Microstructure of Neutron-Irradiated Al(3)Hf-Al Thermal Neutron Absorber Materials

中子辐照Al(3)Hf-Al热中子吸收材料的微观结构

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Abstract

A thermal neutron-absorbing metal matrix composite (MMC) comprised of Al(3)Hf particles in an aluminum matrix was developed to filter out thermal neutrons and create a fast flux environment for material testing in a mixed-spectrum nuclear reactor. Intermetallic Al(3)Hf particles capture thermal neutrons and are embedded in a highly conductive aluminum matrix that provides conductive cooling of the heat generated due to thermal neutron capture by the hafnium. These Al(3)Hf-Al MMCs were fabricated using powder metallurgy via hot pressing. The specimens were neutron-irradiated to between 1.12 and 5.38 dpa and temperatures ranging from 286 °C to 400 °C. The post-irradiation examination included microstructure characterization using transmission electron microscopy (TEM) and energy-dispersive X-ray spectroscopy. This study reports the microstructural observations of four irradiated samples and one unirradiated control sample. All the samples showed the presence of oxide at the particle-matrix interface. The irradiated specimens revealed needle-like structures that extended from the surface of the Al(3)Hf particles into the Al matrix. An automated segmentation tool was implemented based on a YOLO11 computer vision-based approach to identify dislocation lines and loops in TEM images of the irradiated Al-Al(3)Hf MMCs. This work provides insight into the microstructural stability of Al(3)Hf-Al MMCs under irradiation, supporting their consideration as a novel neutron absorber that enables advanced spectral tailoring.

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