Abstract

It is known that grain boundaries (GBs) provide sinks for defects induced into a solid by irradiation. At the same time radiation can change the atomic structure and chemistry of GBs, which in turn impacts the ability of GBs to continue absorbing defects. Although a number of studies have been reported for tilt GBs acting as defect sinks, the questions of how twist GBs evolve to absorb non-equilibrium concentrations of defects and whether GBs saturate as defect sinks for typical irradiation conditions have remained largely unanswered. Here, we used a combination of molecular dynamics and grand canonical Monte Carlo simulations to determine how twist GBs accommodate point defects. We used SiC and {001} and {111} twist GBs as model systems. We found that diffusion of defects along GBs in this material is slow and for most experimentally relevant conditions point defects will accumulate at twist GBs, driving structural and chemical evolution of these interfaces. During irradiation, screw dislocations within GB planes absorb interstitials by developing mixed dislocation segments that climb. Formation of mixed dislocations occurs either by nucleation of interstitial loops or by faulting/unfaulting of stacking faults. Both types of twist GBs can accommodate a high density of interstitials without losing the crystalline structure, irrespectively of the interstitial flux.

Highlights

  • It is known that grain boundaries (GBs) provide sinks for defects induced into a solid by irradiation

  • In the calculations of segregation energy, the interstitial is placed at different sites in the GB, followed by a 50 ps molecular dynamics (MD) simulation in NVT ensemble at 500 K to relax the structure and a fast quenching to bring the system to a local energy minimum

  • We found that interstitial intersections play an important role in determining interstitial kinetics and in accommodating interstitials in twist GBs

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Summary

Introduction

It is known that grain boundaries (GBs) provide sinks for defects induced into a solid by irradiation. We perform a similar analysis of tseg, tmigr, and tsink to that conducted for {001} twist GBs in order to investigate defect accumulation in {111} twist GBs. First, the time interval tseg between the arrivals of two successive interstitials from grain interior to the GB is calculated based on the interstitial flux as predicted by ab initio based rate theory model[32].

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