Nozzle seal
AssigneeThe United States of America as represented by the United States Energy Research and Development Administration
InventorRichard Frederick Herman
Life of this patent
Estimating the term…
Abstract
In an illustrative embodiment of the invention, a nuclear reactor pressure vessel, having an internal hoop from which the heated coolant emerges from the reactor core and passes through to the reactor outlet nozzles, is provided with sealing members operatively disposed between the outlet nozzle and the hoop. The sealing members are biased against the pressure vessel and the hoop and are connected by a leak restraining member establishing a leak-proof condition between the inlet and outlet coolants in the region about the outlet nozzle. Furthermore, the flexible responsiveness of the seal assures that the seal will not structurally couple the hoop to the pressure vessel.
Claims5
A reactor system comprising a pressure vessel having inlet and outlet nozzles, a distribution hoop within said pressure vessel having a fluid passage opening in flow communication with a respective one of said inlet and outlet nozzles, sealing means disposed about said hoop opening and interposed between said hoop and said outlet nozzle to establish a leak-proof connection between said hoop and said nozzle, said sealing means having an annular cup shaped cross section compressing ring, a sealing ring in axial alignment with the compression ring, the sealing ring being slideably engaged within the cup shaped compression ring forming a restricted leakage flow passageway therethrough, a spring operatively disposed between said compression ring and said sealing ring to force the sealing ring into leak tight engagement with the outlet nozzle, and an impervious flexible leak restraining member disposed in space surrounding relation to the compression ring and the sealing ring and circumferentially seal welded thereto to prevent leakage flow through the passageway.
Dependencies are inferred from the claim text.