Model validation of tungsten erosion and redeposition properties using biased tungsten samples on DiMES

L. Cappelli; J. Guterl; N. Fedorczak; D. L. Rudakov; G. Sinclair; T. Abrams; S. Di Genova; U. Losada; I. Bykov; Popović; D. Truong; J. Watkins; R. S. Wilcox; W. R. Wampler; E. Serre

doi:10.1016/j.nme.2023.101551

Model validation of tungsten erosion and redeposition properties using biased tungsten samples on DiMES

L. Cappelli, J. Guterl, N. Fedorczak, D. L. Rudakov, G. Sinclair, T. Abrams, S. Di Genova, U. Losada, I. Bykov, Popović, D. Truong, J. Watkins, R. S. Wilcox, W. R. Wampler, E. Serre

Advanced Tokamak Physics

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

Abstract

An experiment was performed in the DIII-D lower divertor to validate numerical SOL tungsten (W) impurity erosion and redeposition simulations against experimental data. The net and gross erosion of W were calculated as a function of the voltage (or bias) applied to the exposed material. Five samples were inserted into the DIII-D lower divertor using the Divertor Material Evaluation System (DiMES) manipulator and exposed to constant L-mode attached plasma conditions. Each sample was partially coated with W. During plasma shots, samples were biased with respect to the machine vessel ground, ranging from −60 V to 25 V. The ERO2.0 code was used to numerically simulate the experiment aiming to compare the numerical results with experimental measures. A good agreement is found between estimated and measured tungsten erosion at least for negative biases.

Original language	English
Article number	101551
Journal	Nuclear Materials and Energy
Volume	37
DOIs	https://doi.org/10.1016/j.nme.2023.101551
State	Published - Dec 2023

Funding

This work has been supported by the French National Research Agency grant SISTEM ( ANR-19-CE46-0005-03 ) and has received funding from the Excellence Initiative of Aix-Marseille University - A*Midex, a French “Investissements d’Avenir” program AMX-19-IET-013 . This work has been carried out within the framework of the EUROfusion Consortium, funded by the European Union via the Euratom Research and Training Programme (Grant Agreement No 101052200 - EUROfusion). Views and opinions expressed are however those of the authors only and do not necessarily reflect those of the European Union or the European Commission. Neither the European Union nor the European Commission can be held responsible for them. This material is based upon work supported by the U.S. Department of Energy, Office of Science, Office of Fusion Energy Sciences , using the DIII-D National Fusion Facility, a DOE Office of Science user facility, under Awards DE-SC0018423 and DE-FC02-04ER54698 ”. This work has been supported by the French National Research Agency grant SISTEM (ANR-19-CE46-0005-03) and has received funding from the Excellence Initiative of Aix-Marseille University - A*Midex, a French “Investissements d'Avenir” program AMX-19-IET-013. This work has been carried out within the framework of the EUROfusion Consortium, funded by the European Union via the Euratom Research and Training Programme (Grant Agreement No 101052200 - EUROfusion). Views and opinions expressed are however those of the authors only and do not necessarily reflect those of the European Union or the European Commission. Neither the European Union nor the European Commission can be held responsible for them. This material is based upon work supported by the U.S. Department of Energy, Office of Science, Office of Fusion Energy Sciences, using the DIII-D National Fusion Facility, a DOE Office of Science user facility, under Awards DE-SC0018423 and DE-FC02-04ER54698”. 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.

Keywords

Bias
ERO2.0
Erosion
Redeposition
Tungsten

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10.1016/j.nme.2023.101551

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Cappelli, L., Guterl, J., Fedorczak, N., Rudakov, D. L., Sinclair, G., Abrams, T., Di Genova, S., Losada, U., Bykov, I., Popović, Truong, D., Watkins, J., Wilcox, R. S., Wampler, W. R., & Serre, E. (2023). Model validation of tungsten erosion and redeposition properties using biased tungsten samples on DiMES. Nuclear Materials and Energy, 37, Article 101551. https://doi.org/10.1016/j.nme.2023.101551

@article{2ded066428594cb785bf9cd43366684e,

title = "Model validation of tungsten erosion and redeposition properties using biased tungsten samples on DiMES",

abstract = "An experiment was performed in the DIII-D lower divertor to validate numerical SOL tungsten (W) impurity erosion and redeposition simulations against experimental data. The net and gross erosion of W were calculated as a function of the voltage (or bias) applied to the exposed material. Five samples were inserted into the DIII-D lower divertor using the Divertor Material Evaluation System (DiMES) manipulator and exposed to constant L-mode attached plasma conditions. Each sample was partially coated with W. During plasma shots, samples were biased with respect to the machine vessel ground, ranging from −60 V to 25 V. The ERO2.0 code was used to numerically simulate the experiment aiming to compare the numerical results with experimental measures. A good agreement is found between estimated and measured tungsten erosion at least for negative biases.",

keywords = "Bias, ERO2.0, Erosion, Redeposition, Tungsten",

author = "L. Cappelli and J. Guterl and N. Fedorczak and Rudakov, \{D. L.\} and G. Sinclair and T. Abrams and \{Di Genova\}, S. and U. Losada and I. Bykov and Popovi{\'c} and D. Truong and J. Watkins and Wilcox, \{R. S.\} and Wampler, \{W. R.\} and E. Serre",

note = "Publisher Copyright: {\textcopyright} 2023",

year = "2023",

month = dec,

doi = "10.1016/j.nme.2023.101551",

language = "English",

volume = "37",

journal = "Nuclear Materials and Energy",

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Cappelli, L, Guterl, J, Fedorczak, N, Rudakov, DL, Sinclair, G, Abrams, T, Di Genova, S, Losada, U, Bykov, I, Popović, Truong, D, Watkins, J, Wilcox, RS, Wampler, WR & Serre, E 2023, 'Model validation of tungsten erosion and redeposition properties using biased tungsten samples on DiMES', Nuclear Materials and Energy, vol. 37, 101551. https://doi.org/10.1016/j.nme.2023.101551

TY - JOUR

T1 - Model validation of tungsten erosion and redeposition properties using biased tungsten samples on DiMES

AU - Cappelli, L.

AU - Guterl, J.

AU - Fedorczak, N.

AU - Rudakov, D. L.

AU - Sinclair, G.

AU - Abrams, T.

AU - Di Genova, S.

AU - Losada, U.

AU - Bykov, I.

AU - Popović,

AU - Truong, D.

AU - Watkins, J.

AU - Wilcox, R. S.

AU - Wampler, W. R.

AU - Serre, E.

PY - 2023/12

Y1 - 2023/12

N2 - An experiment was performed in the DIII-D lower divertor to validate numerical SOL tungsten (W) impurity erosion and redeposition simulations against experimental data. The net and gross erosion of W were calculated as a function of the voltage (or bias) applied to the exposed material. Five samples were inserted into the DIII-D lower divertor using the Divertor Material Evaluation System (DiMES) manipulator and exposed to constant L-mode attached plasma conditions. Each sample was partially coated with W. During plasma shots, samples were biased with respect to the machine vessel ground, ranging from −60 V to 25 V. The ERO2.0 code was used to numerically simulate the experiment aiming to compare the numerical results with experimental measures. A good agreement is found between estimated and measured tungsten erosion at least for negative biases.

AB - An experiment was performed in the DIII-D lower divertor to validate numerical SOL tungsten (W) impurity erosion and redeposition simulations against experimental data. The net and gross erosion of W were calculated as a function of the voltage (or bias) applied to the exposed material. Five samples were inserted into the DIII-D lower divertor using the Divertor Material Evaluation System (DiMES) manipulator and exposed to constant L-mode attached plasma conditions. Each sample was partially coated with W. During plasma shots, samples were biased with respect to the machine vessel ground, ranging from −60 V to 25 V. The ERO2.0 code was used to numerically simulate the experiment aiming to compare the numerical results with experimental measures. A good agreement is found between estimated and measured tungsten erosion at least for negative biases.

KW - Bias

KW - ERO2.0

KW - Erosion

KW - Redeposition

KW - Tungsten

UR - https://www.scopus.com/pages/publications/85176418650

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DO - 10.1016/j.nme.2023.101551

M3 - Article

AN - SCOPUS:85176418650

SN - 2352-1791

VL - 37

JO - Nuclear Materials and Energy

JF - Nuclear Materials and Energy

M1 - 101551

ER -

Model validation of tungsten erosion and redeposition properties using biased tungsten samples on DiMES

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Keywords

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