 percent; silicon in a range of 50 to 200 ppm, and typically 100 ppm; and oxygen in a range 1200 to 2500 ppm, typically 1800 to 2200 ppm. The high oxygen level assists in reducing hydrogen uptake of the alloy compared to Zircaloy-4, for example.

Abstract: A liquid-vapor separator for two-phase fluids in general and specifically a steam-water separator in a steam drum of a steam generator includes axial or radial spinner blades to create a centrifugal motion which causes liquid to be forced outward against the outer wall and the vapor to be concentrated in the center. Conical extraction skimmers systematically extract and discharge the liquid outwardly and downwardly through the side walls such that it impinges on an oval discharge screen surrounding the skimmers. The vapor flows out the top through a central opening and enters a secondary separator packed with crimped wire mesh encased in a perforated enclosure.

Abstract: A method of controlling the reheat steam temperature in a circulating fluidized bed combustion system wherein the circulating solids are cooled in a heat recovery fluid bed system containing reheat heat exchange surface. The rate of heat transfer and thus the reheat steam temperature are controlled by adjusting the flow rate of fluidizing air to the portion of the heat recovery fluid bed system containing the reheat surface.

Abstract: A method for enhancing the wear and corrosion resistance of a tubular nuclear fuel assembly component (40), comprising the step of coating the component with a corrosion and wear resistant material by an anodic arc plasma deposition process (70). The coating is preferably a nitride reactively formed during the plasma deposition process. The component is preferably a nuclear fuel rod cladding tube and the coating material is one of ZrN or TiN.

Abstract: A valve test unit (100) for attachment to a value (12) having a fluidly operated stem actuator (20a) responsive to a positioner device (24a). The unit includes a first input port (102) connectable to a source (104) of fluid pressure, a second input port (106) connectable to a source (108) of electrical power, a first output port (110) fluidly connected to the first input port, for delivering a controlled fluid pressure from the unit, and a second output port (114) electrically connected to the second input port, for delivering a controlled electrical signal from the unit. Test programs (118) are provided for converting fluid pressure, at the first input port, into a controlled, time dependent fluid pressure at the first output port and converting electrical power at the second input port into a controlled, time dependent electrical signal at the second output port.

Abstract: A permanent annular ring seal and refueling deck assembly providing an effective water barrier over the annular space between a nuclear reactor vessel flange and a surrounding annular ledge includes annular platform, a support and a joint seal.The joint seal has an upper straight walled cylindrical section and a lower flexible coil or arcuate shaped section which provides for greater accommodation of vessel radial, axial and rotational movements, and reduces joint stress.