METHOD FOR MEASURING COOLANT FLOW IN PROCESS CHANNELS OF GRAPHITE-MODERATED WATER-COOLED REACTOR Russian patent published in 2005 - IPC

Abstract RU 2252461 C2

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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RU 2 252 461 C2

Authors

Rjakhin V.M.

Cherkashov Ju.M.

Filimontsev Ju.N.

Egorov A.K.

Poljanskikh S.A.

Druzhinin V.E.

Uvakin A.V.

Nikolaev P.T.

Kalinin P.V.

Degtjarev V.G.

Ivanov V.I.

Shmonin Ju.V.

Chizhevskij Ju.B.

Rechkiman A.Eh.

Shevelev A.F.

Dates

2005-05-20Published

2003-01-10Filed