Abstract
Mixed-material DIVIMP-WallDYN modeling, now incorporating ExB drifts, is presented that simultaneously reproduces tungsten (W) erosion and deposition patterns observed during the DIII-D metal rings campaign, in which a toroidally symmetric set of W-coated tiles were installed in the carbon (C) DIII-D divertor. Since most reactor plasma facing component (PFC) designs call for mixed-material environments, including ITER's W/Be environment, the divertor targets will quickly evolve into reconstituted surfaces of multiple elements. This work identifies controlling physics that affects material migration patterns in the divertor, which impact PFC lifetimes and impurity leakage from the divertor to the core. These simulations indicate that radial and poloidal ExB transport dominates over parallel force balance for high-Z impurities such as Win the divertor region of DIII-D. It is demonstrated that ExB drifts are required to reproduce the experimental observation of non-localW and C co-accumulation in a band ∼7-9 cm outboard of the outer-strike-point (OSP) W source, for attached L-mode conditions in the unfavorable ion grad-B drift direction. In addition,W gross erosion is localized to the region outboard of the OSP, as the formation of C co-deposits suppresses W erosion at the strike point. Time-dependent simulations with scaled ExB impurity drifts (60% of the OEDGE-calculated drift velocity) and W re-erosion quantitatively reproduce these features, including depth-resolvedW/C ratios, within a factor of 2 over ∼115 s of accumulated plasma exposure. The location of co-deposition regions is shown to be well-represented by an analytic leakage model, driven largely by poloidal ExB drifts. Qualitative agreement is also found between campaign-integratedW deposition measurements and simulations for the favorable ion grad-B drift direction, the standard mode of operation for most tokamaks. These results imply that a long-term inward radial migration of material from the outer divertor through the private flux region may occur in future devices 2021 IAEA, Vienna.
Original language | English |
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Article number | 096018 |
Journal | Nuclear Fusion |
Volume | 61 |
Issue number | 9 |
DOIs | |
State | Published - Sep 2021 |
Funding
This material is based upon work supported by the US Department of Energy, Office of Science, Office of Fusion Energy Sciences, using the DIII-D National Fusion Facility, a DOE Office of Science user facility, under Awards DE-FC02- 04ER54698, DE-AC05-00OR22725, DE-SC0016318, DESC0019256, DE-FG02-07ER54917, and DE-NA0003525. JHN was supported in part by the US DOE Fusion Energy Sciences Postdoctoral Research Program.
Keywords
- DIII-D
- Drifts
- Impurity transport
- Tungsten