Method for calibrating steam generator water level measurement

Induced nuclear reactions: processes – systems – and elements – With control of reactor – By coolant flow

Reexamination Certificate

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Details

C376S258000, C376S246000, C376S260000, C122S451100, C073S299000

Reexamination Certificate

active

07120218

ABSTRACT:
A method is provided for determining and controlling feed water level in a steam generator of a nuclear power plant, whereby the water level sensor is calibrated in terms of the pressure drop across structural components in the feed water path. The water level differential pressure sensor is calibrated so that maximum water level is indicated as the level corresponding to the upper tap level plus the pressure drop across the foregoing structural components at maximum power plant power.

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Mandl et al., “Water Inventory Determination Using Differential Pressure Cells,” v. 110, n 1 12(I), 1988, p. 55-59.
Mandl et al., “Water Inventory Determination Using Differential Pressure Cells,” Nuclear Engineering and Design, 110 (1988), 55-59.

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