Investigation of He–W interactions using DiMES on DIII-D
- Univ. of California, San Diego, CA (United States). Center for Energy Research
- General Atomics, San Diego, CA (United States)
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Australian National Univ., Canberra, ACT (Australia). Research School of Physics and Engineering
- ITER Organization, Saint Paul-Lez-Durance (France)
- Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
- 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
Web of Science
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
Divertor Materials Evaluation System (DiMES)
Impact of divertor material on neutral recycling and discharge fueling in DIII-D