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Structural characterization of nanoscale intermetallic precipitates in highly neutron irradiated reactor pressure vessel steels

  • D. J. Sprouster
  • , J. Sinsheimer
  • , E. Dooryhee
  • , S. K. Ghose
  • , P. Wells
  • , T. Stan
  • , N. Almirall
  • , G. R. Odette
  • , L. E. Ecker
  • Brookhaven National Laboratory
  • University of California at Santa Barbara

Research output: Contribution to journalArticlepeer-review

77 Scopus citations

Abstract

Massive, thick-walled pressure vessels are permanent nuclear reactor structures that are exposed to a damaging flux of neutrons from the adjacent core. The neutrons cause embrittlement of the vessel steel that grows with dose (fluence), as manifested by an increasing ductile-to-brittle fracture transition temperature. Extending reactor life requires demonstrating that large safety margins against brittle fracture are maintained at the higher neutron fluence associated with beyond 60 years of service. Here synchrotron-based x-ray diffraction and small angle x-ray scattering measurements are used to characterize highly embrittling nm-scale Mn-Ni-Si precipitates that develop in the irradiated steels at high fluence. These precipitates lead to severe embrittlement that is not accounted for in current regulatory models. Application of the complementary techniques has, for the very first time, successfully identified the crystal structures of the nanoprecipitates, while also yielding self-consistent compositions, volume fractions and size distributions.

Original languageEnglish
Pages (from-to)18-22
Number of pages5
JournalScripta Materialia
Volume113
DOIs
StatePublished - 2016

Keywords

  • Irradiation embrittlement
  • Precipitation
  • Reactor pressure vessels
  • Small angle x-ray scattering
  • X-ray diffraction

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