FIELD: nuclear reactors. SUBSTANCE: method involves separate measurement of reactivity pulse parameters in frequency ranges of 0.2-5000 and 100-5000 Hz, determination of core response function to passage of first gas bubble from defective point on the basis of these measurements, and comparison of this response function with axial distribution of coolant efficiency for each fuel assembly. Device that implements this method depends for its operation on measurement of time intervals within which gas bubbles pass through characteristic points of core showing extreme or zero values of coolant efficiency distribution and their comparison with time periods when coolant flowing in core passes through same points. EFFECT: improved reliability of measurement results. 2 cl, 2 dwg
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Authors
Dates
1996-11-27—Published
1990-08-22—Filed