“…The corrosion behavior of the main contemporary steam generator tube material for PWRs, namely, Alloy 690 (UNS N06690), has been extensively studied in the last decade in a simulated primary coolant [13][14][15][16][17][18][19][20][21][22][23][24][25][26][27][28][29][30]. The oxide films formed in nominal PWR conditions (~1000 ppm B, ~2 ppm Li, ~20-30 cm 3 kg −1 dissolved H 2 ) are usually described as a duplex oxide layer with a compact inner layer enriched in chromium and a discontinuous outer layer that contains mainly, according to the test facilities, nickel ferrite, nickel chromite and nickel hydroxide [14,16,26,29].…”