Beryllium as a Plasma-Facing Material for Near-Term Fusion Devices

摘要: This chapter reviews the properties and features of beryllium (i.e., plasma–wall interactions, thermal mechanical properties, fabricability ease joining, chemical reactivity, etc.) that are primary relevance for plasma protection applications in near-term magnetic fusion devices together with available knowledge on performance operation existing machines. Special attention is given to beryllium’s erosion deposition, formation mixed materials, hydrogen retention release characteristics play an important role performance, component lifetime, operational safety. The status techniques presently considered joining armor heat sink material copper alloys fabrication beryllium-clad actively cooled ITER first-wall components briefly discussed results durability flux tests conducted frame qualification program. effects neutron irradiation degradation itself joints also analyzed. On basis information from machines, expected behavior future reactors critically attempt made quantify main still issue design ITER.