This paper presents some results achieved from the ongoing ITER Plasma Facing Components research and development tasks. The overall effort involves U.S. industry, universities and national laboratories which are directed towards developing and/or testing: 1) ductile beryllium and beryllium joining techniques; 2) prototype divertor component design, fabrication and testing; 3) fiber-reinforced composites, for beryllium and carbon; 4) beryllium plasma spray processes; 5) complaint layers for PFC armor attachment; 6) sacrificial armor layers for the divertor end-plates; 7) tritium permeation and inventory in proposed PFC materials and components. The paper focuses on work being carried out by the industrial support team.
|Original language||English (US)|
|Number of pages||8|
|Issue number||3 pt 2|
|State||Published - 1994|
|Event||Proceedings of the 11th Topical Meeting on the Technology of Fusion Energy - New Orleans, LA, USA|
Duration: Jun 19 1994 → Jun 23 1994
ASJC Scopus subject areas