Abstract

Silicon carbide (SiC) and SiC/SiC composites are important candidate materials for use in the nuclear industry. Coarse grain models are the only tools capable of modelling defect accumulation under different irradiation conditions at a realistic time and length scale. The core of any such model is the so-called “source term”, which is described by the primary damage. In the present work, classical molecular dynamics (MD), binary collision approximation (BCA) and NRT model are applied to describe collision cascades in 3C-SiC with primary knock-on atom (PKA) energy in the range 1–100 keV. As such, BCA and NRT are benchmarked against MD. Particular care was taken to account for electronic stopping and the use of a threshold displacement energy consistent with density functional theory and experiment. Models and regressions are developed to characterize the primary damage in terms of number of stable Frenkel pairs and their cluster size distribution, anti-sites, and defect type. As such, an accurate cascade database is developed with simple descriptors. One of the main results shows that the defect cluster size distribution follows the geometric distribution rather than a power law.

Highlights

  • Silicon carbide (SiC) and SiC/SiC composites are important candidate materials for use in the nuclear industry

  • A critical temperature, swelling is primarily caused by amorphization of the SiC material as strain accumulates from irradiation‐ induced defects from either ion- or neutron irradiation[5,6,7,8]

  • binary collision approximation (BCA) and NRT are benchmarked against molecular dynamics (MD)

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Summary

Introduction

Silicon carbide (SiC) and SiC/SiC composites are important candidate materials for use in the nuclear industry. Models and regressions are developed to characterize the primary damage in terms of number of stable Frenkel pairs and their cluster size distribution, anti-sites, and defect type. Silicon carbide (SiC) and SiC/SiC composites are candidate materials for use in fission and fusion applications. Depending on the irradiation conditions, point-defects accumulate into defect clusters that may provoke macroscopic swelling and amorphization of the material[2]. Snead and Katoh[4] developed a comprehensive map of the evolution of microstructural features in SiC under irradiation (both ion and neutron) with dose and irradiation temperature. A critical temperature (about 150 °C), swelling is primarily caused by amorphization of the SiC material as strain accumulates from irradiation‐ induced defects from either ion- or neutron irradiation[5,6,7,8]. In the intermediate temperature regime, above the critical amorphization temperature (about 200 °C) and up to the vacancy mobility temperature (about 1000 °C), the swelling of SiC under neutron irradiation appears to saturate with irradiation dose and decreases with irradiation temperature[4]

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