Statistical methods of measuring the power of a reactor are based on the point model of kinetics, which introduces methodological errors into the final result. There exist three main sources of error which are associated with the value of neutrons, the finite dimensions and coordinate of the detector, and the finite time required to establish the neutron flux. Expressions for the corrections as well as the results of Monte Carlo calculations performed for the FS-1M critical stand are presented. It is shown that the resulting correction factor can range from 0.969 to 1.131 depending on the location of the neutron detector.Statistical methods for investigating the physical characteristics of nuclear reactors appeared at the beginning of the 1950s, but already in the 1970s they were replaced by more effective methods using pulsed neutron generators. Nonetheless, statistical methods for measuring the power of a reactor are still needed, since they are more easily implemented than, for example, the absolute counting chamber method, and their statistical accuracy is high and the measurement time is acceptable (3-5% over 30-60 min). Many variants of these methods have been developed, but they all have the same drawbackthey are based on the point kinetics model. This introduces methodological errors into the final result.The present article examines the sources of error and methods for computing the corresponding corrections for one of the most widely used methods -the frequency-noise method. The computational estimates of the corrections are made for the FS-1M critical stand. Sources of Errors and Expression for Corrections.In the frequency-noise method [1], the fission rate -the number of fissions N in a reactor in 1 sec -can be expressed in terms of the measured parameters (detector current I and the spectral density S k ) as follows:
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