Published October 1972 | Version v1
Journal article

Irradiation effects in boron carbide pellets irradiated in fast neutron spectra

Description

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.

Additional details

Identifiers

Publishing Information

Journal Title
Nuclear Technology
Journal Volume
16
Journal Issue
1
Series
Nucl. Technol.
Journal Page Range
238-248
ISSN
0029-5450

Optional Information

Notes
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