2010 OFES Joint Research TargetDivertor Heat Flux Profile Width Final Report DIII-D Contribution

Technical Report · Fri Sep 17 00:00:00 EDT 2010

DOI:https://doi.org/10.2172/1124807· OSTI ID:1124807

Lasnier, C. J. ^[1]; Makowski, M. A. ^[1]; Boedo, J. A. ^[2]; Hill, D. N. ^[1]; Leonard, A. W. ^[3]; Porter, G. D. ^[1]; Rensink, M. E. ^[1]; Watkins, J. G. ^[4]

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1. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
2. Univ. of California, San Diego, CA (United States)
3. General Atomics, San Diego, CA (United States)
4. Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

Conduct experiments on major fusion facilities to improve understanding of the heat transport in the tokamak scrape-off layer (SOL) plasma, strengthening the basis for projecting divertor conditions in ITER. In FY10, FES will measure the divertor heat flux profiles and plasma characteristics in the tokamak scrape-off layer in multiple devices to investigate the underlying thermal transport processes. The unique characteristics of C-Mod, DIII-D, and NSTX will enable collection of data over a broad range of SOL and divertor parameters (e.g., collisionality, beta, parallel heat flux, and divertor geometry). Regimes similar to the ITER operating scenarios will be among those studied and characterized. Coordinated experiments using common analysis methods will generate a data set that will be compared with theory and simulation.

• Research Organization: Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
• Sponsoring Organization: USDOE
• DOE Contract Number: W-7405-ENG-48; AC52-07NA27344; FG002-07ER4917; FC02-04ER54698; AC04-94AL85000
• OSTI ID: 1124807
• Report Number(s): LLNL-TR-455813
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION