METHODOLOGICAL ERRORS OF STATISTICAL MEASUREMENTS OF ABSOLUTE REACTOR POWER

摘要

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.