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How irradiation promotes intergranular stress corrosion crack initiation

  • G. S. Was
  • , C. B. Bahn
  • , J. Busby
  • , B. Cui
  • , D. Farkas
  • , M. Gussev
  • , M. Rigen He
  • , J. Hesterberg
  • , Z. Jiao
  • , D. Johnson
  • , W. Kuang
  • , M. McMurtrey
  • , I. Robertson
  • , A. Sinjlawi
  • , M. Song
  • , K. Stephenson
  • , K. Sun
  • , S. Swaminathan
  • , M. Wang
  • , E. West
  • University of Michigan, Ann Arbor
  • Pusan National University
  • Oak Ridge National Laboratory
  • University of Nebraska-Lincoln
  • Virginia Polytechnic Institute and State University
  • Johns Hopkins University
  • United States Department of Energy
  • Idaho National Laboratory
  • University of Wisconsin-Madison
  • Shanghai Jiao Tong University
  • PLLC
  • Federal Institute for Materials Research and Testing Berlin
  • Studsvik Medical

科研成果: 期刊稿件文献综述同行评审

35 引用 (Scopus)

摘要

Irradiation assisted stress corrosion cracking (IASCC) is a form of intergranular stress corrosion cracking that occurs in irradiated austenitic alloys. It requires an irradiated microstructure along with high temperature water and stress. The process is ubiquitous in that it occurs in a wide range of austenitic alloys and water chemistries, but only when the alloy is irradiated. Despite evidence of this degradation mode that dates back to the 1960s, the mechanism by which it occurs has remained elusive. Here, using high resolution electron backscattering detection to analyze local stress-strain states, high resolution transmission electron microscopy to identify grain boundary phases at crack tips, and decoupling the roles of stress and grain boundary oxidation, we are able to unfold the complexities of the phenomenon to reveal the mechanism by which IASCC occurs. The significance of the findings impacts the mechanical integrity of core components of both current and advanced nuclear reactor designs worldwide.

源语言英语
文章编号101255
期刊Progress in Materials Science
143
DOI
出版状态已出版 - 6月 2024

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