Stress Corrosion Cracking of Alloy 600 in PWR Primary Water: Influence of Chromium, Hydrogen and Oxygen Diffusion

  1. Jeremy T. Busby,
  2. Gabriel Ilevbare and
  3. Peter L. Andresen
  1. C. Guerre1,
  2. P. Laghoutaris1,2,
  3. J. Chêne2,
  4. L. Marchetti1,
  5. R. Molins3,
  6. C. Duhamel3 and
  7. M. Sennour3

Published Online: 26 JUN 2012

DOI: 10.1002/9781118456835.ch154

15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors

15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors

How to Cite

Guerre, C., Laghoutaris, P., Chêne, J., Marchetti, L., Molins, R., Duhamel, C. and Sennour, M. (2012) Stress Corrosion Cracking of Alloy 600 in PWR Primary Water: Influence of Chromium, Hydrogen and Oxygen Diffusion, in 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (eds J. T. Busby, G. Ilevbare and P. L. Andresen), John Wiley & Sons, Inc., Hoboken, New Jersey, Canada. doi: 10.1002/9781118456835.ch154

Author Information

  1. 1

    CEA, DEN, DPC, SCCME, Laboratoire d'Etude de la Corrosion Aqueuse, F-91191 Gif-sur-Yvette, France

  2. 2

    CNRS/CEA UMR8587 LAMBE, Univ. D'Evry Val d'Essonne, 91025 Evry Cedex

  3. 3

    Mines Paristech, Centre des Matériaux, CNRS UMR 7633, BP 87, 91003 Evry Cedex, France

Publication History

  1. Published Online: 26 JUN 2012
  2. Published Print: 2 APR 2012

ISBN Information

Print ISBN: 9781118132418

Online ISBN: 9781118456835

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Keywords:

  • stress corrosion cracking;
  • alloy 600;
  • PWR primary water

Summary

This chapter contains sections titled:

  • Introduction

  • Material

  • Experimental Procedure

  • Results and Discussion

  • Conclusion

  • Acknowledgements