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:
A quick opening hatch for use on a transfer tube of a nuclear reactor plant that is adapted to replace the conventional hatch on the transfer tube. A locking ring is provided with a plurality of screw openings that is adapted for connection to the transfer tube, and a hatch cover fitably received within the locking ring for closing-off the transfer tube. To lock the cover to the ring, latches are movably connected with the cover for locking engagement with the locking ring, and a sprocket with a plurality of crank arms is movably connected with the cover and the latches for movement thereof into locking engagement with a latch housing on the locking ring for locking the cover to the ring and out of engagement with the latch housing for releasing the cover from the locking ring so as to permit removal of the hatch cover from the locking ring to provide access to the transfer tube. A davit assembly is provided which is connected with the transfer tube and the hatch cover to move the cover away and to provide guidance for closing-off the transfer tube. The locking ring and hatch cover also include cooperating keys and keyways for alignment when closing the transfer tube. The cover is provided with sealing rings and the latch housing and latches include cooperating cam surfaces to provide a tight locking engagement by compressing the sealing rings between the transfer tube and the hatch cover.
摘要:
This invention provides shielded access to the irradiated heat exchanger tube bundle of a nuclear steam generator contained within a cask after removal from the generator. This tube bundle must be reduced in size and confined for removal from the containment building through hatchways of generally limited size. Access to the enclosed bundle is at the flanged joints of adjacent sections forming the cask and which are vertically separated to permit an oxygen lance to be inserted therein for burning the tubes at that level. A rotatably supported annular seal ring covers the separation and shields against the escape of radiation or irradiated material during the burning process. The ring provides access ports through which roller supports are mounted on the cask and provide access of the cutting tool to the tubes. Rotation of the ring on the rollers permits the tool to be inserted completely around the cask. After the tubes within one section of the cask are severed, the tubes and that portion of the cask are removed and the ring raised to a next position where the procedure is repeated.
摘要:
A refueling machine for refueling a pressurized water reactor has a trolley which travels on rails mounted on a transversely movable bridge. The trolley supports a refueling mast which includes an outer mast and two horizontally spaced apart, vertically movable gripper masts disposed within the outer mast. This design permits the machine to safely handle two fuel assemblies simultaneously in order to substantially reduce refueling critical path time. The two gripper masts can be raised, lowered and otherwise operated independently of each other. A partition plate extending through the stationary mast between the two movable gripper masts permits each fuel assembly held in the refueling mast to be independently leak tested.
摘要:
An apparatus, which reinforces a shroud that is contained within a reactor vessel, is operable for reinforcement of the shroud in the event of cracking in the shroud. The apparatus comprises a reactor wall positioned surrounding the shroud. A beam is attached to and extends generally axially on the shroud for absorbing the forces generated by the cracking in the shroud, and a radial support is positioned between the beam and the wall of the reactor vessel for transmitting any forces absorbed by the beam to the wall.
摘要:
A jet pump assembly for recirculating coolant through a recirculation loop of a boiling water reactor vessel, the jet pump assembly comprises a jet pump in operative association with the recirculation loop for forcing the coolant through the recirculation loop. A beam is positioned adjacent and in operative association with the jet pump for assisting in maintaining the positional relationship of the jet pump. A bolt is inserted in the beam for resisting the hydraulic forces generated in the jet pump, and an insert is disposed in said beam for receiving and surrounding the bolt which, in turn, reduces stress on the beam.
摘要:
A method of refueling a nuclear reactor whereby the drive mechanism is disengaged and removed by activating a jacking mechanism that raises the closure head. The area between the barrier plate and closure head is exhausted through the closure head penetrations. The closure head, upper drive mechanism, and bellows seal are lifted away and transported to a safe area. The barrier plate acts as the primary boundary and each drive and control rod penetration has an elastomer seal preventing excessive tritium gases from escaping. The individual instrumentation plugs are disengaged allowing the corresponding fuel assembly to be sealed and replaced.
摘要:
A combined fuel assembly and thimble plug gripper for raising and lowering a fuel assembly into a nuclear reactor core, and for lifting and lowering a thimble plug assembly into the fuel assembly, including a vertically movable mast housing a mechanism which causes pivotally mounted fingers on the bottom of the mast to be moved into and out of latching engagement with the nozzle of a fuel assembly when the mast is resting on said assembly. The mast includes a second mechanism which supports second fingers pivotally mounted thereon and actuable by a third mechanism into and out of engagement with a thimble plug assembly suporting plugs adapted to be inserted in control rod guide thimbles in the fuel assembly. The second mechanism further includes an arrangement for lowering or raising the plug assembly respectively into or out of the guide thimbles in the fuel assembly. The apparatus includes control and interlock systems which preclude operation of the mechanisms under certain prescribed conditions.
摘要:
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. The shroud forms a structural element of sufficient strength to support the vessel head, the control rod guide mechanism and the instrumentation tube structure, and includes radiation shielding material for limiting passage of radiation from retracted instrumentation tubes. The shroud is thicker at the bottom adjacent the vessel head, where the more irradiated lower ends of retracted sensors reside. The vessel head, shroud and contents thus can be removed from the reactor as a unit and rested safely and securely on a support.
摘要:
A straightening device (16) for bent fuel assembly alignment pins (12) in an upper core plate (10) comprises elongatged mast (22) haivng an upper and lower portion, bail (25) secured to the upper portion and cross member (28) secured to the lower portion. At one end of the cross member (28) is attached pin straightening assembly (19), the other end having counterweight (31) to assure a horizontal orientation of the cross member (28). Pin straightening assembly (19) is further comprised of housing (37) having wedge-shaped adjustable shim (61) connected to its top surface, the housing (37) secured to the cross member (28) by baseplate (34). Four axially compressible and laterally deformable compression springs (41) are connected between baseplate (34) and housing (37) to provide angular and translational compliance for housing (37). Housing (37) has two vertical holes disposed therein, first hole (50) adapted to receive hardened die insert (54) having bore (55 ) with frusto-conical opening (56) for receiving bent pin (12), and second hole (51) for receiving another pin (14). Connected to baseplate (34) opposite housing (37) is hydraulic ram (44) for moving housing (37) into full planar contact with bottom surface (47) of upper core plate (10) to effectuate the straightening of bent pin (12).