FIELD: power engineering.
SUBSTANCE: method includes a stage for obtaining values of operational parameters of a reactor and determining the first 3D distribution of capacity with the help of a neutron calculation code, which instantly solves a diffusion equation and updates isotopic balance in the core in case of fuel depletion, based on values of parameters of normal operation of reactor code, and also a stage to control 3D distribution of capacity on the basis of measurements of a neutron flow with the help of sensors installed outside the reactor and temperature sensors.
EFFECT: invention makes it possible to efficiently determine 3D distribution of capacity without installation of additional instrumentation in the reactor core.
2 cl, 2 dwg
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