Abstract: A log splitting apparatus and method for use in conjunction with a substantially horizontally mounted source of rotational power, such as the take off (20) and hitch lift unit (16) of a farm type tractor (10). The apparatus is disclosed in the form of a rigid frame (30) attached to the unit (16), and includes strut members (26,28) for maintaining the frame in a horizontal orientation. A drive shaft (60) is horizontally supported through the frame with one end connected as a universal joint (40) to the take off, and the other end extending behind the frame. A drive transfer gear arrangement (42) is connected to the extending end of the drive shaft, and an auger (44,46) is perpendicularly connected to the transfer gear arrangement. Preferably, the tractor is maneuvered to straddle a series of end-to-end logs (12) so that the auger (46), while pointing downward and rotated by the power take off and drive shaft, is lowered onto and lifted from each log in succession, by means of the lift unit.

Abstract: A game for two players including a flat board (10) on which is delineated a uniform rectilinear grid (14, 16) defining eight adjacent rows and columns of square spaces (18). Each space is associated with one of four types of zones. A home zone (24a,b) spans each of the northern and southern ends of the grid, immediately in front of the players. A side zone (44) is located at each of the eastern and western ends of the grid, extending between the opposed home zones. A safe zone (46) of contiguous spaces is centered on the grid, and the remaining spaces constitute the playing zone (48). Each player controls a plurality of game pieces (26) having distinct values (28,30,32,34) indicating the number of spaces the piece can move during a turn. The pieces are initially placed in the home zone (24), and can move diagonally as well as rebound off other pieces or zone boundaries.

Abstract: A repair sleeve assembly (12) secured entirely within a tube (16). A hollow tension member (18) has an enlarged head (26), a lower externally threaded stem (28) and a generally cylindrical body portion (30) intermediate the head and stem. A segmented sheath surrounds the tension member and includes a generally cylindrical nut member (24), a ring member (22) and a sleeve member (20), which are operatively arranged such that when the tension member is drawn downward, the enlarged head and lower ring member compress the sleeve to form seals against the tube wall. A tool for effecting the seal is also disclosed, including an inner rod (38) having an upper end (40) adapted to engage the lower end of the tension member, for aligning the tool relative to the repair assembly, and lugs (42) carried circumferentially on the rod to engage the tension member. A chuck member (44) is adapted to move longitudinally and rotationally with respect to the inner rod, and carries tangs (46) for engaging the nut member.

Abstract: A manually controlled tooling system for the remote placement and removal of a load, such as a plug, (12) at a location (6) inaccessible to maintenance personnel. The tooling provides for both horizontal and vertical movement of the load, and, in the preferred embodiment, rotational restraint. The load is supported vertically by at least one line (21) wrapped on a small diameter drum (19) which is supported from a travelling trolley (11) fitted to a sloping track (10). On the same shaft as the load drum, a large diameter centrally located sheave or control drum (20) accepts a single control line (13) counterwrapped in direction with respect to the load support line and terminating at its other end on a hand operated winch mechanism (14). The tooling acts to first allow the trolley to descend the track without relative motion between trolley and load. Then, with the trolley bottomed against a mechanical stop (26), the load is allowed to descend vertically to its desired position.

Abstract: A control system for overpressure protection of the reactor coolant boundary (14) in a nuclear power plant, comprising a pressure relief line (18a) having a power operated relief valve (24a) controlled by a circuit responsive to the condition of the reactor coolant and a control logic. The circuit includes a mode selector switch (80) having a NORMAL position (82) for establishing a full power overpressure relief valve setpoint (62) and a LTOP position (84) for establishing a low temperature overpressure relief setpoint (58). The control system logic opens the relief valve (24a) when (a) the mode switch is in the NORMAL position and the coolant pressure exceeds the full power setpoint (62), or (b) when the mode switch is in the LTOP position, the coolant temperature is less than a preselected value (52) and the coolant pressure exceeds the LTOP setpoint (58).

Abstract: A tool (100) for scanning the inner surface (110) of a pipe (106), comprising a scanning section (112) interacting with a centering section (114). The scanning section includes an axle member (128) having strut members (130) rigidly connected thereto and projecting diametrically outwardly for urging inspection probe sleds (126) against the pipe surface. The centering section (114) includes a slide cylinder (124) coaxially disposed about the axle member (128), and having rigidly connected actuating members (120) projecting diametrically outward for contacting the pipe inner wall with sufficient force to center and support the tool within the pipe. Locking means (146) are provided within the actuating member (120) for selectively engaging the axle member (128) to lock the longitudinal position of the strut member (130) relative to the actuating member (120).

Abstract: An apparatus (10, 110, 210) including a containment capsule (12, 112, 212) a support member (16, 116, 216) removably disposed within the capsule and carrying therein a solid state track recorder material (20, 120, 220) and a layer of fissile material (20, 120, 220), and means (52) on the exterior of the capsule adapted to be remotely grasped for positioning the capsule adjacent to the fuel. The capsule is lowered into close proximity to the fuel, and positioned at a predetermined location for a period of time between about one hour and one day. The capsule is withdrawn from the fuel, the support member and recording member are withdrawn from the capsule, and the recording member is processed to reveal the fission track density, which is readily correlated to fuel burnup.

Abstract: An arrangement of square fuel assemblies in the first and subsequent cycles of a pressurized water nuclear reactor wherein shimmed feed assemblies and once-burned or equivalent assemblies occupy the same checkerboard component of alternating diagonals in an inner region of the core, and the highest burned or equivalent assemblies occupy the other checkerboard component. The remainder of the core consists of an outer region containing another checkerboard of feed assemblies wherein the feed assemblies occupy less than one-half the assembly locations on the core periphery.

Abstract: A valve seat (28) having a generally saddle-shaped, eccentric surface (52); a groove (50) of constant depth and width formed in the eccentric surface, having sidewalls (70) perpendicular to the eccentric surface and a base (72) parallel to the eccentric surface; and a flexible O-ring (54) retained by friction within the groove. The groove sidewalls and base have a surface finish in the range of about 32 to 125, which provides sufficient smoothness to retain the O-ring in the required non-planar shape.The valve seat groove (50) can be produced according to the disclosed method, which is preferably implemented in a numerically controlled four-axis horizontal milling tool system. The valve seat part (100) is mounted in a fixture (102) on a rotary table (104) such that the part axis (56) is aligned with the longitudinal axis (Z) of the tool (106).

Abstract: Means and method are disclosed for determining the fluid content within a large pressure vessel (12), without penetrating the vessel. Strain gauges (60) are located at the weight-bearing support structures (24) of the vessel, whereby calibrated differences in the weight of the empty vessel and the vessel as measured during operation gives a direct indication of fluid content. Preferably, the strain gauges (60) are associated with strain amplification elements (80) or shims, which are interposed between mating surfaces of the vessel support (24) and its base (44). The stress amplification element (80) has a smaller area of contact with the support member (24) than with the base (44), providing an effective higher coefficient of elasticity than that of the support member. In one embodiment, the strain gauge (60) is connected to a bolt (64) which tightly secures the vessel support (24) to its base (44).

Abstract: A multiple tubing hanger tie back arrangement is disclosed in a preferred embodiment associated with a shear ram tubing head system (10). The arrangement includes a lower tubing hanger (44) sealingly secured within a lower tubing head (28) for supporting a tubing string (22). The lower hanger includes a control shoulder (60) at its upper end and a tapered interior surface (62). An upper tubing hanger (70) spaced above the lower hanger is also sealingly secured within an upper tubing head (24). A tie back subassembly (90) connects the upper and lower hangers, and preferably includes a tubing member (94) and a spacer member (92). The spacer member includes a stab nipple (96) in interference engagement with the lower hanger interior surface (62), and a load transfer surface (98) abuting the control shoulder (60). The tubing member (94) is located in the bore of the shear ram (26) so that severance of the tubing member (94) does not disturb the production tubing string (22) supported by the lower hanger (44).

Abstract: A method for installing a close-fitting cylindrical metal sleeve (26) within a tube (14) secured to a tube sheet (12) of a steam generator, comprising the following steps. First, the sleeve is inserted into the tube until an upper portion (28) of the sleeve is above the tube sheet while the lowr portion (30) of the sleeve is within the tube sheet. Next, the upper portion of the sleeve is radially deformed against the adjacent tube wall to form substantially coextensive permanent bulges (32,34) around the circumferences of the sleeve and the tube. The sleeve is then displaced axially, or longitudinally, relative to the tube, such that the bulge in the sleeve produces a wedge-like mechanical interference seal (40) against the tube wall (16'). Finally, the lower portion (30,38) of the sleeve is joined and sealed (42) against the adjacent tube wall (16') to permanently maintain the tight mechanical interference seal at the upper portion of the sleeve.

Abstract: A valve seat (28) having a generally saddle-shaped, eccentric surface (52); a groove (50) of constant depth and width formed in the eccentric surface, having sidewalls (70) perpendicular to the eccentric surface and a base (72) parallel to the eccentric surface; and a flexible O-ring (54) retained by friction within the groove. The groove sidewalls and base have a surface finish in the range of about 32 to 125, which provides sufficient smoothness to retain the O-ring in the required non-planar shape.The valve seat groove (50) can be produced according to the disclosed method, which is preferably implemented in a numerically controlled four-axis horizontal milling tool system. The valve seat part (100) is mounted in a fixture (102) on a rotary table (104) such that the part axis (56) is aligned with the longitudinal axis (Z) of the tool (106).

Abstract: A generally cylindrical tube repair assembly (26,80) having an outer diameter approximately equal to the tube inner diameter. The assembly includes three main components, one of which is compressed and expanded by the other two into sealing engagement with the tube wall. The components include an elongated tension member (28) having an enlarged head portion (30) at its upper or lead end, and a stem portion (34) at the other end. A generally cylindrical expander ring member (40) is disposed about the lower portion of the tension member, and a ferrule-type, radially expandable compression member or sleeve (44) is interposed between the enlarged head and the ring. Means (42) are included for immobilizing the ring member against the tube sheet (12) while drawing down the tension member head.

Abstract: An arrangement of square fuel assemblies in the first and subsequent cycles of a pressurized water nuclear reactor wherein shimmed feed assemblies and once-burned or equivalent assemblies occupy the same checkerboard component of alternating diagonals in an inner region of the core, and the highest burned or equivalent assemblies occupy the other checkerboard component. The remainder of the core consists of an outer region containing another checkerboard of feed assemblies wherein the feed assemblies occupy less than one-half the assembly locations on the core periphery.

Abstract: A "finger walker" apparatus for remotely traversing a flat surface having a regular array of openings, such as the tube sheet of a nuclear steam generator. The apparatus has a rectangular base having four base fingers disposed in a rectangular pattern for engagement with the openings. An annular platform surrounds the base and is rotatable about the base. The base is adapted to move linearly a pitch multiple within the platform. Fingers on the platform are adapted for engagement with the openings. The apparatus can orient itself for movement in one of many directions by engaging the platform fingers, disengaging the base fingers and rotating the base until the axis of the base is aligned with the intended direction of travel. The apparatus then advances by alternatingly engaging and disengaging the base and platform fingers in coordination with the base and platform moving linearly relative to each other.

Abstract: A method of operating a co-generating steam supply system having two units, the second of which utilizes a molten-salt primary heat transfer fluid, is disclosed for utilizing the steam produced by the first unit for maintaining selected component operating temperatures in the second unit during periods when the second unit is not producing steam. The steam generator of the second unit is maintained at operating temperature by reversing the fluid flow through both the shell and tube sides. The reverse flow of molten salt is in heat exchange relation with the reverse flow of steam drawn from the steam flow line of the first unit.

Abstract: A drum-type apparatus for feeding and retrieving electrical signal cable, having an intermediary reel and cable arrangement for preventing torsional cable stresses anywhere between the drum and the output circuitry. The reel is coaxially mounted with the drum, and rotates simultaneously therewith. A ribbon cable is coiled in layers around the reel, and has one end connected to the tail end of the signal cable such that the connection rotates in unison with the drum and reel. Preferably, a housing is provided around the reel to maintain the concentricity of the ribbon cable layers. As the drum rotates, the average effective diameter of the ribbon cable coil changes without causing torsional stresses.

Abstract: A nuclear fuel assembly grid (12) having four substantially solid perimeter plates (28) forming a rigid quadrangle (20) surrounding the fuel elements (36) and having stop surfaces (32) formed on the internal surfaces thereof for contacting each adjacent fuel element. A plurality of interlaced strips (24) are attached to and extend from each plate to the oppositely facing plate, forming a lattice of regularly spaced openings (16) through which the fuel elements traverse the grid. These strips are of two types, the first consisting of two perpendicular center strips (44,44') that divide the grid into four symmetric quadrants, each center strip having a spring tab (48') projecting into each opening (16') contiguous to the center strip. The second type of interlaced strip consists of the remainder of the strips (52), half of which are oriented parallel to one center strip and the other half are oriented parallel to other center strip.

Abstract: The invention provides a hold-down device which maintains a net downward force on a fuel assembly in a nuclear reactor under all thermal and hydraulic conditions in the reactor core region. The hold-down device is particularly applicable in reactors having stainless steel support barrels and Zircaloy guide tubes.The hold-down device of the preferred embodiment of the invention is comprised of coil springs coaxially disposed about alignment posts which extend upwardly from the top end plate of each fuel assembly. A hold-down plate is slideably mounted on the alignment posts and the coil springs are interposed, in compression, between the hold-down plate and the top end plate. In use, the coil springs bias the hold-down plate upwardly against a core alignment plate to provide a downward force on the fuel assembly. The hold-down plate may also serve as a lifting surface for the fuel assembly during fuel handling.