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

Title: Investigation of He–W interactions using DiMES on DIII-D

Journal Article · · Physica Scripta
 [1];  [1];  [2];  [3];  [4];  [5];  [4];  [6];  [6];  [2];  [5];  [7];  [4];  [7]
  1. Univ. of California, San Diego, CA (United States). Center for Energy Research
  2. General Atomics, San Diego, CA (United States)
  3. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  4. Australian National Univ., Canberra, ACT (Australia). Research School of Physics and Engineering
  5. ITER Organization, Saint Paul-Lez-Durance (France)
  6. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
  7. Univ. of Wisconsin, Madison, WI (United States)

Tungsten button samples were exposed to He ELMing H-mode plasma in DIII-D using 2.3 MW of Electron Cyclotron heating power. Prior to the exposures, the W buttons were exposed to either He, or D, plasma in PISCES-A for 2000 seconds at surface temperatures of 225–850 C to create a variety of surfaces (surface blisters, subsurface nano-bubbles, fuzz). Erosion was spectroscopically measured from each DiMES sample, with the exception of the fuzzy W samples which showed almost undetectable WI emission. Post-exposure grazing incidence small angle x-ray scattering (GISAXS) surface analysis showed the formation of 1.5 nm diameter He bubbles in the surface of W buttons after only a single DIII-D (3 sec., ~150 ELMs) discharge, similar to the bubble layer resulting from the 2000 sec. exposure in PISCES-A. No surface roughening, or damage, was detected on the samples after approximately 600 ELMs with energy density between 0.04 – 0.1 MJm-2.

Research Organization:
Univ. of California, San Diego, CA (United States); Univ. of Wisconsin, Madison, WI (United States); Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); General Atomics, San Diego, CA (United States)
Sponsoring Organization:
USDOE Office of Science (SC), Fusion Energy Sciences (FES)
Contributing Organization:
ITER Organization, Saint Paul-Lez-Durance (France); Australian National Univ., Canberra, ACT (Australia)
Grant/Contract Number:
FG02-07ER54917; FG02-89ER53296; FG02-08ER54999; FG02-07ER54912; AC52-07NA27344; AC05-00OR22725; FC02-04ER54698
OSTI ID:
1319233
Alternate ID(s):
OSTI ID: 1372317
Journal Information:
Physica Scripta, Vol. 2016, Issue T167; ISSN 0031-8949
Publisher:
IOP PublishingCopyright Statement
Country of Publication:
United States
Language:
English
Citation Metrics:
Cited by: 16 works
Citation information provided by
Web of Science

References (15)

Research status and issues of tungsten plasma facing materials for ITER and beyond journal October 2014
Overview of ASDEX Upgrade results journal August 2011
Plasma operation with an all metal first-wall: Comparison of an ITER-like wall with a carbon wall in JET journal July 2013
A design retrospective of the DIII-D tokamak journal May 2002
Plasma surface interaction experimental facility (PISCES) for materials and edge physics studies journal May 1984
Microscopic damage of tungsten exposed to deuterium–helium mixture plasma in PISCES and its impacts on retention property journal August 2011
Formation of Nanostructured Tungsten with Arborescent Shape due to Helium Plasma Irradiation journal January 2006
Helium induced nanoscopic morphology on tungsten under fusion relevant plasma conditions journal January 2008
Formation mechanism of bubbles and holes on tungsten surface with low-energy and high-flux helium plasma irradiation in NAGDIS-II journal August 2004
Helium effects on tungsten under fusion-relevant plasma loading conditions journal July 2013
Near-surface thermal characterization of plasma facing components using the 3-omega method journal December 2014
Sputtering properties of tungsten ‘fuzzy’ surfaces journal August 2011
A full tungsten divertor for ITER: Physics issues and design status journal July 2013
Probing helium nano-bubble formation in tungsten with grazing incidence small angle x-ray scattering journal March 2015
Tungsten ‘fuzz’ growth re-examined: the dependence on ion fluence in non-erosive and erosive helium plasma journal August 2015

Cited By (2)

The influence of plasma-surface interaction on the performance of tungsten at the ITER divertor vertical targets journal March 2018
Plasma Power Recycling at the Divertor Surface journal January 2017

Similar Records

Exposures of tungsten nanostructures to divertor plasmas in DIII-D
Journal Article · Fri Jan 22 00:00:00 EST 2016 · Physica Scripta · OSTI ID:1319233

Divertor Materials Evaluation System (DiMES)
Conference · Sat Nov 01 00:00:00 EST 1997 · OSTI ID:1319233

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:1319233