Evaluation of the Susceptibility to SCC Initiation of Alloy 690 in Simulated PWR Primary Water

  1. Jeremy T. Busby,
  2. Gabriel Ilevbare and
  3. Peter L. Andresen
  1. Kazuya Tsutsumi1,2 and
  2. Thierry Couvant1

Published Online: 26 JUN 2012

DOI: 10.1002/9781118456835.ch6

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

Tsutsumi, K. and Couvant, T. (2012) Evaluation of the Susceptibility to SCC Initiation of Alloy 690 in Simulated PWR Primary Water, 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.ch6

Author Information

  1. 1

    EDF R&D MAI, Site des Renardières, Moret-sur-Loing, Cedex, 77818, FRANCE

  2. 2

    Mitsubishi Heavy Industries, Ltd., 1-1-1, Wadasaki-cho, Hyogo-ku, Kobe, 6528585, JAPAN

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:

  • alloy690;
  • stress corrosion cracking;
  • initiation;
  • ageing;
  • cold rolling

Summary

This chapter contains sections titled:

  • Abstract

  • Introduction

  • Fundamental Characteristics of Materials

  • SCC Testing

  • Results and Discussion

  • Conclusion