SCC Properties of Modified Alloy 718 in BWR Plant

  1. Jeremy T. Busby,
  2. Gabriel Ilevbare and
  3. Peter L. Andresen
  1. Yoshinori Katayama1,
  2. Motoji Tsubota1,
  3. Yoshiaki Saito1,
  4. Norihiko Tanaka2 and
  5. Shigeaki Tanaka2

Published Online: 26 JUN 2012

DOI: 10.1002/9781118456835.ch80

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

Katayama, Y., Tsubota, M., Saito, Y., Tanaka, N. and Tanaka, S. (2012) SCC Properties of Modified Alloy 718 in BWR Plant, 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.ch80

Author Information

  1. 1

    Power and Industrial Systems R&D Center, Toshiba Corporation, Yokohama, Kanagawa, 230-0045, Japan

  2. 2

    Nuclear Division, Toshiba Corporation, Yokohama, Kanagawa, 235-8522, 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:

  • alloy 718;
  • alloy x-750;
  • stress corrosion cracking;
  • jet pump beam;
  • uni-axial constant load test;
  • fatigue test;
  • spring properties

Summary

This chapter contains sections titled:

  • Introduction

  • Experimental Procedure

  • Results and Discussions

  • Conclusions