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

Title: Exposures of tungsten nanostructures to divertor plasmas in DIII-D

Journal Article · · Physica Scripta
 [1];  [2];  [1];  [3];  [4];  [1];  [1];  [5];  [2];  [2];  [1];  [6];  [6];  [6];  [2];  [1];  [2];  [2];  [7]
  1. Univ. of California San Diego, La Jolla, CA (United States)
  2. General Atomics, San Diego, CA (United States)
  3. Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)
  4. Oak Ridge Institute for Science and Education, Oak Ridge, TN (United States)
  5. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  6. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
  7. Sandia National Lab. (SNL-CA), Livermore, CA (United States)

Tungsten nanostructures (W-fuzz) prepared in the PISCES-A linear device have been found to survive direct exposure to divertor plasmas in DIII-D. W-fuzz was exposed in the lower divertor of DIII-D using the Divertor Material Evaluation System (DiMES). Two samples were exposed in lower single null (LSN) deuterium H-mode plasmas. The first sample was exposed in three discharges terminated by Vertical Displacement Event (VDE) disruptions, and the second in two discharges near the lowered X-point. More recently, three samples were exposed near the lower outer strike point in predominantly helium H-mode LSN plasmas. In all cases, the W-fuzz survived plasma exposure with little obvious damage except in the areas where unipolar arcing occurred. Arcing is effective in W-fuzz removal, and it appears that surfaces covered with W-fuzz can be more prone to arcing than smooth W surfaces.

Research Organization:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); General Atomics, San Diego, CA (United States)
Sponsoring Organization:
USDOE Office of Science (SC)
Contributing Organization:
University of California San Diego, 9500 Gilman Drive, La Jolla, CA 92093-0417 USA MIT Plasma Science and Fusion Ctr, 77 Massachusetts Ave.,Cambridge, MA 02139 USA Oak Ridge Institute for Science and Education, Oak Ridge, TN 37830, USA Oak Ridge National Laboratory, Oak Ridge, TN 37830, USA Lawrence Livermore National Laboratory, 7000 East Avenue, Livermore, CA 94550, USA Sandia National Laboratory, PO Box 969, Livermore, CA 94551-0969 USA
Grant/Contract Number:
AC05-00OR22725; AC04-94AL85000; AC05-06OR23100; AC52-07NA27344; FC02-04ER54698; FG02-07ER54917; SC0002060
OSTI ID:
1324205
Alternate ID(s):
OSTI ID: 1235510; OSTI ID: 1369219
Journal Information:
Physica Scripta, Vol. T167; ISSN 0031-8949
Publisher:
IOP PublishingCopyright Statement
Country of Publication:
United States
Language:
English
Citation Metrics:
Cited by: 29 works
Citation information provided by
Web of Science

References (14)

Helium induced nanoscopic morphology on tungsten under fusion relevant plasma conditions journal January 2008
The occurrence and damage of unipolar arcing on fuzzy tungsten journal August 2015
Exposure of tungsten nano-structure to TEXTOR edge plasma journal August 2011
Exfoliation of the tungsten fibreform nanostructure by unipolar arcing in the LHD divertor plasma journal August 2011
Comparison of tungsten nano-tendrils grown in Alcator C-Mod and linear plasma devices journal July 2013
Plasma surface interaction experimental facility (PISCES) for materials and edge physics studies journal May 1984
A design retrospective of the DIII-D tokamak journal May 2002
Divertor materials evaluation system (DiMES) journal October 1998
Investigation of He–W interactions using DiMES on DIII-D journal January 2016
Characterization of heat loads from mitigated and unmitigated vertical displacement events in DIII-D journal June 2013
Plasma-material interactions in current tokamaks and their implications for next step fusion reactors journal December 2001
Arcing and its role in PFC erosion and dust production in DIII-D journal July 2013
Sputtering properties of tungsten ‘fuzzy’ surfaces journal August 2011
Net versus gross erosion of high- Z materials in the divertor of DIII-D journal April 2014

Cited By (3)

Ignition and erosion of materials by arcing in fusion-relevant conditions journal May 2018
The influence of plasma-surface interaction on the performance of tungsten at the ITER divertor vertical targets journal March 2018
Helium flux effects on bubble growth and surface morphology in plasma-facing tungsten from large-scale molecular dynamics simulations journal May 2019

Similar Records

Impact of divertor material on neutral recycling and discharge fueling in DIII-D
Journal Article · Fri Mar 13 00:00:00 EDT 2020 · Physica Scripta (Online) · OSTI ID:1324205

Investigation of He–W interactions using DiMES on DIII-D
Journal Article · Fri Jan 22 00:00:00 EST 2016 · Physica Scripta · OSTI ID:1324205

DiMES Studies of Temperature Dependence of Carbon Erosion and Re-Deposition in the DIII-D Divertor
Journal Article · Mon Oct 02 00:00:00 EDT 2006 · Physica Scripta · OSTI ID:1324205