FIELD: power engineering.
SUBSTANCE: invention may be used for simulated calibration of measurement channels of a nuclear reactor handling machine (HM) control system. Metrological characteristics of measuring channels are defined using a simulated calibration bench connected to the HM and comprising devices that perform functions peculiar to equipment of a process channel of a nuclear reactor, measuring channels and an automated control system comprising hardware and software. Calibration of metrological characteristics is carried out in the bench under parametric conditions that are as realistic as actual conditions of fuel handling using reference measurement facilities. Automated calibration of HM channels measurement facilities is carried out with account of actual functions of conversion and error detection depending on influencing factors that are calculated by comparison of values of output metrological characteristics of the HM and the bench. Using the received data, the degree of HM availability for safe fuel handling from a nuclear reactor is determined.
EFFECT: method makes it possible to increase accuracy of measurement of HM channels metrological characteristics and to increase degree of its safety in process of nuclear reactor fuel handling.
5 cl, 7 dwg
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Authors
Dates
2013-04-20—Published
2011-12-01—Filed