Lithium borohydride (LiBH₄) as a promising material for neutron–gamma radiation shielding

Abstract

Abstract. This review critically examines recent advances in neutron–gamma radiation shielding with a focus on lithium borohydride (LiBH₄) – based composite materials. The analysis centers on the study by Lotfalian et al. (2024), which employed Monte Carlo neutron transport simulations using the MCNPX code to evaluate LiBH₄ incorporated into high‑performance concrete (HPC). Rather than presenting original numerical calculations, the present article synthesizes published results, clarifies the underlying physical mechanisms, and evaluates the methodological assumptions, strengths, and limitations of LiBH₄‑containing shields in comparison with conventional materials. Particular attention is paid to fast‑neutron attenuation, shield compactness, and long‑term material stability.