Irradiation-induced formation of G-phase precipitates and M2X carbides in self-ion irradiated HT-9

Ferritic-martensitic steels with high chromium content are a promising material group for advanced nuclear systems due to their high temperature strength and good irradiation tolerance. HT-9 is an optimized and often-studied alloy in this group, but additional studies are required on its radiation response under extreme conditions to be experienced in various types of nuclear reactors, especially with respect to phase stability under irradiation. Self-ion irradiation of HT-9 by 5 MeV Fe ions was used to simulate neutron-induced behavior reaching peak doses of 100 and 300 dpa at temperatures ranging from 450 to 550 degrees C. M23C6 carbides that existed prior to irradiation were found to remain stable under all examined irradiation conditions. As irradiation progressed at 450 and 500 degrees C, however, formation of spherical-like G-phase precipitates and needle-like M2X carbides was observed. Gphase precipitates were found to be enriched in Ni, Si, and Mn, and show no interface segregation, whereas needle-like M2X carbides were rich in Cr and Mo and clearly displayed interface segregation of Ni and Si. M2X carbide formation is believed to be assisted by vacancies, while G-phase precipitation is thought to be assisted by interstitials. This difference in defect-mediated formation leads to a difference in distribution with depth. M2X carbides are distributed over shallower depths than that of G-phase precipitates, consistent with defect imbalance predictions that consider the influence of the injected interstitial effect.