Abstract
The predicted divertor conditions for the SPARC tokamak are calculated using SOLPS-ITER for a range of scrape-off-layer (SOL) heat flux widths λq, input powers, and particle fueling locations. Under H-mode scenario conditions with an upstream separatrix density of 1 ×1020 m−3, the most conservative range of λq extrapolations (≈0.15 mm) results in extremely high unmitigated particle and energy fluxes to the divertor, both under full field (12.2 T) and power (PSOL = 29 MW) conditions, and 2/3 field with PSOL = 10 MW. Increasing the cross-field SOL diffusivities by 2–10× reduces the magnitude of the mitigation challenge, however strategies such as impurity seeding or strike-point-sweeping will likely still be required. A combination of steady-state and time-dependent SOLPS-ITER simulations are used to map out phase space diagrams of upstream and divertor conditions. The simulations include parallel currents but neglect cross-field drifts. At low upstream density the inner and outer divertor conditions are highly asymmetric, with a large temperature difference and significant heat fluxes driven by parallel currents. The solution has sharp bifurcations with a region of hysteresis, depending on whether the initial state is at a low or high density. This behavior is observed even when the fueling location, cross-field diffusivity, and impurity level is changed, although the density window with asymmetry is reduced with increasing diffusivity. The addition of neon impurity seeding reduces the divertor heat fluxes, but also causes a drop in the upstream electron density with fixed particle throughput. This drop can be counteracted by increased main ion throughput, however too much neon results in a back transition into the asymmetric divertor regimes suggesting a need for control of both main ion and impurity seeding levels to achieve a desired divertor state.
Original language | English |
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Article number | 126054 |
Journal | Nuclear Fusion |
Volume | 64 |
Issue number | 12 |
DOIs | |
State | Published - Dec 2024 |
Funding
This manuscript has been authored by UT-Battelle, LLC, with the US Department of Energy (DOE). The work was supported in part by the US DOE Office of Fusion Energy Sciences under Contract DE-AC05-00OR22725 under the spherical tokamak program, by the ORNL Laboratory Directed Research and Development Program, by the Innovation Network for Fusion Energy (INFUSE), and by Commonwealth Fusion Systems. This research used resources of the Oak Ridge National Laboratory Research Cloud. The results are obtained with the help of the EIRENE package (see www.eirene.de) including the related code, data and tools [22].
Keywords
- SOLPS-ITER
- SPARC
- detachment
- divertor
- hysteresis
- thermo-electric