Development of radiation damage during in-situ Kr++ irradiation of Fe-Ni-Cr model austenitic steels

M. Desormeaux, B. Rouxel, A. T. Motta, M. Kirk, C. Bisor, Y. De Carlan, A. Legris

Research output: Contribution to journalArticlepeer-review

14 Scopus citations


In situ irradiations of 15Cr/15Ni-Ti and 15Cr/25Ni-Ti model austenitic steels were performed at the Intermediate Voltage Electron Microscope (IVEM)-Tandem user Facility (Argonne National Laboratory) at 600 °C using 1 MeV Kr++. The experiment was designed in the framework of cladding development for the GEN IV Sodium Fast Reactors (SFR). It is an extension of previous high dose irradiations on those model alloys at JANNuS-Saclay facility in France, aimed at investigating swelling mechanisms and microstructure evolution of these alloys under irradiation [1]. These studies showed a strong influence of Ni in decreasing swelling. In situ irradiations were used to continuously follow the microstructure evolution during irradiation using both diffraction contrast imaging and recording of diffraction patterns. Defect analysis, including defect size, density and nature, was performed to characterize the evolving microstructure and the swelling. Comparison of 15Cr/15Ni-Ti and 15Cr/25Ni-Ti irradiated microstructure has lent insight into the effect of nickel content in the development of radiation damage caused by heavy ion irradiation. The results are quantified and discussed in this paper.

Original languageEnglish (US)
Pages (from-to)156-167
Number of pages12
JournalJournal of Nuclear Materials
StatePublished - Jul 2016

All Science Journal Classification (ASJC) codes

  • Nuclear and High Energy Physics
  • General Materials Science
  • Nuclear Energy and Engineering


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