Modeling a divertor with mid-leg pumping for high-power H-mode scenarios in DIII-D considering E × B drift flows

Andreas Holm; Robert S. Wilcox; Jonathan H. Yu; Thomas D. Rognlien; Marvin E. Rensink; Filippo Scotti; Roberto Maurizio; Steve L. Allen; Wilkie Choi; Anothony W. Leonard; Morgan W. Shafer; Mathias Groth; Adam McLean

doi:10.1016/j.nme.2024.101782

Modeling a divertor with mid-leg pumping for high-power H-mode scenarios in DIII-D considering E × B drift flows

Andreas Holm, Robert S. Wilcox, Jonathan H. Yu, Thomas D. Rognlien, Marvin E. Rensink, Filippo Scotti, Roberto Maurizio, Steve L. Allen, Wilkie Choi, Anothony W. Leonard, Morgan W. Shafer, Mathias Groth, Adam McLean

Advanced Tokamak Physics

Research output: Contribution to journal › Article › peer-review

Abstract

Edge-plasma simulations of a baffled, long-legged divertor in DIII-D, performed using the multi-fluid code UEDGE, indicate that the position of the detachment front is constrained to the location of the pump duct along the low-field side (LFS) baffle. Simulations including magnetic and E×B drifts were performed for 12.5 MW deuterium plasmas including intrinsic carbon and seeded neon to assess the optimal location of the LFS divertor pump to create a stable detachment front between the target and the X-point. The radiation front position in the simulations, taken to be indicative of the detachment front, can be controlled between the pump and X-point in the favorable magnetic field direction for H-mode access by moving the pump duct location upstream of the target along the LFS baffle. In the unfavorable magnetic field direction, the radial E_θ×B drift flows are directed towards the pumping surface, efficiently removing the injected deuterium gas and limiting the sensitivity of the radiation front location to the gas injection rate. The role of pumping rate and drift direction on the pumping efficiency are also found to affect the divertor plasma conditions and detachment front location in UEDGE simulations.

Original language	English
Article number	101782
Journal	Nuclear Materials and Energy
Volume	41
DOIs	https://doi.org/10.1016/j.nme.2024.101782
State	Published - Dec 2024

Funding

This material is based upon work supported by the U.S. Department of Energy, United States, Office of Science, United States, Office of Fusion Energy Sciences, under Award Numbers DE-FC02-04ER54698, DE-AC52-07NA27344, and DE-AC05-00OR22725. This work was performed using UEDGE V8.1.0 and the results analyzed using the UEDGE Toolbox V1.2.0, available publicly via GitHub (github.com/LLNL/UEDGE and github.com/LLNL/UETOOLS) and PyPi. This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof. This material is based upon work supported by the U.S. Department of Energy , Office of Science , Office of Fusion Energy Sciences , under Award Numbers DE-FC02-04ER54698 , DE-AC52-07NA27344 , and DE-AC05-00OR22725 . This work was performed using UEDGE V8.1.0 and the results analyzed using the UEDGE Toolbox V1.2.0, available publicly via GitHub ( github.com/LLNL/UEDGE and github.com/LLNL/UETOOLS ) and PyPi.

Funders	Funder number
U.S. Department of Energy
United States Government
Office of Science
Fusion Energy Sciences	DE-AC05-00OR22725, DE-FC02-04ER54698, DE-AC52-07NA27344
Fusion Energy Sciences

Keywords

DIII-D
Mid-leg pumping
Plasma drifts
UEDGE

UN SDGs

This output contributes to the following UN Sustainable Development Goals (SDGs)

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10.1016/j.nme.2024.101782

Cite this

Holm, A., Wilcox, R. S., Yu, J. H., Rognlien, T. D., Rensink, M. E., Scotti, F., Maurizio, R., Allen, S. L., Choi, W., Leonard, A. W., Shafer, M. W., Groth, M., & McLean, A. (2024). 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, 41, Article 101782. https://doi.org/10.1016/j.nme.2024.101782

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title = "Modeling a divertor with mid-leg pumping for high-power H-mode scenarios in DIII-D considering E × B drift flows",

abstract = "Edge-plasma simulations of a baffled, long-legged divertor in DIII-D, performed using the multi-fluid code UEDGE, indicate that the position of the detachment front is constrained to the location of the pump duct along the low-field side (LFS) baffle. Simulations including magnetic and E×B drifts were performed for 12.5 MW deuterium plasmas including intrinsic carbon and seeded neon to assess the optimal location of the LFS divertor pump to create a stable detachment front between the target and the X-point. The radiation front position in the simulations, taken to be indicative of the detachment front, can be controlled between the pump and X-point in the favorable magnetic field direction for H-mode access by moving the pump duct location upstream of the target along the LFS baffle. In the unfavorable magnetic field direction, the radial Eθ×B drift flows are directed towards the pumping surface, efficiently removing the injected deuterium gas and limiting the sensitivity of the radiation front location to the gas injection rate. The role of pumping rate and drift direction on the pumping efficiency are also found to affect the divertor plasma conditions and detachment front location in UEDGE simulations.",

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author = "Andreas Holm and Wilcox, {Robert S.} and Yu, {Jonathan H.} and Rognlien, {Thomas D.} and Rensink, {Marvin E.} and Filippo Scotti and Roberto Maurizio and Allen, {Steve L.} and Wilkie Choi and Leonard, {Anothony W.} and Shafer, {Morgan W.} and Mathias Groth and Adam McLean",

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doi = "10.1016/j.nme.2024.101782",

language = "English",

volume = "41",

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T1 - Modeling a divertor with mid-leg pumping for high-power H-mode scenarios in DIII-D considering E × B drift flows

AU - Holm, Andreas

AU - Wilcox, Robert S.

AU - Yu, Jonathan H.

AU - Rognlien, Thomas D.

AU - Rensink, Marvin E.

AU - Scotti, Filippo

AU - Maurizio, Roberto

AU - Allen, Steve L.

AU - Choi, Wilkie

AU - Leonard, Anothony W.

AU - Shafer, Morgan W.

AU - Groth, Mathias

AU - McLean, Adam

PY - 2024/12

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N2 - Edge-plasma simulations of a baffled, long-legged divertor in DIII-D, performed using the multi-fluid code UEDGE, indicate that the position of the detachment front is constrained to the location of the pump duct along the low-field side (LFS) baffle. Simulations including magnetic and E×B drifts were performed for 12.5 MW deuterium plasmas including intrinsic carbon and seeded neon to assess the optimal location of the LFS divertor pump to create a stable detachment front between the target and the X-point. The radiation front position in the simulations, taken to be indicative of the detachment front, can be controlled between the pump and X-point in the favorable magnetic field direction for H-mode access by moving the pump duct location upstream of the target along the LFS baffle. In the unfavorable magnetic field direction, the radial Eθ×B drift flows are directed towards the pumping surface, efficiently removing the injected deuterium gas and limiting the sensitivity of the radiation front location to the gas injection rate. The role of pumping rate and drift direction on the pumping efficiency are also found to affect the divertor plasma conditions and detachment front location in UEDGE simulations.

AB - Edge-plasma simulations of a baffled, long-legged divertor in DIII-D, performed using the multi-fluid code UEDGE, indicate that the position of the detachment front is constrained to the location of the pump duct along the low-field side (LFS) baffle. Simulations including magnetic and E×B drifts were performed for 12.5 MW deuterium plasmas including intrinsic carbon and seeded neon to assess the optimal location of the LFS divertor pump to create a stable detachment front between the target and the X-point. The radiation front position in the simulations, taken to be indicative of the detachment front, can be controlled between the pump and X-point in the favorable magnetic field direction for H-mode access by moving the pump duct location upstream of the target along the LFS baffle. In the unfavorable magnetic field direction, the radial Eθ×B drift flows are directed towards the pumping surface, efficiently removing the injected deuterium gas and limiting the sensitivity of the radiation front location to the gas injection rate. The role of pumping rate and drift direction on the pumping efficiency are also found to affect the divertor plasma conditions and detachment front location in UEDGE simulations.

KW - DIII-D

KW - Mid-leg pumping

KW - Plasma drifts

KW - UEDGE

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ER -

Modeling a divertor with mid-leg pumping for high-power H-mode scenarios in DIII-D considering E × B drift flows

Abstract

Funding

Keywords

UN SDGs

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