Predicting tungsten erosion and leakage properties for the new V-shaped small angle slot divertor in DIII-D
Abstract
Impurity transport modeling of the new tungsten (W)-coated, V-shaped small angle slot (SAS) divertor in the DIII-D tokamak was conducted using the SOLPS-ITER plasma edge code package and the DIVIMP impurity tracking code. The inboard baffle of the current SAS divertor will be shifted closer to the outboard baffle, creating a V-corner at the slot vertex. In addition, the outboard baffle will be coated with 10–15 μm of W for experiments studying high-Z sourcing and leakage in a closed divertor. Modeling of the 'SAS-VW' divertor predicts that these changes to the inner baffle will reduce W gross erosion by 40× relative to the existing SAS divertor when the outer strike point (OSP) is at the V-corner and the ion B × ∇B drift is towards the divertor, driven primarily by significant cooling near the slot vertex. Most W erosion in SAS-VW is expected to occur near the slot entrance, which may pose a higher risk to core contamination than W eroded deeper in the slot. Furthermore, adding a new sheath-based prompt redeposition model increases the sensitivity of redeposition estimates to near-target plasma conditions and may provide more accurate predictions of net erosion. Moving the OSP outboard from the slot vertexmore »
- Authors:
-
- General Atomics, San Diego, CA (United States)
- Univ. of Toronto Inst. for Aerospace Studies (Canada)
- General Atomics, San Diego, CA (United States); ENN Science and Technology Development Co., Ltd, Langfang (China)
- Publication Date:
- Research Org.:
- General Atomics, San Diego, CA (United States)
- Sponsoring Org.:
- USDOE Office of Science (SC), Fusion Energy Sciences (FES)
- OSTI Identifier:
- 1971197
- Grant/Contract Number:
- FC02-04ER54698
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Nuclear Fusion
- Additional Journal Information:
- Journal Volume: 62; Journal Issue: 10; Journal ID: ISSN 0029-5515
- Publisher:
- IOP Science
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; plasma-material interactions; SOLPS-ITER; divertor closure; tungsten; erosion; DIII-D
Citation Formats
Sinclair, G., Maurizio, R., Ma, X., Abrams, T., Elder, J. D., Guo, H. Y., Thomas, D. M., and Leonard, A. W. Predicting tungsten erosion and leakage properties for the new V-shaped small angle slot divertor in DIII-D. United States: N. p., 2022.
Web. doi:10.1088/1741-4326/ac8b95.
Sinclair, G., Maurizio, R., Ma, X., Abrams, T., Elder, J. D., Guo, H. Y., Thomas, D. M., & Leonard, A. W. Predicting tungsten erosion and leakage properties for the new V-shaped small angle slot divertor in DIII-D. United States. https://doi.org/10.1088/1741-4326/ac8b95
Sinclair, G., Maurizio, R., Ma, X., Abrams, T., Elder, J. D., Guo, H. Y., Thomas, D. M., and Leonard, A. W. Tue .
"Predicting tungsten erosion and leakage properties for the new V-shaped small angle slot divertor in DIII-D". United States. https://doi.org/10.1088/1741-4326/ac8b95. https://www.osti.gov/servlets/purl/1971197.
@article{osti_1971197,
title = {Predicting tungsten erosion and leakage properties for the new V-shaped small angle slot divertor in DIII-D},
author = {Sinclair, G. and Maurizio, R. and Ma, X. and Abrams, T. and Elder, J. D. and Guo, H. Y. and Thomas, D. M. and Leonard, A. W.},
abstractNote = {Impurity transport modeling of the new tungsten (W)-coated, V-shaped small angle slot (SAS) divertor in the DIII-D tokamak was conducted using the SOLPS-ITER plasma edge code package and the DIVIMP impurity tracking code. The inboard baffle of the current SAS divertor will be shifted closer to the outboard baffle, creating a V-corner at the slot vertex. In addition, the outboard baffle will be coated with 10–15 μm of W for experiments studying high-Z sourcing and leakage in a closed divertor. Modeling of the 'SAS-VW' divertor predicts that these changes to the inner baffle will reduce W gross erosion by 40× relative to the existing SAS divertor when the outer strike point (OSP) is at the V-corner and the ion B × ∇B drift is towards the divertor, driven primarily by significant cooling near the slot vertex. Most W erosion in SAS-VW is expected to occur near the slot entrance, which may pose a higher risk to core contamination than W eroded deeper in the slot. Furthermore, adding a new sheath-based prompt redeposition model increases the sensitivity of redeposition estimates to near-target plasma conditions and may provide more accurate predictions of net erosion. Moving the OSP outboard from the slot vertex ~4 cm onto the W-coated region yields a 40× increase in the gross erosion rate and a 50% decrease in the core leakage fraction. Thus slight variations in strike point location may counteract the potential benefits of the tightly-baffled V slot on minimizing erosion. This impurity transport modeling provides useful guidance for future experiments on the SAS-VW divertor focused on high-Z erosion/redeposition, scrape-off layer transport, and core leakage.},
doi = {10.1088/1741-4326/ac8b95},
journal = {Nuclear Fusion},
number = 10,
volume = 62,
place = {United States},
year = {Tue Sep 13 00:00:00 EDT 2022},
month = {Tue Sep 13 00:00:00 EDT 2022}
}
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