Study on corrosion control in reactors using Radiation Induced Surface Activation (RISA) - Mechanism behind stainless steel durability due to RISA against crevice corrosion

Shogo Mabuchi*, Tatsuya Hazuku, Shin Ichi Motoda, Tomoji Takamasa, Susumu Uematsu, Masahiro Furuya

*Corresponding author for this work

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Abstract

This study examines a corrosion control technique for corrosion-resistant materials or of stainless steel in piping for nuclear reactors. This employs an effect of Radiation Induced Surface Activation (RISA). The experimental results revealed: (1) The mechanism behind the corrosion control proposed by the previous report was confirmed to be appropriate. This via tests that measured the amount of dissolved oxygen and iron ions, in the solution. (2) The corrosion control technique was confirmed to be useful for stainless steel with any kind of metal oxide film coating on the surface. (3) It was also shown to be useful even in actual seawater, due to biological effects, which is a far more severe environment for corrosion control than simple salt water. The corrosion control technique for corrosion-resistant material using RISA in seawater has therefore been shown to offer a significant potential for practical applications in naval architecture and marine structures.

Original languageEnglish
Title of host publication18th International Conference on Nuclear Engineering, ICONE18
DOIs
Publication statusPublished - 2010
Externally publishedYes
Event18th International Conference on Nuclear Engineering, ICONE18 - Xi'an, China
Duration: 2010 May 172010 May 21

Publication series

NameInternational Conference on Nuclear Engineering, Proceedings, ICONE
Volume2

Conference

Conference18th International Conference on Nuclear Engineering, ICONE18
Country/TerritoryChina
CityXi'an
Period10/5/1710/5/21

ASJC Scopus subject areas

  • Nuclear Energy and Engineering

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