DOE OSTI · 3002692
Be₂C as a neutron moderator for molten salt reactors: A first-principles study of structural, electronic, and defect properties
Abstract
Beryllium carbide (Be 2 C), valued for its high neutron moderation efficiency and low absorption cross section, is a promising high-temperature neutron moderator for molten salt reactors. Its practical adoption, however, demands significant technological maturation, requiring comprehensive theoretical and experimental studies of its response to different conditions, including high temperature and irradiation. Here, we report initial results on the fundamental properties and radiation-induced defects of Be 2 C, focusing on antisites, vacancies, interstitial atoms, and Frenkel pairs in the Be and C sublattices. Using density functional theory (DFT) and ab initio molecular dynamics (AIMD), we calculate the defects formation and binding energies, evaluating their dependence on the supercell size, charge states, and chemical environment. In general, carbon defects exhibit higher formation energies, greater sensitivity to cell size, and stronger impacts on the density of states compared to beryllium defects, with charged state the effects being more pronounced. Static DFT reveals multiple metastable interstitial configurations, while AIMD identifies ground states as C-C <100> dumbbells and octahedral Be interstitials. In conclusion, the diversity of metastable configurations and defect states complicates the diffusion mechanisms, requiring further molecular dynamics analysis to elucidate the mechanisms and rates of radiation-induced atomic transport, as well as the structural stability of Be2C.
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Osetskiy, Yuri [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States). Materials Science & Technology Division] (ORCID:0000000281090030), Du, Mao-Hua [NAGA, Knoxville, TN (United States)], Samolyuk, German D. [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States). Materials Science & Technology Division] (ORCID:0000000168778255), Zarkadoula, Eva [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States). Center for Nanophase Materials Sciences (CNMS)] (ORCID:0000000268869664), Campbell, Anne [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States). Materials Science & Technology Division] (ORCID:0000000191099541). 2025-08-22. Be₂C as a neutron moderator for molten salt reactors: A first-principles study of structural, electronic, and defect properties. https://doi.org/10.1016/j.jallcom.2025.183209
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