Be₂C as a neutron moderator for molten salt reactors: A first-principles study of structural, electronic, and defect properties

Yuri Osetskiy, Mao Hua Du, German Samolyuk, Eva Zarkadoula, Anne Campbell

Research output: Contribution to journalArticlepeer-review

Abstract

Beryllium carbide (Be2C), 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 Be2C, 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. 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.

Original languageEnglish
Article number183209
JournalJournal of Alloys and Compounds
Volume1039
DOIs
StatePublished - Sep 10 2025

Funding

This research was supported by the US Department of Energy Office of Nuclear Energy Molten Salt Reactor Program. EZ was supported by the Center for Nanophase Materials Sciences, (CNMS), which is a US Department of Energy, Office of Science User Facility at Oak Ridge National Laboratory. Computer modeling was supported by a U.S. Department of Energy Office of Science User Facility NERSC located at Lawrence Berkeley National Laboratory, operated under Contract No. DE-AC02–05CH11231 using NERSC award FES-ERCAP0025846 as well as Compute and Data Environment for Science (CADES) at the Oak Ridge National Laboratory, managed by UT-Battelle, LLC, under contract No. DE-AC05–00OR22725 for the US Department of Energy. This manuscript has been authored in part by UT-Battelle, LLC, under contract DE-AC05–00OR22725, with the US Department of Energy (DOE). The US government retains and the publisher, by accepting the article for publication, acknowledges that the US government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for US government purposes. DOE will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan ( http://energy.gov/downloads/doe-public-access-plan ).

Keywords

  • Ab initio modeling
  • Charged defects
  • Density functional theory
  • Lattice defects
  • Molten salt reactors
  • Neutron moderator

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