The role of Ti and TiC nanoprecipitates in radiation resistant austenitic steel: A nanoscale study

  • Niels Cautaerts*
  • , Rémi Delville
  • , Erich Stergar
  • , Janne Pakarinen
  • , Marc Verwerft
  • , Yong Yang
  • , Christina Hofer
  • , Ronald Schnitzer
  • , Steffen Lamm
  • , Peter Felfer
  • , Dominique Schryvers
  • *Corresponding author for this work

Research output: Contribution to journalArticleScientificpeer-review

21 Citations (Scopus)

Abstract

This work encompasses an in-depth transmission electron microscopy and atom probe tomography study of Ti-stabilized austenitic steel irradiated with Fe-ions. The focus is on radiation induced segregation and precipitation, and in particular on how Ti and TiC affect these processes. A 15-15Ti steel (grade: DIN 1.4970) in two thermo-mechanical states (cold-worked and aged) was irradiated at different temperatures up to a dose of 40 dpa. At low irradiation temperatures, the cold-worked and aged materials evolved to a similar microstructure dominated by small Si and Ni clusters, corresponding to segregation to small point defect clusters. TiC precipitates, initially present in the aged material, were found to be unstable under these irradiation conditions. Elevated irradiation temperatures resulted in the nucleation of nanometer sized Cr enriched TiC precipitates surrounded by Si and Ni enriched shells. In addition, nanometer sized Ti- and Mn-enriched G-phase (M6Ni16Si7) precipitates formed, often attached to TiC precipitates. Post irradiation, larger number densities of TiC were observed in the cold-worked material compared to the aged material. This was correlated with a lower volume fraction of G-phase. The findings suggest that at elevated irradiation temperatures, the precipitate-matrix interface is an important point defect sink and contributes to the improved radiation resistance of this material. The study is a first of its kind on stabilized steel and demonstrates the significance of the small Ti addition to the evolution of the microstructure under irradiation.

Original languageEnglish
Pages (from-to)184-197
Number of pages14
JournalActa Materialia
Volume197
DOIs
Publication statusPublished - 15 Sept 2020
MoE publication typeA1 Journal article-refereed

Funding

This work was supported by ENGIE [contract number 2015-AC-007 e BSUEZ6900]; the U.S. Department of Energy, Office of Nuclear Energy under DOE Idaho Operations Office Contract DE-AC07-051D14517 as part of a Nuclear Science User Facilities experiment; and by the MYRRHA program at SCK-CEN, Belgium. Funding of the Austrian BMK (846933) in the framework of the program ”Production of the future” and the ”BMK Professorship for Industry” is gratefully acknowledged. We want to thank the staff at MIBL for assisting with the ion irradiations as well as the staff at CAES for assisting with FIB work and conducting APT measurements.

Keywords

  • APT
  • Austenitic steel
  • G-phase
  • Precipitation
  • Radiation induced segregation
  • TEM
  • TiC

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