Bwr core flow measurement enhancements

Abstract

An apparatus and process for the accurate measurement and calibration of core flow in a boiling water reactor is disclosed. The reactor includes a pressure vessel having internal forced circulation through the core. An annular downcomer region establishes reactor coolant flow downwardly in the periphery of the reactor vessel and finally upwardly and centrally into the core across a core plate. A pressure sensor detecting the pressure differential across the core plate is utilized. This pressure sensor has its measurement enhanced by input from local power range monitors in the core to utilize both the sensed pressure differential and the power to predict more accurately flow in the reactor. An algorithm is developed for utilizing the pressure differential and the real time readings from the local power range monitor to accurately gauge overall reactor coolant flow. To ensure accurate calibration, two calibration standards are itilized at steady states of reactor power output and coolant flow. A first calibration standard includes the installation of thermocouples adjacent the reactor core plate for measurement of fluid enthalpy of the coolant as it flows upwardly through the reactor core. The determined enthalpy is utilized in an energy flow balance wherein the core flow rate is solved for as an unknown. A second calibration standard utilizes the sensed pressure differential across the annular pump deck of the forced circulation pumps. The two standards are combined in output utilizing a least squares averaging, and the result combined to calibrate the disclosed algorithm.