ITER divertor research and development activities

D. Driemeyer, D. Bowers, J. Davis, D. Kubik, H. Mantz, M. McSmith, T. Rigney, C. Baxi, L. Sevier, M. Carelli, L. Green, D. Ruzic, D. Hayden, M. Gabler, J. Yuen

Research output: Contribution to journalConference article


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 languageEnglish (US)
Pages (from-to)603-610
Number of pages8
JournalFusion Technology
Issue number3 pt 2
StatePublished - 1994
Externally publishedYes
EventProceedings of the 11th Topical Meeting on the Technology of Fusion Energy - New Orleans, LA, USA
Duration: Jun 19 1994Jun 23 1994

ASJC Scopus subject areas

  • Engineering(all)

Fingerprint Dive into the research topics of 'ITER divertor research and development activities'. Together they form a unique fingerprint.

  • Cite this

    Driemeyer, D., Bowers, D., Davis, J., Kubik, D., Mantz, H., McSmith, M., Rigney, T., Baxi, C., Sevier, L., Carelli, M., Green, L., Ruzic, D., Hayden, D., Gabler, M., & Yuen, J. (1994). ITER divertor research and development activities. Fusion Technology, 26(3 pt 2), 603-610.