FIELD: nuclear power stations; coolant flow measurements in nuclear reactor process channels.
SUBSTANCE: coolant flow measurement method depends on neutron flow disturbances in reactor core causing changes in nitrogen activity within steam-water pipeline loop of process channel. Changes in power and nitrogen activity signals in process channel are recorded and time shift between these signals is calculated; then coolant volumetric flowrate through process channel is calculated, pipeline volume being known in advance.
EFFECT: enhanced accuracy and reliability of coolant flowrate measurement results.
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Authors
Dates
2005-05-20—Published
2003-01-10—Filed