Induced nuclear reactions: processes – systems – and elements – With control of reactor – By coolant flow
Reexamination Certificate
2006-10-10
2006-10-10
Palabrica, R (Department: 3663)
Induced nuclear reactions: processes, systems, and elements
With control of reactor
By coolant flow
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,” Nuclear Engineering and Design, 110 (1988), 55-59.
Palabrica R
Westinghouse Electric Co LLC
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