Design of Aluminum Matrix B₄C In-Core Irradiation Test Program

As a new candidate for spent fuel storage framework material, in-core irradiation test for aluminum matrix boron carbide (B₄C) was performed to evaluate its irradiation behavior. The experiment was designed and analyzed according to sample’s composition and shape, irradiation box characters, and core arrangement. The neutronic and thermal hydraulic simulations indicate that the scheme of the experiment chosen can meet the requirement of all parameters, such as γ dose, integral fast neutron flux, power peaking factor, core reactivity, and sample heating rate.