Stress corrosion crack initiation susceptibility of irradiated austenitic stainless steels

Kale J. Stephenson, Yugo Ashida, Jeremy T. Busby, Gary S. Was

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

3 Scopus citations

Abstract

The susceptibility of neutron irradiated austenitic stainless steels to the initiation of irradiation-assisted stress corrosion cracking (IASCC) was assessed. Solution annealed (SA), high purity (HP) type 304 stainless steel with and without additions of Mo and Si, and HP type 316L +Hf were strained by constant extension rate testing (CERT) in simulated 288°C BWR NWC at a rate of 3.5 × 10 -7/s. CERT test data and fracture analysis showed that IASCC susceptibility increased in order of HP304, HP304+Mo, HP316L+Hf, and HP304+Si. This trend was also observed when comparing fracture surfaces of the same alloys tested by CERT in BWR NWC after proton irradiation. Differences were insignificant among reported crack growth rate (CGR) values for the same neutron irradiated alloys, and no connection between crack initiation and CGR was confirmed from the alloys tested.

Original languageEnglish
Title of host publication15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011
Pages1126-1138
Number of pages13
StatePublished - 2011
Event15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011 - Colorado Springs, CO, United States
Duration: Aug 7 2011Aug 11 2011

Publication series

Name15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011
Volume2

Conference

Conference15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011
Country/TerritoryUnited States
CityColorado Springs, CO
Period08/7/1108/11/11

Keywords

  • BWR NWC
  • CERT
  • IASCC
  • Neutron irradiation
  • Stainless steel

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