System for automatic refueling of a nuclear reactor

Abstract

A refueling system for a nuclear power plant utilizing a data network to provide for automatic control and enhanced monitoring of the entire fuel transfer process. The refueling system of this invention provides integrated control of the refueling machine within the containment building, the spent fuel handling machine within the fuel storage building, and the fuel transfer system between the buildings. The system provides supervisory control of the overall system operation via a remote control station, while at the same time, having the capability for local on-line control of each element of the system in the event of network failure. The system may automatically identify individual fuel assemblies with an optical scanner. An in-mast sipper connected to the network automatically tests for leaking fuel assemblies. A revised core load pattern and a revised sequence plan can be calculated by the system in the event of the discovery of a leaking fuel assembly. The system may also include a fuel loading guide to facilitate the automatic loading of bowed fuel assemblies. Human interface with the system may be provided at a plurality of locations, including for example, a refueling control station and a remote status panel. The reactivity of the reactor core may be monitored by the system during core loading, and corrective action taken automatically if a predetermined setpoint is exceeded. Core spacing verification may also be performed automatically.