skip to main content


Title: Innovative divertor concept development on DIII-D and EAST

A critical issue facing the design and operation of next-step high-power steady-state fusion devices is the control of heat fluxes and erosion at the plasma-facing components, in particular, the divertor target plates. A new initiative has been launched on DIII-D to develop and demonstrate innovative boundary plasma-materials interface solutions. The central purposes of this new initiative are to advance scientific understanding in this critical area and develop an advanced divertor concept for application to next-step fusion devices. Finally, DIII-D will leverage strong collaborative efforts on the EAST superconducting tokamak for extending integrated high performance advanced divertor solutions to true steady-state.
 [1] ;  [1] ;  [1] ;  [1] ;  [1] ;  [1] ;  [1] ;  [1] ;  [1] ;  [2] ;  [2] ;  [2] ;  [2]
  1. DIII-D National Facility, San Diego, CA (United States)
  2. Chinese Academy of Sciences (CAS), Hefei (China)
Publication Date:
Grant/Contract Number:
Accepted Manuscript
Journal Name:
2015 IEEE 26th Symposium on Fusion Engineering (SOFE)
Additional Journal Information:
Journal Name: 2015 IEEE 26th Symposium on Fusion Engineering (SOFE); Conference: Austin, TX (United States), 31 May - Jun 4 2015; Journal ID: ISSN 2155-9953
Research Org:
General Atomics, San Diego, CA (United States)
Sponsoring Org:
Boundary/Plasma-Materials Interaction Center, DIII-D National Facility, San Diego, USA; USDOE
Country of Publication:
United States
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; heating; tokamaks; plasma temperature; temperature measurement; physics; collaboration; plasma-materials interaction; divertor
OSTI Identifier: