Microstructural effects on stress corrosion initiation in austenitic stainless steel in PWR environments

D. R. Tice, V. Addepalli, K. J. Mottershead, M. G. Burke, F. Scenini, S. Lozano-Perez, G. Pimentel

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

1 Scopus citations

Abstract

Although service experience of austenitic stainless steels exposed to PWR primary coolant has been good, stress corrosion crack propagation has been observed in laboratory tests in the presence of ≥15% cold work. Data on crack initiation are much more limited and this study therefore aims to improve the understanding of the conditions under which crack initiation and subsequent development of stress corrosion cracking might be possible. Testing was performed on two heats of Type 304/304L stainless steel under slow strain rate tensile loading. A range of analytical techniques were used to characterize the resultant precursor features and cracking, and digital image correlation before and after testing was also used to evaluate the influence of localized deformation on SCC. The results indicate that crack initiation can occur in austenitic stainless steels exposed to good quality primary coolant under dynamic straining conditions; additional testing underway under more plant-representative conditions will be reported later. Significant influences of steel microstructure on crack initiation susceptibility were observed.

Original languageEnglish
Title of host publicationProceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors
EditorsDenise Paraventi, Michael Wright, John H. Jackson
PublisherSpringer International Publishing
Pages775-792
Number of pages18
ISBN (Print)9783319672434
DOIs
StatePublished - 2018
Externally publishedYes
Event18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, 2017 - Portland, United States
Duration: Aug 13 2017Aug 17 2017

Publication series

NameMinerals, Metals and Materials Series
VolumePart F9
ISSN (Print)2367-1181
ISSN (Electronic)2367-1696

Conference

Conference18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, 2017
Country/TerritoryUnited States
CityPortland
Period08/13/1708/17/17

Keywords

  • Crack growth
  • Initiation
  • LWR
  • PWR
  • SCC
  • Stainless steel
  • Stress corrosion cracking

Fingerprint

Dive into the research topics of 'Microstructural effects on stress corrosion initiation in austenitic stainless steel in PWR environments'. Together they form a unique fingerprint.

Cite this