2021
DOI: 10.3390/ma14154105
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Effects of Zinc Addition on the Corrosion Behavior of Pre-Filmed Alloy 690 in Borated and Lithiated Water at 330 °C

Abstract: The purpose of this work is to quantify the effects of dissolved zinc cations on corrosion and release rates from a pre-filmed Alloy 690 steam generator tubing material that was subsequently exposed to water containing zinc. The corrosion tests were performed in circulating 2 ppm Li and 1000 ppm B water without and with 60 ppb zinc at 330 °C. Gravimetric analyses and oxide characterization revealed that the corrosion rates, release rates, and oxide thicknesses decreased by subsequent exposure of the pre-filmed… Show more

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Cited by 5 publications
(2 citation statements)
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“…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].…”
Section: Introductionmentioning
confidence: 99%
“…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].…”
Section: Introductionmentioning
confidence: 99%
“…The addition of nickel (Ni 2+ ) or zinc (Zn 2+ ) ions in circulating water is an effective measure to suppress 60 Co deposition in boiling water reactors (BWRs) [3]. The positive effect of Zn 2+ ions on corrosion reduction and prevention of radiation buildup on stainless steel and Alloy 690 have been reported [4][5][6][7]. Zn 2+ ions injection technique is applied in BWRs and pressurised water reactors (PWRs) [8].…”
Section: Introductionmentioning
confidence: 99%