SCC Crack Growth Rate of Alloy 82 in PWR Primary Water Conditions - Effect of a Thermal Treatment -

  1. Jeremy T. Busby,
  2. Gabriel Ilevbare and
  3. Peter L. Andresen
  1. C. Guerre1,
  2. C. Duhamel2,
  3. M. Sennour2,
  4. J. Crépin2 and
  5. M. Le Calvar3

Published Online: 26 JUN 2012

DOI: 10.1002/9781118456835.ch116

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., Duhamel, C., Sennour, M., Crépin, J. and Le Calvar, M. (2012) SCC Crack Growth Rate of Alloy 82 in PWR Primary Water Conditions - Effect of a Thermal Treatment -, 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.ch116

Author Information

  1. 1

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

  2. 2

    Mines Paritech, Centre des matériaux (CNRS UMR 7633). BP 87, 91003 Evry Cedex, France

  3. 3

    Institute for Radiological Protection and Nuclear Safety (IRSN), DSR/SAMS, BP 17, 92262 Fontenay-aux-Roses 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 82;
  • PWR primary water

Summary

This chapter contains sections titled:

  • Introduction

  • Operating Experience

  • Experimental

  • Microstructural Charaterization: Effect of the Thermal Treatment

  • Results and Discussion

  • Conclusion