Abstract: Apparatus for visually indicating a worn brush condition for carbon brushes arranged in a gang-type brush holder. A strip of red Teflon tape, or other distinctive marking, is positioned on the linear spring having a coiled top portion which biases the brush into contact with the collector ring. As the brush wears down, the marking on the spring becomes visible as the spring coils more and more. The tape is positioned on the spring such that, when the exposed top portion of the spring shows completely red (i.e., the color of the marking), it is indicated to the operator that a worn brush is to be replaced.

Abstract: An apparatus for monitoring hydrogen leakage from a generator frame into the stator coil water cooling system. The monitor is designed to alert the operator should leakage exceed a rate of twenty cubic feet per day (20 cfd). A pressure relief valve set at four (4) psig and orifice are provided, along with a second relief valve having a higher setpoint than the first, such that pressure will increase in the holding tank if leakage exceeds 20 cfd setpoint of the orifice. A high pressure alarm, set at a level higher than the first relief valve but less than that of the second, will then sound to alert the operator to protect the system from an overly large or gross failure of the system. By continusouly monitoring a relatively small steady state leakage rate, the operator can be aware of a minor problem which can be corrected at a scheduled maintenance outage, before a gross failure of the system, requiring a costly shutdown of the turbine-generator, would otherwise occur.

Abstract: A worn brush detector 43 for an electric generator. The worn brush detector 43 comprises a contactor strip 55 of electrically-conductive material secured to and insulated from a brush holder 28, the contactor strip 55 having a plurality of fingers 52 projecting downward from the strip 55 and generally perpendicular thereto, the fingers 52 being disposed adjacent to a hole 62 in the brush holder 28 and electrically insulated therefrom. An electrically insulated knob 61 on the opposite end of the fingers 52 projects through the hole 62 such that when a brush 25 is inserted into the holder 28 the corresponding finger 52 is pushed away from the holder by the knob 61 contacting the brush 25. When one of the brushes 25 has worn down a predetermined amount the brush 25 is disengaged from the knob 61 so that the corresponding finger 52 is caused to contact the holder 28 to generate an electrical signal.

Abstract: Apparatus 50 for the detection and location of arcing within an enclosed electrical device, such as an electric generator 20. Fiber optic cables 53 are strategically mounted within the generator 20 detect emitted light 44 incident to arcing of the stator windings 32. Positive indication is given that the source of the arcing is within the generator 20 itself. By examining and comparing the relative magnitude and intensity of the light 44 received by each of the individual fiber optic cables 53, the location of arcing within the generator 20 can be established.

Abstract: A new design for nuclear reactor internals resulting in reduced fast neutron leakage to the reactor vessel. The first step of the two-stage process reflects high energy or fast neutrons back into the core, by placement of a reflector made of tungsten, stainless steel, or zirconium oxide in the baffle barrel region. The second stage involves reducing the energy of any fast neutrons that may pass through the reflector by the use of a neutron energy reducer, composed of an hydrogenous material such as titanium hydride, surrounding the core barrel in the areas of high neutron flux. In addition to protecting the reactor vessel wall and increasing the operating life of a nuclear reactor, the neutron economy in the core, and hence the operating efficiency of a nuclear power plant, are significantly increased.

Abstract: A steam generator upper support arrangement provides restraint to the steam generator during operating and non-operating conditions, for loading forces resulting from seismic and postulated accident conditions, while allowing for free thermal expansion of the steam generator in the radial, lateral, and vertical directions. Four embodiments of the present invention are described. In a first embodiment, inclined bumpers are placed at predetermined angles with respect to the load path, such that as the steam generator is thermally displaced the placement and incline angles of the bumpers will compensate for the expansion and maintain a nominal gap therebetween. In a second embodiment, the variable shim mechanism comprised of cams, bumper rods, and a pivoted linkage between the steam generator and the building structure maintains the nominal gap for the required support. In the third embodiment, a single small snubber is utilized.

Abstract: A remotely operated device which attaches to an existing internals lifting rig to safely lift and transport nuclear reactor internals structures. The device includes a grapple assembly uniquely formed to maximize the effective bearing surface of an annular shoulder disposed on the grapple assembly to engage the internal structure. The annular shoulder comprises a first outer diameter, the annular shoulder defining a second outer diameter disposed thereabove. The grapple assembly comprises a plurality of fingers circumferentially disposed about an actuator rod which has a diameter essentially equal to a first inner diameter of the grapple assembly. The lower end of the grapple assembly has a second inner diameter smaller than the first and axially adjacent to the annular shoulder.

Abstract: A straightening device (16) for bent fuel assembly alignment pins (12) in an upper core plate (10) comprises elongatged mast (22) haivng an upper and lower portion, bail (25) secured to the upper portion and cross member (28) secured to the lower portion. At one end of the cross member (28) is attached pin straightening assembly (19), the other end having counterweight (31) to assure a horizontal orientation of the cross member (28). Pin straightening assembly (19) is further comprised of housing (37) having wedge-shaped adjustable shim (61) connected to its top surface, the housing (37) secured to the cross member (28) by baseplate (34). Four axially compressible and laterally deformable compression springs (41) are connected between baseplate (34) and housing (37) to provide angular and translational compliance for housing (37).

Abstract: A gas/liquid separating and vent apparatus wherein gas trapped and/or entrained in a standpipe containing liquid medium is separated from the liquid and vented off. The valve can be power or manually operated. In both modes, the separator distinguishes between gas and liquid because of the differences in compressibility of the fluids. The venting of liquid is prevented if no significant amount of gas is present in the system.

Abstract: A method and apparatus for continually obtaining accurate opacity monitor readings of an exhaust gas stream (15) is disclosed. A conventional opacity monitor having a transmitter (10) and a receiver (13) is shielded from an exhaust stack (16) environment by two scratch-resistant windows (19, 20). The windows (19, 20) are periodically kept clean by spraying a volatile nonflammable cleaning solvent (28) onto each of the windows (19, 20), and a reciprocating resilient wiper arm (22) is used to remove the solvent (28) and any particulate matter (14) from the windows (19, 20). This cleaning is performed for a period of about twenty seconds. The next step is to then obtain an accurate opacity monitor by directing a light beam (34) across the stack (16) from the transmitter (10) via first window (19) through the exhaust gas stream (15) to the receiver (13) via second window (20). The reading is obtained during about the next ten seconds.

Abstract: The total transmissibility optical system or lens is an assembly of curved members or mirrors arranged such that a beam of radiation will reflect through the apparatus and come to a focus on an opposite side. An inner member, comprised of a pair of conical reflectors joined at their respective bases, is disposed within an outer member such that their axes are parallel to the radiation beam. The outer member is comprised of a first inner reflective surface in the shape of a hollow segment of a paraboloid of revolution and a second inner reflective surface in the shape of a hollow truncated cone. The two inner reflective surfaces of the outer member are also joined at their respective bases. The mirrors are made of a highly polished metal which will reflect any type of radiation beam, such as infrared radiation as in a night vision device. The lens can be used in harsh environments, such as an irradiated environment, since the lens will not be affected thereby as will a glass lens.

Abstract: A multi-point wall thickness gage (10) comprises a pad (16) of flexible magnetic material that includes an array of ultrasonic transducers (13) and a multi-point ultrasonic transmitter and receiver (25) to which each transducer (13) is attached. The magnetic pad (16) is attachable to the wall of a ferro-magnetic object (19), and serves to hold the array or matrix of ultrasonic transducers (13) against the wall of the object. The specific region of the object wall being inspected is marked off (17), and the magnetic pad (16) is periodically applied over this region (17). The output of the transducers (13) is used to detect whether any wall thinning is occurring over the particular area of the object covered by the magnetic pad (16), and if so, the particular pattern of thinning within the area. Trend monitoring is simplified since exact relocation of the transducers (13) for periodic measurements is more readily accomplished.

Abstract: An improved method for automatically controlling rate of combustion in a rotary combustor having a rotating combustion barrel (11) by precisely controlling a supply of combustion gas to three separate combustion zones (A, B and C) of the combustion barrel (11) in the rotary combustor used for the incineration of municipal solid waste material (15), the combustion zones (A, B and C) have an associated windbox (34, 37 and 40) disposed directly beneath a respective combustion zone, the windboxes (34, 37 and 40) are further divided into an overfire air zone (36, 39 and 42) and an underfire air zone (35, 38 and 41) forming six air zones which are adjusted by a controller (51) to precisely regulate the supply of combustion gas to each of the six air zones (35, 36, 38, 39, 41, 42).

Abstract: Concrete support ledges (67) and columns (94) for the upper internals (60) and lower internals (63) structures are poured into the floor (41) and walls (36) of the refueling cavity (33) at the time of initial plant construction. Such concrete supports (67, 94) provide greater stability and do not require any external bracing. A pedestal assembly (100) is associated with each of the concrete supports (67, 94) to provide an adjustable and secure support for the internals structures (60, 63).

Abstract: A temporary support structure for supporting a lower internals assembly above the reactor vessel during inspection and/or maintenance thereof. A support bracket is bolted to the reactor vessel flange at the vessel head stud closure holes. A pivotally mounted arm, upon the top surface of which the internals rest, is attached at one end to the support bracket and projects radially inwardly therefrom. A compliant foot depends from the bottom of the opposite end of the arm and engages the vessel internals support ledge to provide a secure support structure for the internals assembly. An alignment bracket on the arm aligns the internals with the support. Four such structures are installed around the circumference of the vessel flange while the internals are within the reactor vessel. The structure allows the lower internals to be quickly removed from the interior of the reactor vessel and placed on the temporary supports.

Abstract: System provides a positive verification of the presence of a reactor coolant leak in the reactor vessel head area, identifies its location, and enables its size to be determined. A series of video cameras 28 strategically placed about the shroud 16 on the vessel head 13 provide complete viewing coverage. Variable intensity halogen lamps 46, 47 provide illumination for the area to be inspected. The equipment is specially adapted for use in a highly irradiated environment. The system 25 allows for inspection of the reactor vessel head area without the need for shutting down the plant.

Abstract: A thimble grip fuel assembly handling tool (20) for transporting fully loaded fuel assemblies (52) is disclosed. The tool (20) comprises an elongated mast (23) slidingly disposed within an elongated cylinder (113), the cylinder being of a length less than the mast (23) such that the tool defines a mast fill-up position (126) and a mast full-down position (128). A cage (110) assembly acts to protect the gripping means (32) when the tool is transported in the mast full-up position (126). The gripping means (32) is comprised of a plurality of gripping members (49) which grip the inside diameter of control rod guide thimbles (50). The load path is distributed in the tool such that when the fuel assembly (52) secured to the gripping means (32) is raised, the weight of the fully loaded fuel assembly (52) acts to increase the gripping force on the fuel assembly.

Abstract: A straightening device (16) for bent fuel assembly alignment pins (12) in an upper core plate (10) comprises elongated mast (22) having an upper and lower portion, bail (25) secured to the upper portion and cross member (28) secured to the lower portion. At one end of the cross member (28) is attached pin straightening assembly (19), the other end having counterweight (31) to assure a horizontal orientation of the cross member (28). Pin straightening assembly (19) is further comprised of housing (37) having wedge-shaped adjustable shim (61) connected to its top surface, the housing (37) secured to the cross member (28) by baseplate (34). Four axially compressible and laterally deformable compression springs (41) are connected between baseplate (34) and housing (37) to provide angular and translational compliance for housing (37).

Abstract: The reactor vessel thread protector is a metal cover that is placed over the exposed stud, nut and washer projecting above the closure head to protect the threads from accidental corrosive leakage impingement emitted from mechanical seals on the top of the reactor vessel head. The stud protector includes a drip pan to collect any such fluid being emitted from the reactor vessel. Additionally, the reactor vessel stud thread protector will provide protection from accidental deformation to a stud due to operator maintenance around adjacent studs. The reactor vessel stud thread protector can be in the form of a cylinder which would cover a single stud bolt or a curved box having a rectangular cross-section that would cover a plurality of stud bolts.

Abstract: A high preload quick operating closure for a pressure vessel (17) comprises a vessel opening or nozzle (19) having a port flange (20) with an upper surface (23), which has a wall (26) affixed thereto, the wall (26) having one or more circumferentially spaced holes (32), the combination of the wall (26) and port flange (20) forming a well (29), and a vessel head (27) forming a closure for the port flange. A plurality of wedge assemblies (30) secured to the wall (26) at holes (32), comprising hydraulically operated cylinders (39) operably connected to wedges (33) which slidably engage a tapered surface (40) of the vessel head (27) creating a larger sealing force between the head (27) and the flange (20) to seal the pressure vessel (17) with an enormous preload. The closure incorporates a control system (50) with two independent safety features to prevent the closure device from opening when the pressure vessel ( 17) is pressurized.