FIELD: nuclear power.
SUBSTANCE: invention relates to nuclear power and can be used for determination of heat carrier flow in channels or fuel assemblies of nuclear reactors in tests and operation. Said result is achieved by measuring maximum and mean-square deviation of heat carrier temperature at output of channels and maximum or mean-square deviation of reactor power or heat carrier flow rate through reactor, used for checking quality of flow of transient processes and adjustment of reactor automatic control systems.
EFFECT: technical result is higher accuracy and efficiency by determining values of thermal inertia of thermal detectors in reactor channels in real conditions of their operation.
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