Method of controlling corrosion rate of technical circuit equipment in nuclear power plant

摘要

Measuring the electrochemical potential of the structural material of the heat exchange tube and the specific electrical conductivity value of the purified water of the steam generator as a method of controlling the corrosion rate of equipment in the technological circuit of a nuclear power plant. Measure the value of the polarization resistance of the structural material of the pipeline of the condensate supply path and the specific electrical conductivity of the feed water of the steam generator, automatically averaging these parameters and comparing them with standardized values. The electrochemical potential and specific electrical conductivity values of the purged water of the steam generator are two variables, together with the coordinates of the “electrochemical potential of the cationized sample - specific electrical conductivity” of the purified water divided into regions A, B, D, F. It is represented in the form of dots in the nomogram. The zone characterizes the degree of corrosive activity on the heat exchange material of the purifying water pipe of the steam generator, depending on the operating conditions. The values of the polarization resistance and specific electrical conductivity of the feed water of the steam generator are plotted on a two-parameter nomogram with the coordinates “Polarization resistance - H-cationized sample of specific electrical conductivity” of the feed water divided into regions G, Y, X, Z. displayed in the form of dots. The domains characterize different degrees of corrosive activity with respect to the material of the feedwater circuit pipeline of the steam generator, depending on the operating regime. Depending on the position of the point in one of the two parameter nomograms, no action is taken, a coolant parameter adjustment is performed, or the power supply is stopped.