Speaker
Description
UEDGE simulations of a “chimney” divertor, utilizing mid-leg pumping upstream of the divertor target along the outer baffle, predict the formation of a stable radiation front between the pumping plenum and X-point. The mid-leg pumping plenum is proposed as an engineering solution to stabilize the detachment front location downstream of the X-point, maintaining a hot X-point ($\rm T_{e,Xpt}$ ~ $\rm T_{e,sep,OMP}$) simultaneously with a detached divertor target (Te,targ < ~5 eV). UEDGE simulations, including magnetic and $\rm\bf E\times B$ drifts, predict radiation front control between the pumping plenum and X-point using low-field side main-ion gas puffing with the ion $\rm \mathbf{B}\times\nabla B$ directed towards the X-point. In the opposite B-field direction, with ion $\rm \mathbf{B}\times\nabla B$ directed away from the X-point, limited control is predicted due to $\rm\bf E_\theta\times B$ and $\rm\mathbf{E}_r\times \bf B$ divertor drift flows yielding significant current to the pumping surface, resulting in efficient removal of the injected gas.
This work will expand on previous simulations of a proposed mid-leg pumped low-field side “chimney” divertor, planned to be installed in the DIII-D upper divertor [1,2]. The “chimney” design employs a closed divertor structure and an extended outer leg with a 4.5 cm deep volume at the end of the divertor slot, which acts as a neutral reservoir for power exhaust through ion-neutral interaction [3]. The UEDGE-predicted sensitivity of the radiation front location, volume, and power to operational parameters, including main- and impurity particle injection and applied heating power will be presented. Furthermore, UEDGE model fidelity will be increased compared to initial simulations [1] by modeling the transport of individual charge states of the seeded impurities and including fluid molecules as a separate species in the simulations. The UEDGE pumping model applied will be compared to DEGAS2 kinetic Monte-Carlo neutral simulations to assess the fidelity of the UEDGE fluid neutral pumping model and validate previous results [1].
The predictive UEDGE and SOLPS-ITER simulations used to design the divertor will be validated against experimental measurements using the proposed chimney divertor and associated diagnostic systems in DIII-D. If passive radiation front stabilization and location control consistent with edge-plasma code predictions are observed experimentally, mid-leg pumped divertors may present an alternative divertor design for future divertors with reduced requirements on divertor volume and radiating impurity injection.
[1] A. Holm et al., “Modeling a divertor with mid-leg pumping for high-power H-mode scenarios in DIII-D considering E × B drift flows,” Nuclear Materials and Energy, vol. 41, p. 101782, 2024.
[2] J. H. Yu et al., “Simulations of divertor designs that spatially separate power and particle exhaust using mid-leg divertor particle pumping,” Nuclear Materials and Energy, vol. 41, p. 101826, 2024.
[3] R. S. Wilcox, et al., “The “Chimney” divertor: A closed divertor with mid-leg pumping for core-edge integration in DIII-D”, this meeting.
This work was supported in part by the US Department of Energy under contract nos. DE-FC02-04ER54698, DE-AC52-07NA27344, and DE-AC05-00OR22725. LLNL-ABS-2006456.
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Speaker's title | Mr |
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Speaker's Affiliation | Lawrence Livermore National Laboratory, Livermore, CA |
Member State or IGO | United States of America |