Although the spent fuel discharged from the nuclear reactor cannot continue to meet the power and efficiency requirements of the nuclear reactor, it still contains a large amount of radioactive elements and releases a small number of neutrons. The structural material used to absorb the subsequent neutrons is a key factor in the medium-term storage scheme of spent fuel.

Thermal neutron absorption materials usually refer to materials containing elements with high neutron absorption cross sections. Common elements with high neutron absorption cross sections include boron, silver, cadmium, etc.

B4C has excellent mechanical and mechanical properties, as well as high neutron absorption cross section element B-10, Al/B4C metal matrix composites are considered as excellent candidates for neutron absorption materials to prevent critical reactions in spent fuel storage.