TY - GEN
T1 - Crevice corrosion control for stainless steel using radiation-induced surface activation
AU - Kato, Taichi
AU - Hazuku, Tatsuya
AU - Motoda, Shin Ichi
AU - Takamasa, Tomoji
AU - Hishida, Mamoru
AU - Kumata, Takanori
AU - Abe, Hiroaki
AU - Furuya, Masahiro
PY - 2009/1/1
Y1 - 2009/1/1
N2 - When a semiconductor film is irradiated by γ-rays, excited electrons are transferred to a base metal in contact with the film, resulting in cathodic-anodic reactions and surface activation of the metal oxide film. The authors first produced radiation-induced surface activation (RISA) in 2000 and have used it in the development of a new corrosion protection method. This report describes a corrosion mitigation technique based on RISA to prevent crevice corrosion in stainless steel, using low-intensity radiation. Experimental results show that an electrode potential of -100 mV vs. Ag/AgCl was produced and maintained on TiO2-coated SUS304 stainless steel specimens immersed in artificial seawater and in close contact with a small, sealed 60Co source (external irradiation) or activated by neutron irradiation to become self-exciting, with no corrosion observed for more than 7 days. In contrast, the potential of a specimen without a radiation source decreased to less than -280 mV vs. Ag/AgCl and crevice corrosion occurred beneath the O-ring within a few days. The corrosion control mechanism was explored by measurement of dissolved oxygen and iron ions in the solution.
AB - When a semiconductor film is irradiated by γ-rays, excited electrons are transferred to a base metal in contact with the film, resulting in cathodic-anodic reactions and surface activation of the metal oxide film. The authors first produced radiation-induced surface activation (RISA) in 2000 and have used it in the development of a new corrosion protection method. This report describes a corrosion mitigation technique based on RISA to prevent crevice corrosion in stainless steel, using low-intensity radiation. Experimental results show that an electrode potential of -100 mV vs. Ag/AgCl was produced and maintained on TiO2-coated SUS304 stainless steel specimens immersed in artificial seawater and in close contact with a small, sealed 60Co source (external irradiation) or activated by neutron irradiation to become self-exciting, with no corrosion observed for more than 7 days. In contrast, the potential of a specimen without a radiation source decreased to less than -280 mV vs. Ag/AgCl and crevice corrosion occurred beneath the O-ring within a few days. The corrosion control mechanism was explored by measurement of dissolved oxygen and iron ions in the solution.
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M3 - Conference contribution
AN - SCOPUS:84907931005
T3 - International Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009
SP - 2088
EP - 2094
BT - International Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009
PB - Atomic Energy Society of Japan
T2 - International Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009
Y2 - 10 May 2009 through 14 May 2009
ER -