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U.S. Department of Energy
Office of Scientific and Technical Information

Apparatus and method for servicing a nuclear reactor system

Patent ·
OSTI ID:5466690

An apparatus is described for servicing a pressurized water nuclear power system during a fuel outage wherein the system is the type which includes a reactor vessel disposed in a containment annulus beneath a refueling canal, a hot leg piping system connecting the vessel to an inlet of an associated steam generator unit through which heated water flows, a cold leg piping system connecting a lower portion of the steam generator unit to the nuclear reactor vessel for returning cooled water to the vessel, a pumping unit connected in the cold leg piping system for pumping the water to the nuclear reactor vessel, and a cold leg entrance nozzle in the reactor vessel connected to the cold leg piping system. The apparatus consists of: a plug unit for sealing the entrance nozzle of the cold leg piping system; the plug including sealing means for sealing the entrance nozzle and cold leg piping system; an installation assembly for inserting the plug unit in the cold leg entrance nozzle; the installation assembly including reciprocating insertion means for inserting the plug unit into the entrance nozzle of the cold leg piping system and removing the plug unit therefrom following servicing of the nuclear reactor system; connecting means carried adjacent an end of the reciprocating insertion means for releasably connecting the insertion means and the plug unit so that plug unit may be left detached in the cold leg piping system after insertion; and means carried above the reactor vessel for raising and lowering the installation assembly in and out of the reactor vessel.

Assignee:
NOV; EDB-86-135095; NOV-85-014960
Patent Number(s):
US 4591477
OSTI ID:
5466690
Country of Publication:
United States
Language:
English