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Irradiation Assisted Stress Corrosion Cracking Susceptibility of Alloy X-750 Exposed to BWR Environments

  • S. TeysseyreEmail author
  • J. H. Jackson
  • P. L. Andresen
  • P. Chou
  • B. Carter
Conference paper
Part of the The Minerals, Metals & Materials Series book series (MMMS)

Abstract

The effect of irradiation on stress corrosion cracking susceptibility and fracture toughness of alloy X-750 has been investigated. The material has been irradiated at a target temperature of 288 ℃ in the Advanced Test Reactor at Idaho National Laboratory to a fluence of approximately 1.93 × 1020 n/cm2 (E >1 meV). Stress corrosion cracking crack growth rates were determined in both unirradiated and irradiated materials in normal water chemistry and hydrogen water chemistry environments. Although the effect of irradiation on tensile properties and fracture toughness was observed, there was no significant effect of irradiation observed on the propagation rate of stress corrosion cracks.

Notes

Acknowledgements

This work was supported under a Cooperative Research and Development Agreement between the Idaho National Laboratory (under the Nuclear Science User Facilities) and the Electric Power Research Institute.

References

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Copyright information

© The Minerals, Metals & Materials Society 2019

Authors and Affiliations

  • S. Teysseyre
    • 1
    Email author
  • J. H. Jackson
    • 1
  • P. L. Andresen
    • 2
  • P. Chou
    • 3
  • B. Carter
    • 3
  1. 1.Idaho National LaboratoryIdaho FallsUSA
  2. 2.GE Global Research Center New YorkUSA
  3. 3.Electric Power Research InstitutePalo AltoUSA

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