Developing PWR Aging-Management Strategies for Reactor Vessel Internals

  1. Jeremy T. Busby,
  2. Gabriel Ilevbare and
  3. Peter L. Andresen
  1. S.B. Davidsaver,
  2. S. Fyfitch and
  3. H. Xu

Published Online: 26 JUN 2012

DOI: 10.1002/9781118456835.ch183

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

Davidsaver, S.B., Fyfitch, S. and Xu, H. (2012) Developing PWR Aging-Management Strategies for Reactor Vessel Internals, 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.ch183

Author Information

  1. AREVA NP Inc., P.O. Box 10935, Lynchburg, VA 24506-0935

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:

  • alloy 600;
  • stress corrosion cracking;
  • polychromatic x-ray microdiffraction;
  • dislocations;
  • residual strain

Summary

This chapter contains sections titled:

  • Introduction and Background

  • B&W-Designed RV Internals

  • B&W Owners Group and Industry Programs

  • Material Age-Related Degradation Mechanism Evaluations

  • B&W Design Assessments and Evaluations

  • Summary and Conclusions