Irradiation Effects in Boron Carbide Pellets Irradiated in Fast Neutron Spectra

Abstract

Fast neutron spectra irradiations of boron carbide are being performed. Hardened spectra irradiations in ETR, material irradiations in EBR-II, and EBR-II components yielded the data which are being used for design and analysis of FFTF control elements. Boron carbide was irradiated at temperatures from 800 to 1600°F at burnup values from 2 × 10²⁰ to 20 × 10²⁰ captures/cm³. A variety of material parameters such as pellet density and boron-to-carbon ratios were measured. Data on gas release, swelling, thermal conductivity, microscopy, and compatibility were found to differ substantially from data obtained in thermal reactors.