METHOD TO CONTROL SPEED OF CORROSION OF COOLANT CIRCUIT IN NUCLEAR URANIUM AND GRAPHITE REACTOR

摘要

FIELD: power engineering.;SUBSTANCE: values of electrochemical potential, specific electric conductivity are measured, these parameters are automatically averaged, compared with the rated values. Results of comparison are displayed on a mnemonic circuit of a display screen, quality of the water and chemical regime is assessed. Actions aimed at corrosion speed optimisation are taken. At the same time values of electrochemical potential and specific electric conductivity are displayed in the form of points in a two-parameter nomogram with coordinates "electrochemical potential - specific electric conductivity", separated into three zones, A, B, C, which characterise different extents of corrosion activity of a coolant in accordance with the mode of operation. Depending on availability of the point of coordinates crossing in one of action zones, coolant parameters are either left as they are or adjusted, or a power unit is shut down.;EFFECT: efficient assessment of corrosion activity of a coolant in a process circuit of a power unit at a nuclear power plant and efficiency of corrective actions.;3 dwg