摘要:
Apparatus for releasably engaging an elongated member that is releasably connected to the top nozzle of a nuclear reactor fuel assembly. The top nozzle has an adapter plate disposed at its lower end having at least one passageway therethrough through which the elongated member is disposed. The elongated member has a releasable latching structure at one end that is able to be engaged by the apparatus, having at least one latching member movable between a latched position in which the latching member is able to engage said adapter plate and secure the absorber rod in a stationary relationship with respect to the adapter plate and an unlatched position in which the latching member is able to disengage from said adapter plate so that the elongated member be removed from the fuel assembly. The apparatus comprises a hollow releasing member for moving the latching member of the latching structure between its latched position and its unlatched position, an engaging member connected to the releasing member and extending downwardly through the hollow portion of the releasing member, and an actuating member extending downwardly through the hollow portion of the releasing member and coacting with the engaging member to releasably engage the latching structure.
摘要:
During unrodded refueling, the drive rods and the control rods and coolant-displacement rods, attached to the drive rods, are removed from a fuel assembly, preliminary to the transfer of the fuel assembly, and are reinserted in the reactor after a replacement fuel assembly has been positioned in the reactor. Prior to the transfer of a fuel assembly, a lifting rig is secured to the upper-internals support. A lift plate is removeably mounted on latches in a lower position of the lifting rig. The latches are released and the lift plate is connected to the drive rods. The lift plate is then raised and removeably mounted on latches in an upper position on the lifting rig. In this position, the control rods and coolant-displacement rods are in the guides in the upper internals of the reactor. During the lift-plate raising operation, the loading on the drive rods is monitored and if the loading exceeds a predetermined magnitude, the excess loading is indicated. After the lift plate and the rods suspended from it are positioned on the latches in the upper position, the lifting rig and the upper internals and rods attached to the lift plate are removed from the reactor so that the unrodded transfer of the fuel assemblies may proceed. The replacement of the rods proceeds reversely. In this case, the device which indicates excess loading of a drive rod operates to indicate that the control rod or coolant-displacement rod connected to the drive rod has encountered an obstruction.
摘要:
Method and apparatus for dismantling, shearing and compacting a fuel assembly frame skeleton. A frame is provided which can be placed into the transfer canal of a fuel-handling building for severing a bottom nozzle from the thimble tubes and grids of the frame skeleton, compacting the remainder of the skeleton, and then further severing the thimble tubes and grids into shorter longitudinal lengths, and placing the shortened compacted severed pieces into a container for off-site shipment or on-site storage.
摘要:
A nuclear reactor containment arrangement incorporating a permanent cavity to vessel seal in the form of a flexible quarter-circular annular steel gasket affixed to and extending between the reactor vessel seal plate and cavity wall. The seal functions to isolate the periphery of the vessel from a permanent water-tight compartment above the reactor vessel which is flooded during refueling operations to minimize the release of radiation upon exposure of the nuclear core. The seal is designed to accommodate both radial and axial expansion of the pressure vessel relative to the cavity wall occurring during reactor operation without breaking the water-tight integrity of the seal. The pressure vessel ventilation system is provided with an air exit duct at the reactor nozzle level to facilitate the circulation of air around the periphery of the vessel which would otherwise be restricted at the seal to vessel interface.
摘要:
An apparatus and method are provided for inverting the lower internal assembly of a nuclear reactor. The apparatus includes a frame which is sized to receive the lower internal assembly. The frame supports the lower internal assembly as it is being inverted. The apparatus also includes a spider assembly which fits within the lower internal assembly and provides support for a baffle assembly located therein. The method includes the steps of removing the lower internal assembly from a reactor vessel and rotating the lower internal assembly prior to performing maintenance.
摘要:
A tank is disclosed for containing a liquid in which control rod drive shafts of a nuclear power plant are stored. The tank comprises a lower tank portion having a bottom and a tank wall extending outwardly from the bottom for defining a lower storage cavity of the tank. An upper tank portion having walls is removably attached to the lower tank portion for defining an upper storage cavity of the tank. A plurality of tubes are arranged in the lower tank portion for adaptably receiving the shafts for storage.
摘要:
A method for limiting movement of a thermal shield of a nuclear reactor, and a thermal shield displacement limiter therefor, is provided where at least four and preferably six or more key-way inserts are positioned in pockets machined in the upper portion of a thermal shield, and bolted and doweled to the thermal shield. Each key-way insert is engaged by a limiter key that is bolted and doweled to the core barrel to tangentially restrain movement of the thermal shield relative to the core barrel, while allowing radial and axial movement to the thermal shield relative to the core barrel. Preferably, lock pins extend diametrically through the bolts and dial pins and engage the key-way insert and limiter key, respectively, to lock the bolts and dowels in position, and the engaging surfaces between the key-way inserts and the limiter keys are wear hardened.
摘要:
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. A number of indicators on the tool act to indicate to an operator: when the tool is in the mast full-down position; when the gripping members (49) have been fully actuated; and if there is any slipping of the gripping members within the fuel assemblies. The tool also includes a secondary gripping mechanism which engages the top nozzle of the fuel assembly.
摘要:
A support framework for a double column of U-shaped tubes of a heat exchanger for vertically suspending the tubes above the heat exchanger during a tubing operation is shown. That portion of the framework which supports the U-bends of the tubes is primarily used to support the tubes above the tubesheet and lower the tubes into the tubesheet as a unit. The U-bend support framework includes a vertical member in which the separate tubes of the double column are clamped to normally prevent movement of the tubes therein and also permits individual release of the tubes when necessary.
摘要:
Described is a movable work station apparatus including travelling-hoist supported tools and a vertically and rotarywise movable frame-carried radiation-shielded enclosure, or gondola, for working personnel involved in tube-bundle-replacement tasks performed within the shell of a steam generator in a nuclear plant. The enclosure, or gondola, is divided and accommodates four upright workers in mutually-facing pairs at opposite sides of a work-accommodating clearanceway observable and accessible from the gondola interior via lead glass windows and hand holes.