Measurements and modeling of type-I and type-II ELMs heat flux to the DIII-D divertor

Journal Article · Wed Jul 12 00:00:00 EDT 2023 · Nuclear Fusion

DOI:https://doi.org/10.1088/1741-4326/acdf02· OSTI ID:1989770

Perillo, R. ; Boedo, J. A.; Lasnier, C. J. ; Pitts, R. A. ; Brank, M.; Bykov, I.; Coburn, J. D. ; Glass, F.; Marini, C. ; Osborne, T.; Riding, M.; Rudakov, D. L. ; Watkins, J. G.; Zeng, L.

Abstract Type-I and type-II edge-localized-modes (ELMs) heat flux profiles measured at the DIII-D divertor feature a peak in the vicinity of the strike-point and a plateau in the scrape-off-layer (SOL), which extends to the first wall. The plateau is present in attached and detached divertors and it is found to originate with plasma bursts upstream in the SOL. The integrated ELM heat flux is distributed at ∼65% in the peak and ∼35% in this plateau. The parallel loss model, currently used at ITER to predict power loads to the walls, is benchmarked using these results in the primary and secondary divertors with unprecedented constraints using experimental input data for ELM size, radial velocity, energy, electron temperature and density, heat flux footprints and number of filaments. The model can reproduce the experimental near-SOL peak within ∼20%, but cannot match the SOL plateau. Employing a two-component approach for the ELM radial velocity, as guided by intermittent data, the full radial heat flux profile can be well matched. The ELM-averaged radial velocity at the separatrix, which explains profile widening, increases from ∼0.2 km s ⁻¹ in attached to ∼0.8 km s ⁻¹ in detached scenarios, as the ELM filaments’ path becomes electrically disconnected from the sheath at the target. The results presented here indicate filaments fragmentation as a possible mechanism for ELM transport to the far-SOL and provide evidence on the beneficial role of detachment to mitigate ELM flux in the divertor far-SOL. However, these findings imply that wall regions far from the strike points in future machines should be designed to withstand significant heat flux, even for small-ELM regimes.

• Sponsoring Organization: USDOE
• Grant/Contract Number: AC52-07NA27344
• OSTI ID: 1989770
• Alternate ID(s): OSTI ID: 1985575
• Journal Information: Nuclear Fusion, Journal Name: Nuclear Fusion Vol. 63 Journal Issue: 8; ISSN 0029-5515
• Publisher: IOP Publishing
• Country of Publication: IAEA
• Language: English