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Dependence of divertor heat flux widths on heating power, flux expansion, and plasma current in the NSTX

Journal Article · · Journal of Nuclear Materials
 [1];  [2];  [3];  [4];  [2];  [2]
  1. Oak Ridge Institute for Science and Education (ORISE), Oak Ridge, TN (United States); Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
  2. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
  3. Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States)
  4. Princeton University, NJ (United States)
Here, we report the dependence of the lower divertor surface heat flux profiles, measured from infrared thermography and mapped magnetically to the mid-plane on loss power into the scrape-off layer (PLOSS), plasma current (Ip), and magnetic flux expansion (fexp), as well as initial results with lithium wall conditioning in NSTX. Here we extend previous studies to higher triangularity ~0.7 and higher Ip ≤ 1.2 MA. First we note that the mid-plane heat flux width mapped to the mid-plane, $$λ^{mid}_q$$, is largely independent of PLOSS for PLOSS ≥ 4 MW. $$λ^{mid}_q$$ is also found to be relatively independent of fexp; peak heat flux is strongly reduced as fexp is increased, as expected. Finally, $$λ^{mid}_q$$ is shown to strongly contract with increasing Ip such that $$λ^{mid}_q$$ ∝ I$$^{-1.6}_p$$ with a peak divertor heat flux of qdiv, peak ~ 15 MW/m2 when Ip = 1.2 MA and PLOSS ~ 6 MW. These relationships are then used to predict the divertor heat flux for the planned NSTX-Upgrade, with heating power between 10 and 15 MW, Bt = 1.0 T and Ip = 2.0 MA for 5 s.
Research Organization:
Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA); USDOE Office of Science (SC), Fusion Energy Sciences (FES)
Grant/Contract Number:
AC02-09CH11466; AC05-00OR22725; AC05-06OR23100; AC52-07NA27344
OSTI ID:
1898294
Alternate ID(s):
OSTI ID: 21579081
Report Number(s):
LLNL-JRNL-434147; 402075
Journal Information:
Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Journal Issue: 1 Vol. 415; ISSN 0022-3115
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English

References (20)

Heat flux scaling experiments in NSTX journal March 2003
Multi-machine scaling of the divertor peak heat flux and width for L-mode and H-mode discharges journal March 1999
SOL width scaling from consideration of edge transport in tokamaks journal March 1999
Engineering design of the National Spherical Torus Experiment journal February 2001
Divertor regimes in NSTX journal March 2005
Divertor heat flux scaling with heating power and plasma current in H-mode discharges in the national spherical torus experiment journal June 2007
On the secular density rises in NBI-heated H-mode plasmas in NSTX journal June 2009
Plasma diagnostics for the DIII‐D divertor upgrade journal November 1990
Infrared camera diagnostic for heat flux measurements on the National Spherical Torus Experiment journal December 2003
Geometrical properties of a “snowflake” divertor journal June 2007
The effect of lithium surface coatings on plasma performance in the National Spherical Torus Experiment journal May 2008
Divertor heat flux mitigation in the National Spherical Torus Experiment journal February 2009
Disruptive tokamak density limit as scrape-off layer/divertor phenomenon journal June 1991
Survey of target plate heat flux in diverted DIII-D tokamak discharges journal August 1998
Exploration of spherical torus physics in the NSTX device journal March 2000
Observation of a high performance operating regime with small edge-localized modes in the National Spherical Torus Experiment journal March 2005
Divertor heat flux mitigation in high-performance H-mode discharges in the National Spherical Torus Experiment journal September 2009
Recent results from the National Spherical Torus Experiment journal March 2003
Plasma response to lithium-coated plasma-facing components in the National Spherical Torus Experiment journal November 2009
Edge-Localized-Mode Suppression through Density-Profile Modification with Lithium-Wall Coatings in the National Spherical Torus Experiment journal August 2009

Cited By (1)

Conceptual design of a pre-loaded liquid lithium divertor target for NSTX-U journal November 2016