A Preliminary Hybrid Model of Irradiation-Assisted Stress Corrosion Cracking of 300 Series Stainless Steels in PWR Primary Environments

  1. Jeremy T. Busby,
  2. Gabriel Ilevbare and
  3. Peter L. Andresen
  1. E. D. Eason1,
  2. G. Ilevbare2 and
  3. R. Pathania2

Published Online: 26 JUN 2012

DOI: 10.1002/9781118456835.ch136

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

Eason, E. D., Ilevbare, G. and Pathania, R. (2012) A Preliminary Hybrid Model of Irradiation-Assisted Stress Corrosion Cracking of 300 Series Stainless Steels in PWR Primary Environments, 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.ch136

Author Information

  1. 1

    Modeling & Computing Services, LLC P.O. Box 18583, Boulder CO 80308

  2. 2

    EPRI, Inc. P.O. Box 10412, Palo Alto CA 94303

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:

  • IASCC;
  • PWR;
  • primary water;
  • hybrid;
  • model;
  • stainless steel;
  • strain rate

Summary

This chapter contains sections titled:

  • Introduction

  • Database

  • Hybrid IASCC Model

  • Discussion

  • Conclusions

  • Acknowledgments