REACTOR CONTROL SYSTEM VERIFICATION

A computer controlled system and method accurately and rapidly verifies the in-place, dynamic response of a transducer/sensor to a time dependent state variable. The verification system includes a programmable ramp generator which introduces a time varying signal simulating a time dependent state variable, e.g., pressure, temperature, flow rate, etc., to a protection system such as used in a nuclear reactor power plant. The verification system further includes means for measuring and displaying the response of the protection system to input signal variation over time. The verification system and method ensures that the protection system outputs an appropriate control signal, such as a shutdown signal, for terminating nuclear reactor power plant operation when the magnitude or time dependent variation of the state variable is not within predetermined limits.