Method for controlling a pressurized water nuclear reactor during stretchout
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United States of America Patent
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Nov 24, 2020
Grant Date -
Dec 22, 2016
app pub date -
Jul 4, 2014
filing date -
Jul 4, 2013
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Abstract
A method for controlling a pressurized water nuclear reactor is provided, including core producing thermal power, sensors for acquiring the mean temperature of the primary coolant and for calculating the thermal power, actuators for controlling the axial distribution of power, the control method including:
- a first control phase for controlling the reactor during normal operation by controlling the mean temperature of the primary coolant so as to make it correspond to a reference temperature profile (Pref) dependent on the thermal power of the reactor; anda second control phase, referred to as stretchout, that occurs after normal operation of the reactor in order to control the reactor in stretchout by controlling the axial distribution of power, the mean temperature varying freely in a temperature range delimited by an upper limit and a lower limit.
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