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: A temperature monitor for a generator stator core is disclosed. The monitor comprises a light source which generates a light beam, heat sensitive targets which receive the light beam and which either block the light beam or allow the light beam to pass through, depending on the temperature in the stator core, fiber optic receivers associated with the target which detect whether the light beam has passed through or been blocked by the targets and which also convert the light beams into responsive electrical signals, and a computer which receives the responsive electrical signals from the receiver, converts the responsive electrical signals into processed electrical signals, and outputs data to a user, whereby temperature conditions in the stator core can be monitored.

Abstract: Apparatus for sealing the seam between two conduits which includes two cooperatively threaded members for applying relative axial clamping forces to the conduits. When the two cooperatively threaded members are relatively rotated, they apply relative axial force to the conduits thereby causing a sealing means to be disposed in tight contact between the conduits.

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 portable test device for set point and leakage testing of a variety of sizes of pressure relief valves using the actual operating fluid under realistic test conditions includes a housing having a cylindrical bore, a main piston slidable in the bore to form at one end a test chamber, a translator piston also slidable in the bore to form at the other end a pressurizing chamber, and a spring pack biasing the pistons apart. An adapter plate mounts various size relief valves to the device with the valve inlet in communication with the test chamber. With a fixed amount of test fluid sealed in the test chamber, the pressure of hydraulic fluid introduced into the pressurizing chamber increases the pressure of the test fluid until the valve actuates. An electric immersion heater in the test chamber provides the capability for hot liquid testing and vapor testing.