Carbon steel is considered in Japan the candidate material for overpacks in high-level radioactive waste disposal. Effects of bicarbonate solutions on the corrosion behavior and corrosion products of carbon steel were investigated by electrochemical measurements, FT-IR and XRD analyses. The anodic polarization measurements showed that bicarbonate ions (HCO3−) accelerated the anodic dissolution and the outer layer film formation of carbon steel in the case of high concentrations, on the other hand, it inhibited these processes in the case of low concentrations. The FT-IR and XRD analyses of the anodized film showed that siderite (FeCO3) was formed in 0.5 to 1.0mol/L bicarbonate solution, and Fe2(OH)2CO3 in 0.1 to 0.2mol/L bicarbonate solution, while Fe6(OH)12CO3 was formed in 0.02 to 0.05mol/L bicarbonate solutions. The stability of these corrosion products was able to be explained by using the actual potential – pH diagrams for the Fe-H2O-CO2 system.
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16th International Conference on Nuclear Engineering
May 11–15, 2008
Orlando, Florida, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-4814-0
PROCEEDINGS PAPER
Corrosion Behavior of Carbon Steel for the Overpack in the Groundwater Containing Bicarbonate Ions Available to Purchase
Toshiyasu Nishimura,
Toshiyasu Nishimura
National Institute for Materials Science, Tsukuba, Ibaraki, Japan
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Junpha Dong
Junpha Dong
National Institute for Materials Science, Tsukuba, Ibaraki, Japan
Search for other works by this author on:
Toshiyasu Nishimura
National Institute for Materials Science, Tsukuba, Ibaraki, Japan
Junpha Dong
National Institute for Materials Science, Tsukuba, Ibaraki, Japan
Paper No:
ICONE16-48081, pp. 443-448; 6 pages
Published Online:
June 24, 2009
Citation
Nishimura, T, & Dong, J. "Corrosion Behavior of Carbon Steel for the Overpack in the Groundwater Containing Bicarbonate Ions." Proceedings of the 16th International Conference on Nuclear Engineering. Volume 1: Plant Operations, Maintenance, Installations and Life Cycle; Component Reliability and Materials Issues; Advanced Applications of Nuclear Technology; Codes, Standards, Licensing and Regulatory Issues. Orlando, Florida, USA. May 11–15, 2008. pp. 443-448. ASME. https://doi.org/10.1115/ICONE16-48081
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