Corrosion Science and Technology

The Corrosion Science Society of Korea (한국부식방식학회)
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Irradiation Assisted Stress Corrosion Cracking of Austenitic Stainless Steels in Water Reactors

  • Yonezawa, Toshio (Fracture and Reliability Research Institute, Tohoku University)
  • Published : 2008.04.01
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Abstract

Based upon the good compatibility to neutron irradiation and high temperature water environment, austenitic stainless steels are widely used for core internal structural materials of light water reactors. But, recently, intergranular cracking was detected in the stainless steels for the core applications in some commercial PWR plants. Authors studied on the root cause of the intergranular cracking and developed the countermeasure including the alternative materials for these core applications. The intergranular cracking in these core applications are defined as an irradiation assisted mechanical cracking and irradiation assisted stress corrosion cracking. In this paper, the root cause of the intergranular cracking and its countermeasure are summarized and discussed.

Keywords

References

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