Nuclear reactor internals construction and failed fuel rod detection system
AssigneeWestinghouse Electric Corp.
InventorsErling Frisch, deceased, Harry N. Andrews
Life of this patent
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Abstract
A system is provided for determining during operation of a nuclear reactor having fluid pressure operated control rod mechanisms the exact location of a fuel assembly with a defective fuel rod. The construction of the reactor internals is simplified in a manner to facilitate the testing for defective fuel rods and to reduce the cost of producing the upper internals of the reactor.
Claims13
In a nuclear reactor having a pressure vessel with a removable closure head and fuel assemblies mounted within the vessel between a lower core plate and an upper core plate, in combination, means supporting the lower core plate and the fuel assemblies, an upper support plate mounted in the vessel, support tubes extending between the upper support plate and the upper core plate to support the upper core plate, rectilinearly movable control rods for preselected fuel assemblies, drive shafts attached to the control rods, adapter tubes extending through the closure head, said drive shafts entering the vessel through the adapter tubes, a plurality of control rod guide tubes located in each of said support tubes and extending the length thereof, and at least one of said control rod drive shafts and its attached control rod in each of said guide tubes.
Dependencies are inferred from the claim text.