Irradiation Effects in Boron Carbide Pellets Irradiated in Fast Neutron Spectra

1 October 1972

journal article
research article
Published by Taylor & Francis in Nuclear Technology

Vol. 16 (1) , 238-248
https://doi.org/10.13182/nt72-a31190

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.

Keywords

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