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Mechanism for radiation damage resistance in yttrium oxide dispersion strengthened steels

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Original languageEnglish
Pages (from-to)291-297
Number of pages7
JournalJournal of Nuclear Materials
Volume445
Issue number1-3
Early online date9 Nov 2013
DOIs
StatePublished - 1 Feb 2014

Abstract

ODS steels based on yttrium oxide have been suggested as potential fusion reactor wall materials due to their observed radiation resistance properties. Presumably this radiation resistance can be related to the interaction of the particle with vacancies, self-interstitial atoms (SIAs) and other radiation damage debris. Density functional theory has been used to investigate this at the atomic scale. Four distinct interfaces, some based on HRTEM observations, between iron and yttrium oxide were investigated. It is been shown that the Y2O3-Fe interface acts as a strong trap with long-range attraction for both interstitial and vacancy defects, allowing recombination without altering the interface structure. The catalytic elimination of defects without change to the microstructure explains the improved behaviour of ODS steels with respect to radiation creep and swelling.

    Research areas

  • AUGMENTED-WAVE METHOD, IRRADIATION CREEP, ODS STEELS, AB-INITIO, MICROSTRUCTURAL DEVELOPMENT, FERRITIC STEELS, ALLOYS, IRON, POTENTIALS, PARTICLES

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