skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Measurements of tungsten migration in the DIII-D divertor

Journal Article · · Physica Scripta
 [1];  [1];  [1];  [2]; ORCiD logo [3];  [4]
  1. Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
  2. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
  3. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  4. Univ. of Toronto, ON (Canada)

An experimental study of migration of tungsten in the DIII-D divertor is described, in which the outer strike point of L-mode plasmas was positioned on a toroidal ring of tungsten-coated metal inserts. Net deposition of tungsten on the divertor just outside the strike point was measured on graphite samples exposed to various plasma durations using the divertor materials evaluation system. Tungsten coverage, measured by Rutherford backscattering spectroscopy (RBS), was found to be low and nearly independent of both radius and exposure time closer to the strike point, whereas farther from the strike point the W coverage was much larger and increased with exposure time. Depth profiles from RBS show this was due to accumulation of thicker mixed-material deposits farther from the strike point where the plasma temperature is lower. These results are consistent with a low near-surface steady-state coverage on graphite undergoing net erosion, and continuing accumulation in regions of net deposition. This experiment provides data needed to validate, and further improve computational simulations of erosion and deposition of material on plasma-facing components and transport of impurities in magnetic fusion devices. Such simulations are underway and will be reported later.

Research Organization:
Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
USDOE Office of Science (SC), Fusion Energy Sciences (FES)
Grant/Contract Number:
AC04-94AL85000; AC05-00OR22725
OSTI ID:
1477317
Alternate ID(s):
OSTI ID: 1483173
Report Number(s):
SAND-2018-10807J; 668371
Journal Information:
Physica Scripta, Vol. T170; ISSN 0031-8949
Publisher:
IOP PublishingCopyright Statement
Country of Publication:
United States
Language:
English
Citation Metrics:
Cited by: 8 works
Citation information provided by
Web of Science

References (11)

Modelling of Impurity Transport and Plasma-Wall Interaction in Fusion Devices with the ERO Code: Basics of the Code and Examples of Application: Modelling of Impurity Transport and Plasma-Wall Interaction in Fusion Devices with the ERO Code: Basics of the Code and Examples of Application journal July 2016
WALLDYN simulations of global impurity migration in JET and extrapolations to ITER journal April 2015
Analysis of a tungsten sputtering experiment in DIII-D and code/data validation of high redeposition/reduced erosion journal May 2015
Simulation of gross and net erosion of high- Z materials in the DIII-D divertor journal December 2015
DiMES PMI research at DIII-D in support of ITER and beyond journal November 2017
Net versus gross erosion of high- Z materials in the divertor of DIII-D journal April 2014
Measurements of net erosion and redeposition of molybdenum in DIII-D journal July 2013
Gross and net erosion of tungsten in the outer strike-point region of ASDEX Upgrade journal January 2016
Tungsten as target material in fusion devices journal June 1996
Modelling of tungsten re-deposition coefficient journal August 2015
Modelling of carbon migration during JET 13 C injection experiments journal August 2008

Cited By (3)

Impact of ELM control techniques on tungsten sputtering in the DIII-D divertor and extrapolations to ITER journal June 2019
Multiple Analytical Approach to Isotopic Transport Analysis in Magnetic Fusion Devices journal May 2019
DIII-D research towards establishing the scientific basis for future fusion reactors journal June 2019