|About this Abstract
||2023 TMS Annual Meeting & Exhibition
||Ceramic Materials for Nuclear Energy Research and Applications
||Radiation Damage in Lithium Oxide, a Surrogate for Beryllium Carbide
||David Magee, David E. Holcomb, Stephen S. Raiman
|On-Site Speaker (Planned)
Be2C is a proposed moderator material for molten salt reactors due to its neutron moderating properties, high melting point, and corrosion resistance in FLiBe salt. Radiation damage in this material at high temperature is unknown. The only known study of irradiation damage in Be2C was at 90°C to a fluence of less than 0.01 dpa. The toxicity of beryllium makes studying its properties especially difficult. Li2O is a useful surrogate because it shares a common antifluorite crystal structure with Be2C.
For this work, radiation damage in Li2O was investigated. Solid Li2O was fabricated from powder with spark plasma sintering, and irradiated with oxygen ions at 700ᴼC. Samples were examined with TEM and data is presented showing how radiation affected the microstructure of the materials. This work presents new data on the behaviour of an antifluorite structured ceramic under irradiation, for use in understanding the potential behaviour of Be2C.
||Nuclear Materials, Ceramics, Other