The plasma–material interaction and high heat flux properties of beryllium are reviewed to determine its suitability as a plasma‐facing component in magnetic fusion energy reactors. Consideration is given to beryllium’s outgassing, erosion, and hydrogen retention characteristics. Its responses to normal and off‐normal high heat fluxes are compared to graphite in both the as‐received and the neutron‐irradiated states. Beryllium’s performance in present‐day devices is assessed, and its expected behavior in future reactors is summarized. It is concluded that beryllium is potentially a better plasma‐facing material than graphite and that more development and testing is warranted.