Manufacturing B4C-Al dispersion absorber plates using the picture-frame technique

Abstract

The rising global demand for nuclear energy emphasizes the importance of neutron absorber materials, essential for spent fuel storage and other nuclear applications. This study focuses on manufacturing neutron absorber plates using the picture-frame technique, incorporating varying B4C volume contents on an aluminum matrix in the plates' meat. Three configurations were explored, and the plates underwent radiographic, mechanical, microstructural, and neutronic evaluations. The results confirmed the viability of producing neutron absorber plates with reduced dimensions using the picture-frame method. Material properties were comparable to those of commercial neutron absorbers, indicating scalability for larger sizes, and facilitating the eventual deployment of this product. Plates with 45 vol% B4C demonstrated favorable neutron shielding properties, achieving 100 % attenuation in a thermal neutron beam with a 4.0 mm thick B4C-Al dispersion. However, adding B4C to the aluminum matrix caused a decline in mechanical performance, with elongation values around 2 %, making these plates unsuitable for structural use, similar to other commercial materials in this category.