Combustion Engineering, Inc.

Christo Andrea

Richard C Noyes

Edward A Siegel

Clive Frederick Dupen

Improved core servicing apparatus for a nuclear reactor of the type having a reactor vessel, a vessel head having a head penetration therethrough, a removable plug adapted to fit in the head penetration, and a core of the type having an array of elongated assemblies. The improved core servicing apparatus comprises a plurality of support columns suspended from the removable plug and extending downward toward the nuclear core, rigid support means carried by each of the support columns, and a plurality of servicing means for each of the support columns for servicing a plurality of assemblies. Each of the plurality of servicing means for each of the support columns is fixedly supported in a fixed array from the rigid support means. Means are provided for rotating the rigid support means and servicing means between condensed and expanded positions. When in the condensed position, the rigid support means and servicing means lie completely within the coextensive boundaries of the plug, and when in the expanded position, some of the rigid support means and servicing means lie without the coextensive boundaries of the plug.

Nuclear reactor core servicing apparatus

Improved nuclear reactor arrangement to facilitate both through the head instrumentation and insertion and removal of assemblies from the nuclear core. The arrangement is of the type including a reactor vessel head comprising a large rotatable cover having a plurality of circular openings therethrough, a plurality of upwardly extending nozzles mounted on the upper surface of a large cover, and a plurality of upwardly extending skirts mounted on a large cover about the periphery or boundary of the circular openings; a plurality of small plugs for each of the openings in the large cover, the plugs also having nozzles mounted on the upper surface thereof, and drive mechanisms mounted on top of some of the nozzles and having means extending therethrough into the reactor vessel, the drive mechanisms and nozzles extending above the elevation of the upwardly extending skirts. The improvement in the above type of arrangement comprises a skirt extension and refueling plug for each of the holes of the large rotatable cover for providing access to the nuclear core over each of the assemblies therein. The extension skirt is mountable in sealing relationship to the upwardly extending skirts when the small plugs are removed from the holes in the large rotatable cover, the upwardly extending extension skirt extending upwardly above the elevation of the nozzles on a large rotatable cover when the drive mechanisms have been removed therefrom. The extension skirt includes a laterally extending lip which overlies and is positioned above some of the nozzles in close proximity with the upwardly extending skirt and which supports bearing means for rotatably supporting the refueling plugs for rotation within a circular opening defined within the upwardly extending skirt. The refueling plug includes an opening therethrough through which the assemblies from in the nuclear core may pass. The opening in the refueling plug is such as to provide access over each of the assemblies of the nuclear core upon rotation of the refueling plug and a large rotatable cover.

Core access system for nuclear reactor

A fuel handling machine for a liquid metal cooled nuclear reactor in which a retractable handling tube and gripper are lowered into the reactor to withdraw a spent fuel assembly into the handling tube. The handling tube containing the fuel assembly immersed in liquid sodium is then withdrawn completely from the reactor into the outer barrel of the handling machine. The machine is then used to transport the spent fuel assembly directly to a remotely located decay tank. The fuel handling machine includes a decay heat removal system which continuously removes heat from the interior of the handling tube and which is capable of operating at its full cooling capacity at all times. The handling tube is supported in the machine from an articulated joint which enables it to readily align itself with the correct position in the core. An emergency sodium supply is carried directly by the machine to provide make up in the event of a loss of sodium from the handling tube during transport to the decay tank.

Nuclear fuel handling apparatus

A spent fuel assembly handling tube closure valve is provided which assures minimal or zero leakage of trapped liquid metal coolant from the handling tube. One sealing surface of the closure valve is spherical while the other is conical. The spherical-conical combination enables an adequate seal even when the valve cap is misaligned. A further safeguard against leakage is made possible by a sacrificial inert gas system utilizing the diving bell principle. A metered gas supply system supplies additional sacrificial gas should a leak develop. A high-low level mutual inductance probe operates as a leak detector allowing the timely addition of greater quantities of sacrificial gas.

Anti-leak closure valve

A device is provided which is installed in a reactor prior to carrying out refueling operations and which accurately locates and isolates a selected core location to permit rapid withdrawal and insertion of fuel subassemblies at that location. A shielded plug designed to cooperate with the refueling apparatus is inserted into an access port in the reactor head. A structural shroud extends down from the plug and carries at its lower end a radially floating, hexagonal spreader tube with mechanisms to rotate it for angular alignment purposes and a linear drive for inserting it into the core. The upper end of the spreader tube serves as a guide for leading the fuel handling apparatus into alignment with the chosen subassembly.

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Windsor Locks, CT, United States of America

Christo Andrea