Innovative divertor concept development on DIII-D and EAST

Journal Article · Thu Jun 02 00:00:00 EDT 2016 · 2015 IEEE 26th Symposium on Fusion Engineering (SOFE)

DOI:https://doi.org/10.1109/SOFE.2015.7482265· OSTI ID:1372692

Guo, H. Y. ^[1]; Allen, S. ^[1]; Canik, J. ^[1]; Hill, D. N. ^[1]; Leonard, T. ^[1]; Sang, C. F. ^[1]; Stangeby, P. C. ^[1]; Thomas, D. M. ^[1]; Unterberg, Z. ^[1]; Luo, G. N. ^[2]; Wang, L. ^[2]; Wan, B. N. ^[2]; Xu, G. S. ^[2]

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1. DIII-D National Facility, San Diego, CA (United States)
2. Chinese Academy of Sciences (CAS), Hefei (China)

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.

• Research Organization: General Atomics, San Diego, CA (United States)
• Sponsoring Organization: Boundary/Plasma-Materials Interaction Center, DIII-D National Facility, San Diego, USA; USDOE
• Grant/Contract Number: FC02-04ER54698
• OSTI ID: 1372692
• Journal Information: 2015 IEEE 26th Symposium on Fusion Engineering (SOFE), Conference: Austin, TX (United States), 31 May - Jun 4 2015; ISSN 2155-9953
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
heating
tokamaks
plasma temperature
temperature measurement
physics
collaboration
plasma-materials interaction
divertor