Crack Growth Behavior of Irradiated Type 316 SS in Low Dissolved Oxygen Environment

  1. Jeremy T. Busby,
  2. Gabriel Ilevbare and
  3. Peter L. Andresen
  1. Y. Chen1,
  2. B. Alexandreanu1,
  3. Y. Yang2,
  4. W. J. Shack1,
  5. K. Natesan1,
  6. E. E. Gruber1 and
  7. A. S. Rao3

Published Online: 26 JUN 2012

DOI: 10.1002/9781118456835.ch121

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

Chen, Y., Alexandreanu, B., Yang, Y., Shack, W. J., Natesan, K., Gruber, E. E. and Rao, A. S. (2012) Crack Growth Behavior of Irradiated Type 316 SS in Low Dissolved Oxygen Environment, 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.ch121

Author Information

  1. 1

    Nuclear Engineering Division, Argonne National Laboratory; 9700 South Cass Ave., Argonne, IL 60439, USA

  2. 2

    Nuclear and Radiological Engineering Department, University of Florida; 202 Nuclear Science Bldg., Gainesville, FL 32611, USA

  3. 3

    US Nuclear Regulatory Commission; Washington, DC 20555, USA

Publication History

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

ISBN Information

Print ISBN: 9781118132418

Online ISBN: 9781118456835

SEARCH

Keywords:

  • IASCC;
  • stainless steels;
  • BWR;
  • HWC;
  • crack growth rate

Summary

This chapter contains sections titled:

  • Abstract

  • Introduction

  • Experimental

  • Crack Growth Rate Test Results

  • Discussion

  • Conclusions

  • Acknowledgments