The corrosion behavior of B4C/6061Al in spent nuclear fuel (SNF) storage environments was investigated in H3BO3 solutions (0-10,000 ppm) at temperatures ranging from 20 degrees C to 90 degrees C by using experimental and computational approaches. The results reveal that dispersed B4C particles act as cathodes, accelerating the dissolution of the aluminum matrix rather than causing localized trench formation. In deionized water, a dual-layered protective corrosion product film forms, consisting of an inner gamma-AlOOH layer and an outer Al(OH)(3) layer. H3BO3 dissolves both the aluminum matrix and its corrosion products in the following order: Al(OH)(3) > gamma-AlOOH > aluminum matrix, with increasing effect at higher concentrations. Elevated temperatures enhance both the formation of corrosion products and the dissolution rate by H+. Overall, the results suggest that B4C/6061Al exhibits high corrosion resistance in deionized water (BWR conditions) but suffers significant degradation in H3BO3-containing pools (PWR conditions).