PROCÉDÉ DE CONTRÔLE DE LA VITESSE DE CORROSION D'ÉQUIPEMENTS DE CIRCUITS INDUSTRIELS DE CENTRALES NUCLÉAIRES

摘要

A method of corrosion rate control of nuclear power plants process circuits equipment, whereby the electrochemical potential of the structural material of heat exchanging tubes and the specific electrical conductivity of blowdown water in steam generators are measured, the polarization resistance of the structural material of the pipelines of the condensate-feeding path and the specific electrical conductivity of feed water in steam generators are measured, and these parameters are automatically averaged and compared with the rated values. The electrochemical potential and the specific electrical conductivity of blowdown water from steam generators are displayed as points on a two-parameter nomogram with the coordinates of "electrochemical potential and specific electrical conductivity of the H-cationated sample" of blowdown water divided into areas A, B, D, and F which determine various degrees of corrosion activity in relation to the material of heat exchanging tubes of the blowdown water in steam generators in accordance with the operating conditions. The values of the polarization resistance and the specific electrical conductivity of feed water from steam generators are displayed as points on a two-parameter nomogram with the coordinates of "polarization resistance and specific electrical conductivity of the H-cationated sample" of feed water divided into areas G, Y, X, and Z which determine various degrees of corrosion activity in relation to the material of pipelines of the feed water circuit in steam generators in accordance with the operating conditions. Depending on the location of the point in one of the areas of the two-parameter nomograms, no actions are taken, or coolant parameters are adjusted, or the power unit is shut down.