Abstract: A pressure tight seal is formed between the confronting planar sealing surfaces on the flanges of a nuclear reactor pressure vessel and its hemispherical head, by a toroidal, crushable tubular seal member which is locked into a flat annular spacer member by a resilient annular member, such as a circular coil spring seated in a V-shaped recess in the inner surface of the flat annular member. The thickness of the flat annular member and the resiliency of the circular coil spring control the deformation of the tubular seal member as the sealing surfaces are drawn toward each other by flange bolts. The flat annular member is provided with axial bores which register with the flange bolts to provide positive positioning of the tubular seal member without the necessity of providing grooves in the confronting planar sealing surfaces.

Abstract: An upwardly convex resilient annular strainer, fixed to the secondary core support base plate in a PWR, bends to remain in contact with the lower hemispherical head section of the pressure vessel as the gap between the internals and the lower hemispherical head section varies in size with reactor temperature to prevent debris from lodging in the gap where it could lead to reactor damage.

Abstract: A thimble guide extender for use in a nuclear power plant provides a shielded passage beteewn the guide and the bottom nozzle of a fuel assembly to protect the thimble from turbulence. The extender includes a hollow element having an upper portion which contacts the bottom nozzle, a lower portion which extends around the sides of the thimble guide, and a thimble passage through which the thimble movably extends. In one embodiment the thimble passage is aligned with a channel in the thimble guide by being permanently attached to the bottom nozzle of the fuel assembly. For this purpose the hollow element is provided with locking fingers which extend into flow openings in the bottom nozzle. In another embodiment the thimble passage of the hollow element is aligned with the channel of the thimble guide by being operatively mounted on the thimble guide, with spring fingers having enlarged regions or with locking balls fitting into an annular groove in the thimble guide.

Abstract: A self-adjustable supplementary support system for a cylindrical container coaxially disposed in a cylindrical housing by upper flanged supports has a plurality of outwardly extending bracket units on the external surface of the container which coact with inwardly extending resiliently outwardly extending bracket units on the inner wall of the cylindrical housing. The bracket units have flanges which form a concave surface that seats on support bars, attached by links to torsion bars that are secured to ring segments annularly spaced about the inner wall of the cylindrical housing and the bracket units and support bars coact with each other to radially position and support the container in the housing during movement of the two components from a vertical to a horizontal position, and during transportation of the same.

Abstract: A position indication system for detecting the position of an elongated, metallic member which is linearly movable between first and second positions along an axis corresponding to its longitudinal dimension. A sensor is operatively associated with the member for producing a first output signal which corresponds to the position of the member and which fluctuates with changes in the temperature of the member. A temperature monitoring device is operatively associated with the member for monitoring its temperature and for producing a second output signal which varies in direct response to changes in the temperature of the member. A combining circuit is connected to the sensor and to the temperature monitoring device for receiving the first and second output signals and for producing a third output signal which represents the position of the member compensated for changes in temperature of the member.

Abstract: An enclosure for a collector set on a turbine generator includes a non-conducting transverse baffle which divides the enclosure into a separate compartment for each polarity. An aperture in the baffle forms with the generator shaft an annular passage through which cooling air passes from one compartment to the other and in so doing flows directly over the collector ring and brush sets in each compartment to provide more efficient cooling. A removable housing is guided into place over the collector set by a grooved guide which engages the top edge of the baffle and forms a seal between compartments. Single doors on each side of the housing provide access to both polarities and carry a seal, which mates with the baffle with the doors closed, to force the air to pass through the annular passage. An insulated safety handle above each door provides support when leaning inward to change brushes with the generator at full load, and discourages inserting both hands into the enclosure at once.

Abstract: A calibrator for a pressurized water reactor (PWR) core predictor utilizing a distribution expression for the transverse buckling factor, in a one dimensional diffusion model, which has coefficients correlated with overall neutron balance and with a set of power distribution characterization parameters including axial offset, axial pinch, axial quarters and axial fifths. The coefficients are periodically adjusted incrementally one at a time to produce criticality with the model at measured values of rod position, reactor power level, cold leg temperature and boron concentration until the power distribution characterization parameters calculated from a power distribution generated by the model are within preset tolerances of those from a power distribution measurement generated by movable, or if provided, fixed, incore detectors.

Abstract: Removable cruciforms are selectively installed at predetermined, spaced elevations within ice baskets associated with a nuclear power system, each ice basket having a generally cylindrical sidewall with plural, annular retaining rings secured therein at predetermined, spaced elevations, each cruciform being installed at predetermined, axially displaced elevations, engaging a corresponding annular retaining ring. Each cruciform comprises a pair of brackets joined together between parallel base portions by respective support plate assemblies and slide plates in telescoping, sliding relationshp, defining with the base portions, a spring housing of generally square configuration within which a generally C-shaped spring is received. A pair of legs extends integrally from the longitudinal edges of the base portion of each bracket, angularly disposed so as to extend radially within the ice basket.

Abstract: A method and apparatus for impacting a surface with a desired kinetic impact energy wherein an impacting device which can apply a variable impact energy corresponding to the magnitude of an input control signal is provided and placed adjacent the surface to be impacted. Thereafter, an input control signal of a preset magnitude is applied to the impact device to initiate an impact, the kinetic energy of the impact is determined, the value of the determined kinetic energy is compared with a value corresponding to the desired kinetic impact energy, the results of the comparison are indicated, the preset magnitude of the signal used for the control signal is adjusted to reduce any difference noted as a result of the comparison, and the process is repeated until a repeatable impact of the desired impact energy is determined and indicated.

Abstract: In a nuclear reactor including a core, a plurality of control rods, a support supporting the control rods and movable for displacing the control rods in their longitudinal direction between a first end position in which the control rods are fully inserted into the core and a second end position in which the control rods are retracted from the core, and guide elements contacting discrete regions of the outer surface of each control rod at least when the control rods are in the vicinity of the second end position, the control rods being longitudinally movable relative to the guide elements to thereby cause the outer surface of the control rods to experience wear as a result of sliding contact with the guide elements, there is provided a displacement device operatively coupled to the control rods for periodically rotating the control rods in order to change the locations on the outer surfaces of the control rods at which the control rods are contacted by the guide elements.

Abstract: A cask for storing spent nuclear fuel after removal from a pool of water includes a container with a cylindrical cavity and a basket which is inserted into the container. The basket includes disk-like grid assemblies which provide spent fuel storage slots and which are coaxially mounted at spaced-apart positions, each grid assembly having a diameter that is slightly less than the one above it. If fuel assemblies are to be stored, hollow cells are affixed to one of the grid assemblies and positioned in the others by heat-conducting wedges which permit the basket and cells to expand at different rates. Rings which project slightly into the interior of the container are provided on the container walls, each ring being positioned to be in alignment with the periphery of a corresponding grid assembly after the basket is inserted into the container.

Abstract: Position indicating device for producing an indication of the position of a displaceable structure, the device including:a plurality of sensing elements extending along a defined path such that each element is associated with a respective location along the defined path, each element being operative to respond to the presence of a position representing member when the member extends from a starting point to the respective location associated with that element, the elements being coupled into respective pairs of elements, with each pair of elements having an output producing a signal only when a single element of its respective pair is responding to the presence of the member; a plurality of signal producing members each operative for producing a signal representing a predetermined logic state in response to a predetermined input signal; and circuit components operatively connecting the outputs to the signal producing members for causing a signal at each output to produce a predetermined input signal at a corr

Abstract: An improved nuclear reactor wherein the bolted connections between the baffle plates and baffle former and the baffle former and the core barrel are provided with a noval locking device that prevents loosening of the bolted connections. The locking device to prevent loosening of bolted connections where a threaded bolt is used to secure two components together uses a threaded lock nut over the bolt head, cooperative with a threaded wall in a recess in a component. The lock nut and wall of the recess have threads opposite the threads of the bolt. Deformable sections are formed in the base of the lock nut to engage an unsymmetrical cavity in the head of the bolt. Turning of the bolt in a direction that would tend to loosen the connection causes tightening of the lock nut. The wall of the lock nut may be threadedly engaged with the wall of the recess or the lock nut wall may have slits formed thereon which enable deformation of wall portions to engage the threaded wall of the recess.

Abstract: A method for automatically calibrating a touch screen used in conjunction with a graphic display is executed prior to every interactive session. Three points, defining perpendicular axes, are displayed and an operator is instructed to touch the touch screen at each of the points in succession. Coordinates for the three points output by the touch screen are checked for reasonableness and perpendicularity. If these checks are passed, a coordinate translation matrix is generated for converting touch screen coordinates into display coordinates.

Abstract: An electroencephalographic (EEG) cap for a human head for use in an evoked potential autorefractometry system which includes an adjustable headband having relatively rigid straps crossing over EEG measurement regions. Inserted through the straps are self-preparing electrodes which are connected to shielded cables. The self-preparing electrodes penetrate a dead skin layer without causing bleeding during positioning of the cap and do not require a previously prepared electrode positioning site. An electrolyte solution can be applied to the electrodes and the regions for measurement after the cap is in position by an electrolyte solution pump system. The entire cap can be shielded by a metal shield dome and held in place by a chin strap.

Abstract: Two sets of heater support members angularly distributed around a central vertical member are radially extendable individually or in groups to position heater elements within a preset distance of the cylindrical walls of any one of a series of pressure vessels having a range of diameters. A convex bottom heater support member is provided for each diameter vessel and is axially telescoped into the central vertical member so that an additional set of heater support members can be installed between the first mentioned two sets of heater support members and the bottom heater support member to accommodate for varying depths of the vessels in the series. Thermocouples are extended from the annealing device by actuators which use a spring or pneumatic pressure to press the thermocouple against the vessel wall with a preset constant force for accurate temperature measurements.

Abstract: A combined in-core flux detector and thermocouple assembly for a nuclear reactor composed of an outer tube which is sealed at its upper end; an inner tube disposed within, and extending along the length of, the outer tube; a neutron detector means disposed within the inner tube; an element connected to the neutron detector for displacing the neutron detector along the length of the inner tube; and a plurality of thermocouples disposed outside of the inner tube and enclosed within the outer tube.

Abstract: Apparatus comprising a seal connector is disclosed for sealingly connecting flow channels in the core support plate with flow channels in fuel assemblies for use in a spectral shift pressurized water nuclear reactor. Spectral shift is obtained by displacing a portion of the light water in the core with deuterium oxide or a combination of deuterium oxide and light water or various gases such as helium during the initial state of reactor operation to harden the nuclear spectrum and thereby reduce excess reactivity and increase the production of fissile materials. The seal connectors provide a sealed flow channel for introducing the deuterium oxide into the core during the early stages of reactor operation and for reintroducing the light water into the core during the later stages of reactor operation.

Abstract: The present invention includes an adjustable head set held in place on the back of a patient's head when the patient leans back against a chair head rest. The head set includes self-preparing disposable monitors that provide good contact with the patient's head without prior skin preparation. The monitors include a conductive tube containing conductive wires, the tips of which form a planar cushion surface for contacting the patient's head through a caratinaceous layer of skin. The monitors are held in adjustable holders that allow the contact force to be adjusted. The adjustable holders are mounted in holder slots of head set springs where the slots also allow adjustment of the placement of the monitors. The springs can include hinges for rotatably adjusting placement of the monitors. The disposable monitors are filled with an electrolyte solution using a disposable applicator including a puncturable film, punctured by a monitor when the electrolyte solution is being applied.

Abstract: A gauge plate for use in customizing replacement upper core plate inserts of a nuclear reactor which comprises: a circular metal plate of a known diameter corresponding to that of the upper core plate of the nuclear reactor to be gauged; a plurality of U-shaped gauging slots of known size formed in the peripheral surface of the gauge plate at locations corresponding to the locations of the guide pins for the lower internals of the reactor; an arrangement for positioning the gauge plate within the core barrel at the normal elevation of the upper core plate inserts and the guide pins; and devices, disposed on the gauge plate, for positioning the gauge plate relative to the reactor baffle plate arrangement; and, for determining the actual position of the gauge plate relative to the baffle plate arrangement.