Reactor control system verification

Details Reactor control system verification Reactor control system verification

1987-03-05

1988-11-08

Walsh, Donald P.

Induced nuclear reactions: processes, systems, and elements

With control of reactor

By electronic signal processing circuitry

376216, 364579, 364580, G21C 736

Patent

active

047833076

ABSTRACT:
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.

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Exerpt from the official transcript of meeting of United States of America Nuclear Regulatory Commission on Jun. 30, 1987 regarding "Discussion/Possible Vote on Full Power Operating License for Braidwood-1."

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