Abstract

As one candidate alloy for future Generation IV and fusion reactors, a dual-phase 12Cr oxide-dispersion-strengthened (ODS) alloy was developed for high temperature strength and creep resistance and has shown good void swelling resistance under high damage self-ion irradiation at high temperature. However, the effect of helium and its combination with radiation damage on oxide dispersoid stability needs to be investigated. In this study, 120 keV energy helium was preloaded into specimens at doses of 1 × 1015 and 1 × 1016 ions/cm2 at room temperature, and 3.5 MeV Fe self-ions were sequentially implanted to reach 100 peak displacement-per-atom at 475 °C. He implantation alone in the control sample did not affect the dispersoid morphology. After Fe ion irradiation, a dramatic increase in density of coherent oxide dispersoids was observed at low He dose, but no such increase was observed at high He dose. The study suggests that helium bubbles act as sinks for nucleation of coherent oxide dispersoids, but dispersoid growth may become difficult if too many sinks are introduced, suggesting that a critical mass of trapping is required for stable dispersoid growth.

Highlights

  • Oxide-dispersion-strengthened (ODS) alloys are one class of promising candidate alloys for GenIV and fusion reactors due to their superior high temperature strength and creep resistance [1,2,3,4,5,6,7].Among various ODS alloys developed worldwide, a dual-phase ferritic/martensitic (F/M) 12Cr ODS alloy has shown good high-temperature oxidation resistance and corrosion resistance [3]

  • A previous study on the same alloy using the same irradiation condition employed in this study showed that the dispersoid density increased in both ferrite and tempered martensite (TM) phases due to ballistic dissolution by irradiation and thermodynamic homogenous

  • transmission electron microscope (TEM) images were taken from the 350 nm depth region where the He ion peak is located to see the were taken fromdispersoid the 350 nm depth region where

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Summary

Introduction

Oxide-dispersion-strengthened (ODS) alloys are one class of promising candidate alloys for Gen. Among various ODS alloys developed worldwide, a dual-phase ferritic/martensitic (F/M) 12Cr ODS alloy has shown good high-temperature oxidation resistance and corrosion resistance [3]. Recent studies have shown good grain stability at 800 displacement-per-atom (dpa) after 600 ◦ C self-ion irradiation, and good swelling resistance (less than 2% and 0.06% at 475 ◦ C for the ferrite and TM phases, respectively) [8,9]. These studies show that oxide dispersoid size changes saturate with increasing dose. Thereby TM phase-dominated ODS alloys are very attractive to further improve swelling resistance

Materials and Experimental Procedure
He Implantation Only
Timeasured
Fe Irradiation Only
He Implantation Followed by Fe Irradiation
Oxide Dispersoid Size and Density Comparison
Summary
Discussion
Conclusions
Methods
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