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Title: Scaling of Divertor Heat Flux Profile Widths in DIII-D

Conference ·

The width of the divertor heat flux profile w{sub q,div} is of great interest in future large tokamaks as well as many present devices. Previous studies examining the parametric dependence of w{sub q,div} have arrived at diverse scalings in JET, ASDEX-Upgrade, JT60-U, DIII-D, and NSTX with results somewhat at variance with each other. We attempt here to perform a new series of experiments in DIII-D under controlled conditions to obtain scaling of the divertor heat flux peak value, profile width, and divertor plate power as a function of plasma input parameters, with the maximum number of divertor and scrape-off-layer (SOL) diagnostics brought to bear. We performed measurements in lower single-null edge localized mode (ELM) H-mode diverted configurations that were not strongly pumped due to the strike-point positions. We varied the plasma current I{sub p} at constant toroidal field (B{sub T}) and line-averaged density {bar n}{sub e} at constant I{sub p} and B{sub T}. The neutral beam injected power P{sub inj} was changed at constant I{sub p} and BT, B{sub T} at constant I{sub p}, and B{sub T}/I{sub p} at constant q{sub 95}. The divertor heat flux was calculated from infrared camera measurements using a new high-resolution fast-framing IR camera. The IR camera recorded divertor plate surface thermal emission at many-kilohertz frame rates through the whole discharge, so that time-averaged data as well as rapid changes due to ELMs were obtained. The heat flux at each position in the radial profile was calculated at each of the times steps using the THEODOR 2D heat flux analysis code. We show scaling of the divertor peak heat flux and profile width as a function of the parameters varied, and compare with published results from other devices.

Research Organization:
Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
Sponsoring Organization:
USDOE
DOE Contract Number:
W-7405-ENG-48
OSTI ID:
966573
Report Number(s):
LLNL-PROC-413814; TRN: US0904064
Resource Relation:
Journal Volume: 415; Journal Issue: 1; Conference: Presented at: 36th EPS Conference on Plasma Physics, Sofia, Bulgaria, Jun 29 - Jul 03, 2009
Country of Publication:
United States
Language:
English

References (6)

Chapter 4: Power and particle control journal June 2007
Disruption heat loads on the JET MkIIGB divertor journal May 2002
Chapter 1: Overview and summary journal December 1999
Multi-machine scaling of the divertor peak heat flux and width for L-mode and H-mode discharges journal March 1999
Survey of target plate heat flux in diverted DIII-D tokamak discharges journal August 1998
Divertor heat flux scaling with heating power and plasma current in H-mode discharges in the national spherical torus experiment journal June 2007