Inventors:
James R. Raymond - Allegheny PA
Clarence I. Thomson - Murrysville PA
Assignee:
Westinghouse Electric Corporation - Pittsburgh PA
International Classification:
G21C 19307
Abstract:
In a nuclear reactor water cleanup pump, a purge fluid is continuously delivered during at least the operation of the pump into the cavities containing the bearings and the electrical motor at a desired flow rate. The desired flow rate being based on the heat loss from said pump and a differential temperature defined as being the difference between the predetermined temperature of the purge fluid delivered into the pump and the desired temperature for the purge fluid exiting the pump.