Understanding self ion damage in FCC Ni-Cr-Fe based alloy using X-ray diffraction techniques

R. Halder Banerjee*, P. Sengupta, A. Chatterjee, S. C. Mishra, A. Bhukta, P. V. Satyam, I. Samajdar, G. K. Dey

*Corresponding author for this work

Research output: Contribution to journalArticlepeer-review


Using X-ray diffraction line profile analysis (XRDLPA) approach the radiation response of FCC Ni-Cr-Fe based alloy 690 to 1.5 and 3 MeV Ni2+ ion damage was quantified in terms of its microstructural parameters. These microstructural parameters viz. average domain size, microstrain and dislocation density were found to vary anisotropically with fluence. The anisotropic behaviour is mainly attributable to presence of twins in pre-irradiated microstructure. After irradiation, surface roughness increases as a function of fluence attributable to change in surface and sub-surface morphology caused by displacement cascade, defects and sputtered atoms created by incident energetic ion. The radiation hardening in case of 1.5 MeV Ni2+ irradiated specimens too is a consequence of the increase in dislocation density formed by interaction of radiation induced defects with pre-existing dislocations. At highest fluence there is an initiation of saturation.

Original languageEnglish
Pages (from-to)82-93
Number of pages12
JournalJournal of Nuclear Materials
StatePublished - 1 Apr 2018
Externally publishedYes


  • Alloy 690
  • Nano-indentation
  • Radiation damage


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