Abstract: Leak-detection system and method for detecting a leaking container. The system includes an enclosure defining a cavity therein surrounding the container, which container may be a nuclear fuel rod having fission products leaking through a breach in the exterior surface of the fuel rod. The fission products are capable of adhering to the exterior surface of the fuel rod as the fission products leak through the breach in the fuel rod. A radiation detector is in communication with the cavity for detecting the fission products leaking through the breach. Moreover, a gas injector is in communication with the cavity for injecting a multiplicity of carrier gas bubbles into the cavity to remove any fission products adhering to the exterior surface of the fuel rod and to carry the fission products removed thereby to the radiation detector. In this manner, the detector detects the leaking fission products even though they may tend to adhere to the exterior surface of the fuel rod.

Abstract: A device for transferring a poison rod assembly from one fuel assembly to another fuel assembly. The device comprising winch means cooperatively associated with the poison rod assembly for lifting and transferring the poison rod assembly; a tubular member attached to the winch means at one end and adapted to be attached to the poison rod assembly at its other end.for latching onto the poison rod assembly; motor means attached to the winch means for driving the winch means; and actuator means communicating with the tubular member for moving the tubular member in an arcuate motion for latching the tubular member to the poison rod assembly.

Abstract: A nuclear reactor such as a pressurized water reactor has an integrated head package providing structural support and increasing shielding leading toward the vessel head. A reactor vessel head engages the reactor vessel, and a control rod guide mechanism over the vessel head raises and lowers control rods in certain of the thimble tubes, traversing penetrations in the reactor vessel head, and being coupled to the control rods. An instrumentation tube structure includes instrumentation tubes with sensors movable into certain thimble tubes disposed in the fuel assemblies. Couplings for the sensors also traverse penetrations in the reactor vessel head. A shroud is attached over the reactor vessel head and encloses the control rod guide mechanism and at least a portion of the instrumentation tubes when retracted.

Abstract: Refueling apparatus for a nuclear reactor including a bridge and a trolley. The bridge is moveable in tracks along the containment of the pit in which the reactor is immersed in water and the trolley moveable in tracks on the bridge at right angles to the tracks on the bridge. The trolley carries a mast assembly for engaging, raising, and lowering a nuclear-reactor component assembly involved in the refueling. The mast includes an elongated member for engaging control-rod and thimble plug assembly and a gripper for raising fuel assemblies. The elongated member is moveable upwardly or downwardly.A TV camera and a light source and reflector are mounted on the gripper assembly at the lower end of the mast assembly. The source and reflector illuminate a selected part of the fuel assembly which is to be transferred and the camera is directed to this part so as to pick up an image of this part. The cooperative TV-receiver monitor on the console on the trolley is provided with cross hairs.

Abstract: Refueling apparatus for a nuclear reactor including a bridge and a trolley movable at right angles to each other over a pit. The trolley carries a mast assembly for engaging, raising, lowering reactor component assemblies.The mast assembly carries electric cables and compressed air hoses from electric and air driven components on the mast and is rotatable relative to the trolley. The cables and hoses are passed from the mast assembly through a flexible cable tray which is oriented with its cable-carrying slot vertically in the configuration generally of an S. The cable tray is connected to the mast at one of its ends, is partly wound around the mast from that end and departs from the mast a predetermined distance at the opposite end. The tray remains fixed at the opposite end as it is wound on or unwound from the mast, so that the cables and hoses as they pass from the opposite end to electrical and air terminals as the trolley remains anchored at the opposite end.

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: Refueling apparatus for a nuclear reactor including a bridge and a trolley. The bridge is moveable in tracks along the containment of the pit in which the reactor is immersed in water and the trolley moveable in tracks on the bridge at right angles to the tracks on the bridge. The trolley carries a mast assembly for engaging, raising, lowering a nuclear-reactor component assembly involved in refueling. The mast includes an elongated member for engaging control-rod and thimble plug assembly and a gripper for raising fuel assemblies. The elongated member is moveable upwardly or downwardly.The bridge, trolley and mast assembly each has a pulse generator which produces pulses in accordance with the movement of each. The number of pulses produced when the bridge, trolley or elongated member move to a position at a predetermined distance from a reference position is a measure of the new position of each.

Abstract: A guide pin assembly for aligning the upper hold down plate of the top nozzle of a fuel assembly with the upper core plate of a pressurized water nuclear reactor includes a guide pin, a nut and a locking cup. The guide pin includes a nose, a threaded portion, a shaft, and an end. The radial alignment section of the shaft has a diameter that is approximately the diameter of a bore in the upper core plate of a nuclear reactor. The lower section of the shaft has a diameter less than that of the radial alignment section. The end includes a top having a diameter greater than that of the diameter of the bore in the upper core plate. The guide pin is insertable within a bore in the upper hold down plate of the top nozzle of the fuel assembly and through the bore in the upper core plate so that the nose and at least a portion of the threaded portion of the guide pin protrude above the upper core plate. The nut is adapted to be threaded onto the threaded outer surface of the threaded portion of the guide pin.

Abstract: An apparatus for loading and unloading a fuel assembly in a nuclear reactor has a bridge and trolley for positioning the fuel assembly and a pair of concentric inner and outer masts with the inner mast vertically movable in the outer mast and guide means to concentrically position the inner mast within the outer mast during such vertical movement. The guide means comprises inner members on the inner mast which cooperate with outer members on the outer mast, the outer members pivotally mounted on a framework on the outer mast for movement towards or away from the inner members. An alignment device is provided to precisely align superimposed outer members and provide vertical alignment therebetween, with an adjustment device provided to aid in the precise alignment of the same.

Abstract: A method of crimping a locking cap secured to the nut of a new split-pin assembly to the new split-pin to preclude turning of the nut and pin relative to each other. The method is practiced with apparatus including a crimping mechanism including crimping jaws having crimping pins face-to-face near one end. The jaws have external cam surfaces. The crimping pins are retracted and brought into crimping engagement with the cap to be crimped by cam followers which traverse the cam surfaces when actuated hydraulically through a C-frame connected to the cam followers. The crimping mechanism is mounted on a support which is moveable by a hydraulic cylinder between a retracted setting, where it is latched generally vertically, and an operating setting where it is positioned generally horizontally.

Abstract: A refueling machine within a nuclear reactor facility includes an inner mast or gripper tube (12) to the bottom of which is secured a gripper assembly (16). An actuator tube (20) controls the gripper mechanisms of the gripper assembly (16), and in order to insure proper and accurate alignment of the gripper mechanisms with the fuel assembly nozzles, a television camera (26) is mounted within the actuator tube (20). A television monitor (34) is operatively connected to the television camera (26), the monitor (34) being disposed upon the refueling machine personnel trolley. The television camera (26) is removably mounted within the actuator tube (20) by a bayonet-type system which includes camera housing lugs (78) which are adapted to pass through slots (76), subsequent to which the camera housing (28) and the lugs (78) are rotated 90.degree. whereby the lugs (78) are seated within recesses (80).

Abstract: A refueling machine (100) is provided with a latching/unlatching rod (116) which is provided with a hexagonally configured head portion for mated engagement with a hexagonally configured socket (34) defined within a latching/unlatching screw (22) of a fuel assembly (10) whereby the fuel assembly (10) may be securely mechanically connected to the lower core support plate of the reactor internals. The latching/unlatching rod (116) is fixedly connected to a housing (118) which is co-axially disposed within a torque tube (140), the latter of which is fixedly secured to the lower end of a spur gear (130). The spur gear (130) is rotatably engaged with a drive spur gear (148) through means of an idler gear (128), whereby torque is transmitted to the torque tube (140).

Abstract: A refueling machine (10, 100) within a nuclear reactor facility includes an outer stationary mast (12, 112) upon which are mounted a plurality of light sources (28, 128), inclined mirrors (36, 136), and television cameras (24, 124) for scanning a fuel assembly (32) for the existence of any defects or damage as the fuel assembly (32) is being withdrawn from the reactor core into the stationary mast (12, 112). In a first embodiment, the light sources (28), mirrors (36), and cameras (24) are mounted upon a sleeve (14) clamped about the lower end of the stationary mast (12), while in a second embodiment, the light sources (128), mirrors (136), and cameras (124) are mounted upon a basket-type framework (178) which is suspendingly supported upon the stationary mast (112) by support cables (158). A fixture (176) can support the framework (178) in an off-the-mast mode so as to permit remote-controlled maintenance or repair of the light sources ( 128), mirrors (136), or cameras (124).

Abstract: A crimping tool for crimping a locking cap secured to the nut of a new split-pin assembly to the new split-pin to preclude turning of the nut and pin relative to each other. The tool includes a crimping mechanism including crimping jaws having crimping pins face-to-face near one end. The jaws have external cam surfaces. The crimping pins are retracted and brought into crimping engagement with the cap to be crimped by cam followers which traverse the cam surfaces when actuated hydraulically through a C-frame connected to the cam followers. The crimping mechanism is mounted on a support which is moveable by a hydraulic cylinder between a retracted setting, where it is latched generally vertically, and an operating setting where it is positioned generally horizontally. The piston rod of the cylinder has a slotted extension. The slot is engaged by a pin which is connected to the support.

Abstract: The tool serves to brush the upper and lower counterbores and the channels which interconnect the counterbores in the lower flange of the lower guide tube of a nuclear reactor. The top entrance to the counterbores is partially obstructed by the wall of the guide tube which extends above the flange. The tool includes an upper brush and a lower brush mounted with their axes displaced laterally in opposite directions with reference to the common axis of the counterbores. The mounting is movable linearly and is pivotal about a horizontal axis and includes cam slots engaged by cam followers. When the mounting is moved in one direction (down typically) the upper brush is moved by the cam action into cleaning relationship with the upper counterbore. When the mounting is moved in the opposite direction (up), the lower brush is moved by the cam action into cleaning relationship with the lower counterbore and with the channel between counterbores.

Abstract: Apparatus for transferring, not only the fuel assemblies, but other component assemblies including control-rod assemblies, thimble-plug assemblies, poison assemblies and the like during refueling of a nuclear reactor. The apparatus includes an outer mast for guiding and protecting the component assemblies which are transferred, an inner mast movable vertically within the guiding mast. The inner mast has grippers for engaging and lifting or lowering fuel assemblies. The outer mast has internal grooved rollers along its length. The inner mast is formed at oppositely facing channels held in a rigid assembly by plates to which the channels are secured. Opposite corners formed by the flanges and the webs of the channels penetrate into the grooves of the rollers and the inner mast is guided and held in position by the rollers. The apparatus also includes an elongated tube within the inner mast movable vertically relative to the inner mast.

Abstract: A refueling machine for inserting and removing fuel assemblies from a nuclear reactor including a pair of concentrically disposed stationary masts mounted on a movable bridge which spans the containment walls of the reactor. The bridge supports a trolley movable transversely to bridge movement thus providing an arrangement wherein the masts can be precisely positioned over a fuel assembly in the reactor core. A hoist mounted on the outer of the masts supports a vertically movable inner mast of a size sufficient to enclose a fuel assembly. An actuator tube inside the inner mast moves gripper fingers on the bottom thereof into engagement with the top nozzle of a fuel assembly prior to lifting it upwardly out of the reactor core.

Abstract: Apparatus is disclosed for handling radioactive fuel assembly during transfer operations. The radioactive fuel assembly is drawn up into a shielding sleeve which substantially reduces the level of radioactivity immediately surrounding the sleeve thereby permitting direct acess by operating personnel. The lifting assembly which draws the fuel assembly up within the shielding sleeve is mounted to and forms an integral part of the handling apparatus. The shielding sleeve accompanies the fuel assembly during all of the transfer operations.