Effect of microstructure and neutron irradiation defects on deuterium retention in SiC

Leide, Alex; Zhong, Weicheng; Fernandez-Victorio, Isabel; Nguyen-Manh, Duc; Koyanagi, Takaaki

doi:10.3389/fnuen.2025.1534820

Title: Effect of microstructure and neutron irradiation defects on deuterium retention in SiC

Journal Article · Mon Feb 10 00:00:00 UTC 2025 · Frontiers in Nuclear Engineering

DOI: https://doi.org/10.3389/fnuen.2025.1534820 · OSTI ID:2513929

Leide, Alex ^[1];

^[2]; Fernandez-Victorio, Isabel ^[3]; Nguyen-Manh, Duc ^[3];

^[2]

United Kingdom Atomic Energy Authority (UKAEA), Abingdon (United Kingdom)
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
United Kingdom Atomic Energy Authority (UKAEA), Abingdon (United Kingdom); Univ. of Oxford (United Kingdom)

Retention of hydrogen isotopes is a critical concern for operating fusion reactors as retained tritium both activates components and removes scarce fuel from the fuel cycle. Radiation-induced displacement damage in SiC influences the retention of hydrogen isotopes compared to pristine SiC. Deuterium retention in neutron irradiated high purity SiC has been compared to different microstructures of non-irradiated high purity SiC using thermal desorption spectroscopy after gas charging and low energy ion implantation. Experimental results show lower deuterium retention in single crystal SiC than in polycrystal SiC indicating that grain boundaries are key trapping features in unirradiated SiC. Deuterium is released at lower temperatures in neutron irradiated polycrystal SiC compared to pristine polycrystal SiC, suggesting weaker trapping by radiation-induced defects compared to grain boundary trapping sites in the pristine materials. Low energy ion implantation caused a high deuterium release temperature, highlighting the sensitivity of deuterium release behaviour to radiation defect characteristics. First principles calculations have been conducted to identify energetically favourable trapping sites in SiC at the H_ABcV_Si and H_TSiV_C complexes, and migration barriers between interstitial sites. This helps interpret experimental results and derive effective diffusivity of hydrogen isotopes in SiC in the presence of vacancies.

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Research Organization:: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Sponsoring Organization:: USDOE; USDOE Office of Science (SC), Basic Energy Sciences (BES). Scientific User Facilities (SUF); USDOE Office of Science (SC), Fusion Energy Sciences (FES)

Grant/Contract Number:: AC05-00OR22725

OSTI ID:: 2513929

Journal Information:: Frontiers in Nuclear Engineering, Journal Name: Frontiers in Nuclear Engineering Vol. 4; ISSN 2813-3412

Publisher:: Frontiers Media S.A.Copyright Statement

Country of Publication:: United States

Language:: English

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36 MATERIALS SCIENCE
density function theory (DFT)
hydrogen isotope retention
neutron radiation damage
silicon carbide
thermal desorption spectroscopy (TDS)

Title: Effect of microstructure and neutron irradiation defects on deuterium retention in SiC

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