First wall conceptual designs using low atomic number materials

The first wall in a fusion reactor may serve as a sacrificial erosion surface so as to protect the blanket wall behind it. In some applications, it can also serve as an extended-surface plasma limiter. For equal sputtering erosion rates, low Z first wall materials are by far preferable in fusion reactors because the plasma can tolerate greater concentrations. Conceptual designs are presented for radiating, convectively-cooled and direct-contact first wall panels using graphite and silicon carbide. Also presented is a self-adjusting support mechanism to ensure uniform heating of individual first wall panels