Austenitic stainless steels suffer intergranular attack in boiling nitric acid with oxidants. The intergranular corrosion is mainly caused by the segregation of impurities to grain. An extra high purity austenitic stainless steel (EHP alloys) was developed with conducting the new multiple refined melting technique in order to suppress the total harmful impurities less than 100ppm. The basically corrosion behavior of type 310 EHP alloy with respect to nitric acid solution with highly oxidizing ions was investigated. The straining, aging and recrystallizing (SAR) treated type 310 EHP alloy showed superior corrosion resistance for intergranular attack. The segregated boron along the grain boundaries was one of main factor of intergranular corrosion from fission track etching results. The SAR treatment was effective to restrain the intergranular attack for type 310 EHP alloy with B less than 7ppm.
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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
Susceptibility of Intergranular Corrosion for Extra High Purity Austenitic Stainless Steel in Nitric Acid Available to Purchase
Ikuo Ioka,
Ikuo Ioka
Japan Atomic Energy Agency, Tokai, Ibaraki, Japan
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Chiaki Kato,
Chiaki Kato
Japan Atomic Energy Agency, Tokai, Ibaraki, Japan
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Kiyoshi Kiuchi,
Kiyoshi Kiuchi
Japan Atomic Energy Agency, Tokai, Ibaraki, Japan
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Junpei Nakayama
Junpei Nakayama
Kobe Steel, Ltd., Kobe, Hyogo, Japan
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Ikuo Ioka
Japan Atomic Energy Agency, Tokai, Ibaraki, Japan
Chiaki Kato
Japan Atomic Energy Agency, Tokai, Ibaraki, Japan
Kiyoshi Kiuchi
Japan Atomic Energy Agency, Tokai, Ibaraki, Japan
Junpei Nakayama
Kobe Steel, Ltd., Kobe, Hyogo, Japan
Paper No:
ICONE16-48776, pp. 703-707; 5 pages
Published Online:
June 24, 2009
Citation
Ioka, I, Kato, C, Kiuchi, K, & Nakayama, J. "Susceptibility of Intergranular Corrosion for Extra High Purity Austenitic Stainless Steel in Nitric Acid." 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. 703-707. ASME. https://doi.org/10.1115/ICONE16-48776
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