Patents Represented by Attorney Z. L. Dermer
  • Patent number: 4273076
    Abstract: Apparatus for removing sludge that may be deposited on a tubesheet of a steam generator comprises fluid headers at the elevation of the sludge to be removed for establishing a circumferential fluid stream at that elevation. A fluid lance is also provided for being moved along the line between the headers emitting a pulsating fluid jet perpendicular to a line of movement of the fluid lance at an elevation substantially corresponding to the level of sludge deposits. The fluid jet forces the sludge to the periphery of the tubesheet where the sludge is entrained in and carried away by the circumferential fluid stream.
    Type: Grant
    Filed: December 28, 1978
    Date of Patent: June 16, 1981
    Assignee: Westinghouse Electric Corp.
    Inventors: Edward J. Lahoda, Thomas H. Dent
  • Patent number: 4271471
    Abstract: A steam generator tubesheet is serviced by end effectors mounted on a slew table cantilevered from a carriage slidable along an arm rotatable in a plane parallel to the tubesheet. In servicing a selected hole in the tubesheet, the rotatable arm and the carriage arm are driven to positions which allow the cantilevered slew table to be slewed to a predetermined angle associated with the selected hole. The arm and carriage are then driven to positions which place the end effector under the selected hole taking into account the offset of the slew table. Alternatively, a determination is first made whether the arm and carriage can be positioned within preset limits to place the end effector under the selected hole using the existing slew angle. If so, the existing slewed angle is used but, if not, the table is slewed as mentioned above.
    Type: Grant
    Filed: December 28, 1978
    Date of Patent: June 2, 1981
    Assignee: Westinghouse Electric Corp.
    Inventor: Raymond P. Castner
  • Patent number: 4271369
    Abstract: A homopolar machine designed to operate as a generator and motor in reversibly storing and transferring energy between the machine and a magnetic load coil for a thermo-nuclear reactor. The machine rotor comprises hollow thin-walled cylinders or sleeves which form the basis of the system by utilizing substantially all of the rotor mass as a conductor thus making it possible to transfer substantially all the rotor kinetic energy electrically to the load coil in a highly economical and efficient manner. The rotor is divided into multiple separate cylinders or sleeves of modular design, connected in series and arranged to rotate in opposite directions but maintain the supply of current in a single direction to the machine terminals. A stator concentrically disposed around the sleeves consists of a hollow cylinder having a number of excitation coils each located radially outward from the ends of adjacent sleeves.
    Type: Grant
    Filed: February 10, 1978
    Date of Patent: June 2, 1981
    Assignee: The United States of America as represented by the United States Department of Energy
    Inventor: Roy E. Stillwagon
  • Patent number: 4269661
    Abstract: A top nozzle for a nuclear reactor fuel assembly which includes an orifice plate designed to receive control rod guide tubes extending upwardly from the top of the fuel assembly. Nozzle pin extensions connected to the orifice plate are axially coextensive with the guide tubes and project upwardly through a top nozzle hold-down plate, and through openings in the upper core plate in the reactor. The hold-down plate is spring biased into an upper core plate engaging position and since the pin extensions are adapted to move in the core plate and against the action of the springs, the top nozzle thus becomes effective in accommodating upwardly acting hydraulic forces which tend to lift the fuel assembly, and to accommodate differential expansion of parts in the fuel assembly as compared to the core barrel in which the assembly is located.
    Type: Grant
    Filed: June 15, 1978
    Date of Patent: May 26, 1981
    Assignee: Westinghouse Electric Corp.
    Inventors: Stanley Kmonk, Dennis J. Cadwell, Stephen J. Ferlan
  • Patent number: 4268356
    Abstract: A grid for a nuclear reactor fuel assembly which includes intersecting straps arranged to form a structure of egg crate configuration. The cells defined by the intersecting straps are adapted to contain axially extending fuel rods, each of which occupy one cell, while each control rod guide tube or thimble occupies the space of four cells. To effect attachment of each guide thimble to the grid, a short intermediate sleeve is brazed to the strap walls and the guide thimble is then inserted therein and mechanically secured to the sleeve walls. Each sleeve preferably, although not necessarily, is equipped with circumferentially spaced openings useful in adjusting dimples and springs in adjacent cells. To accurately orient each sleeve in position in the grid, the ends of straps extending in one direction project through transversely extending straps and terminate in the wall of the guide sleeve.
    Type: Grant
    Filed: July 14, 1978
    Date of Patent: May 19, 1981
    Assignee: Westinghouse Electric Corp.
    Inventors: Stanley Kmonk, John L. Alder, Francis R. Racki
  • Patent number: 4265010
    Abstract: Method and apparatus for adjusting the level of fuel rods in a fuel assembly which includes a tool having an end insertable between a fuel assembly nozzle plate and the exposed ends of fuel rods. The insertable end of the tool includes stationary and movable plates, the movable plate having a portion which rests on flanges in a forked end of the stationary plate while the other end of said movable plate is bent in a manner such that it lies above the stationary plate.
    Type: Grant
    Filed: November 24, 1978
    Date of Patent: May 5, 1981
    Assignee: Westinghouse Electric Corp.
    Inventors: Glenn D. Doss, Theodore W. Nylund
  • Patent number: 4265025
    Abstract: An inspection probe for inspecting tubular members comprises a housing having a plurality of feeler wires extending therefrom and into contact with the inner side of the tubular members. The inspection probe also comprises a radiation source and radiation sensors arranged in the probe so that the sensors can detect radiation from the source that has been reflected from the feeler wires. The sensors are arranged so that when the feeler wires encounter an irregularity in the tubular member the amount radiation reflected from the feeler wires to the sensors will change in relation to the size of the irregularity. Output from the sensors is calibrated to remotely indicate the size and location of the irregularity.
    Type: Grant
    Filed: November 8, 1978
    Date of Patent: May 5, 1981
    Assignee: Westinghouse Electric Corp.
    Inventors: James W. Finlayson, Harold P. Johnson
  • Patent number: 4259152
    Abstract: Method and apparatus for detecting failure in a welded connection, particrly applicable to not readily accessible welds such as those joining components within the reactor vessel of a nuclear reactor system. A preselected tag gas is sealed within a chamber which extends through selected portions of the base metal and weld deposit. In the event of a failure, such as development of a crack extending from the chamber to an outer surface, the tag gas is released. The environment about the welded area is directed to an analyzer which, in the event of presence of the tag gas, evidences the failure. A trigger gas can be included with the tag gas to actuate the analyzer.
    Type: Grant
    Filed: November 30, 1978
    Date of Patent: March 31, 1981
    Assignee: The United States of America as represented by the Department of Energy
    Inventors: William E. Pennell, Harry G. Sutton, Jr.
  • Patent number: 4257846
    Abstract: Method and apparatus for generating power from a high temperature gas-cooled nuclear reactor utilizing two Brayton-type thermal cycle circuits exchanging heat through a common heat exchanger. The reactor gas coolant is circulated through a primary circuit including the reactor, and a working fluid is circulated through a secondary circuit in heat exchange relation with the reactor gas coolant. Work is extracted from the primary circuit turbine to drive both the primary circuit and secondary circuit compressors. Further, the entire primary circuit and the secondary circuit compressor are preferably disposed within a singular containment structure.
    Type: Grant
    Filed: January 19, 1978
    Date of Patent: March 24, 1981
    Assignee: Westinghouse Electric Corp.
    Inventor: Bill L. Pierce
  • Patent number: 4257847
    Abstract: A breeder reactor fuel element having a tandem arrangement of fissile and fertile fuel with a getter for fission product cesium disposed between the fissile and fertile sections. The getter is effective at reactor operating temperatures to isolate the cesium generated by the fissile material from reacting with the fertile fuel section.
    Type: Grant
    Filed: October 6, 1978
    Date of Patent: March 24, 1981
    Assignee: The United States of America as represented by the United States Department of Energy
    Inventors: Ronald L. Gibby, Leo A. Lawrence, Robert E. Woodley, Charles N. Wilson, Edward T. Weber, Carl E. Johnson
  • Patent number: 4257912
    Abstract: Concrete systems, mixtures and methods for encapsulating and storing spent nuclear fuel. Fuel discharged from nuclear reactors in the form of rods or multi-rod assemblies is completely and contiguously enclosed in concrete having incorporated therein metallic fibers to increase thermal conductivity and polymers to decrease fluid permeability. The metallic fibers and the polymers can be distributed in a single concrete layer, or separate contiguous layers can be utilized for the conductivity and impermeability characteristics.
    Type: Grant
    Filed: June 12, 1978
    Date of Patent: March 24, 1981
    Assignee: Westinghouse Electric Corp.
    Inventors: Leonard R. Fleischer, Muthian Gunasekaran
  • Patent number: 4253241
    Abstract: A bore gauge for measuring the internal diameter of tubes comprises at least two concentrically and rotatably arranged members connected by a helically wound spring member. The spring member is capable of contacting the inside surface of the tube and causing relative rotation of the members thereby indicating the internal diameter of the tube.
    Type: Grant
    Filed: November 8, 1979
    Date of Patent: March 3, 1981
    Assignee: Westinghouse Electric Corp.
    Inventor: William F. Nanstiel, Jr.
  • Patent number: 4249776
    Abstract: A method for optimal placement and orientation of a well field for solution mining comprises first determining the direction and magnitude of the major and minor axes of transmissivity of the ore body. Then, determining the location of the injection and recovery wells based on the magnitude and orientation of the major and minor axes of transmissivity.
    Type: Grant
    Filed: May 29, 1979
    Date of Patent: February 10, 1981
    Assignee: Wyoming Mineral Corporation
    Inventors: David L. Shuck, Calvin C. Chien
  • Patent number: 4246751
    Abstract: 1. A nuclear engine and nozzle arrangement for a nuclear rocket, said arrangement comprising a cluster of elongated fissile fuel bearing and high temperature capacity modules suitably supported in a pressure vessel, said modules each having a plurality of coolant-propellant channels extending therethrough, a convergent-divergent nozzle structure of fixed cross-sectional dimensions secured to the end portion of each of said modules said modules, a divergent-only unitary skirt member connected directly to the propellant exit end of said modular cluster in series with and diverging from the divergent ends of said convergent-divergent nozzle structures, said modules being formed to conduct a compressible propellant therethrough at sub-sonic velocities, said nozzle structures being formed to develop supersonic velocities of the propellant and said divergent-only skirt being formed to develop further the supersonic velocities of said propellant.
    Type: Grant
    Filed: April 12, 1963
    Date of Patent: January 27, 1981
    Assignee: Westinghouse Electric Corporation
    Inventor: Francis D. Retallick
  • Patent number: 4244783
    Abstract: The fluid from a breeder nuclear reactor, which may be the sodium cooling fluid or the helium reactor-cover-gas, or the helium coolant of a gas-cooled reactor passes over the portion of the enclosure of a gaseous discharge device which is permeable to hydrogen and its isotopes. The tritium diffused into the discharge device is radioactive producing beta rays which ionize the gas (argon) in the discharge device. The tritium is monitored by measuring the ionization current produced when the sodium phase and the gas phase of the hydrogen isotopes within the enclosure are in equilibrium.
    Type: Grant
    Filed: January 27, 1975
    Date of Patent: January 13, 1981
    Assignee: The United States of America as represented by the United States Department of Energy
    Inventors: James A. Corbett, Sterling A. Meacham
  • Patent number: 4241271
    Abstract: A solid brush current collecting system for dynamo-electric machines which selectively uses compatible materials in different applications for the moving and stationary contact members. Brushes of different compositions are disclosed and the current transfer and collecting members are operated in an inert gas atmosphere, such as carbon dioxide, having either water or organic additives, such as alcohols, hydrocarbons, ketones, and the like, to achieve operation of the current collector system at higher temperatures, higher velocities and higher current densities than is possible with conventional systems. Low friction and low wear rates are in part achieved by operating the contact members in a low temperature environment.
    Type: Grant
    Filed: July 26, 1978
    Date of Patent: December 23, 1980
    Assignee: Westinghouse Electric Corp.
    Inventors: John L. Johnson, Lawrence E. Moberly
  • Patent number: 4238289
    Abstract: A generally annular condenser compartment of a nuclear reactor containment structure contains a large quantity of fusible material in a solid state, such as ice, for absorbing the energy released from a loss-of-coolant accident in the reactor coolant system. Inlet and outlet doors, which are normally closed, are provided at the bottom and the top, respectively, of the condenser compartment to permit the necessary inflow and outflow of gases and liquids during a loss-of-coolant accident. The inlet doors and door ports are so constructed that during an accident, energy flow is distributed substantially uniformly into all sections of the condenser.
    Type: Grant
    Filed: January 23, 1974
    Date of Patent: December 9, 1980
    Assignee: Westinghouse Electric Corp.
    Inventors: Sterling J. Weems, Harold W. McCurdy
  • Patent number: 4235669
    Abstract: A core and composite fuel assembly for a liquid-cooled breeder nuclear reactor including a plurality of elongated coextending driver and breeder fuel elements arranged to form a generally polygonal bundle within a thin-walled duct. The breeder elements are larger in cross section than the driver elements, and each breeder element is laterally bounded by a number of the driver elements. Each driver element further includes structure for spacing the driver elements from adjacent fuel elements and, where adjacent, the thin-walled duct. A core made up of the fuel elements can advantageously include fissile fuel of only one enrichment, while varying the effective enrichment of any given assembly or core region, merely by varying the relative number and size of the driver and breeder elements.
    Type: Grant
    Filed: March 30, 1978
    Date of Patent: November 25, 1980
    Assignee: The United States of America as represented by the United States Department of Energy
    Inventors: Donn M. Burgess, Duane R. Marr, Michael W. Cappiello, Ronald P. Omberg
  • Patent number: 4233116
    Abstract: A system for transporting reactor coolant in nuclear reactors using a liquid coolant. The system diverts a portion of the output from the main circulating pump in the nuclear reactor primary flow system and introduces this diverted coolant back into the system upstream of the main circulating pump. This diverted coolant compensates for any pressure drop which may occur due to the pumping action, thereby maintaining a constant head to the circulating pump.
    Type: Grant
    Filed: October 18, 1977
    Date of Patent: November 11, 1980
    Assignee: Westinghouse Electric Corp.
    Inventor: James D. Mangus
  • Patent number: 4231843
    Abstract: Nuclear reactor upper internal guide tube having a flow diffuser integral with its bottom end. The guide tube provides guidance for control rods during their ascent or descent from the reactor core. The flow diffuser serves to divert the upward flow of reactor coolant around the outside of the guide tube thereby limiting the amount of coolant flow and turbulence within the guide tube, thus enhancing the ease of movement of the control rods.
    Type: Grant
    Filed: August 2, 1977
    Date of Patent: November 4, 1980
    Assignee: Westinghouse Electric Corp.
    Inventors: Donald L. Myron, Robert T. Berringer