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Title: Plasma Surface Interactions: Bridging from the Surface to the Micron Frontier through Leadership Class Computing (Final Technical Report)

Abstract

The development of magnetic fusion energy requires compatibility between plasmas heated to temperatures much hotter than the sun, and material surfaces which surround the plasma and must survive long term without undue erosion. The goal of the Plasma Surface Interactions (PSI) SciDAC project was to develop robust, high-fidelity simulation tools capable of predicting the plasma facing component (PFC) operating lifetime and the PFC impact on plasma contamination, recycling of hydrogenic species, and tritium retention in future magnetic fusion devices, with a focus on tungsten based material systems. An important aspect of this robust validation of simulation results against observations, including those on the DIII-D and EAST tokamaks. The General Atomics PSI SciDAC project has assembled and extended a database of tokamak plasms material interface (PMI) data, assisted in planning and carrying out experiments appropriate for validation of PSI SciDAC codes, and performed validation using state-of-the-art PMI modeling codes, such as the ERO code. A major activity has been using ERO simulations to understand and control high-Z material erosion in the DIII-D divertor. These simulations have found good agreement with multiple observations of net and gross erosion, and identified the importance of the sheath electric field in erosion/redeposition. They have alsomore » enabled development of techniques to minimize net material erosion. For example, dedicated experiments on DIII-D, guided by ERO simulation results, have been undertaken to further study the role of carbon impurity concentration and sheath potential, yielding important new insights, including methods for substantially reducing high-Z material erosion.« less

Authors:
 [1];  [1]
  1. General Atomics, San Diego, CA (United States)
Publication Date:
Research Org.:
General Atomics, San Diego, CA (United States)
Sponsoring Org.:
USDOE Office of Science (SC), Fusion Energy Sciences (FES)
OSTI Identifier:
1577347
Report Number(s):
DOE-GA-0008698
30391
DOE Contract Number:  
SC0008698
Resource Type:
Technical Report
Resource Relation:
Related Information: R. Ding, P.C. Stangeby, D.L. Rudakov, J.D. Elder, D. Tskhakaya, W.R. Wampler, A. Kirschner, A.G. McLean, H.Y. Guo, V.S. Chan and P.B. Snyder. “Simulation of gross and net erosion of high-Z materials in the DIII-D divertor,” Nuclear Fusion 56 (2016) 016021D.L. Rudakov, T. Abrams, R. Ding, H.Y. Guo, P.C. Stangeby, W.R. Wampler et al., “DiMES PMI Research at DIII-D in Support of ITER and Beyond,” Fusion Engineering and Design 124 196 (2017).R. Ding, D.L. Rudakov, P.C. Stangeby, W.R. Wampler, T. Abrams, S. Brezinsek, A. Briesemeister, I. Bykov, V.S. Chan, C.P. Chrobak, J.D. Elder, H.Y. Guo, J. Guterl, A. Kirschner, C.J. Lasnier, A.W. Leonard, M.A. Makowski, A.G. McLean, P.B. Snyder, D.M. Thomas, D. Tskhakaya, E.A. Unterberg, H.Q. Wang and J.G. Watkins, “Advances in understanding of high-Z material erosion and re-deposition in low-Z wall environment in DIII-D,” Nuclear Fusion 57 056016 (2017).R. Ding, D.L. Rudakov, P.C. Stangeby, W.R. Wampler, T. Abrams, S. Brezinsek, A. Briesemeister, I. Bykov, V.S. Chan, C.P. Chrobak, J.D. Elder, H.Y. Guo, J. Guterl, A. Kirschner, C.J. Lasnier, A.W. Leonard, M.A. Makowski, A.G. McLean, P.B. Snyder, D.M. Thomas, D. Tskhakaya, E.A. Unterberg, H.Q. Wang and J.G. Watkins, “High Z material erosion and its control in DIII-D carbon divertor,” Nuclear Materials and Energy 12 247 (2017).T. Abrams, R. Ding, H.Y. Guo, D.M. Thomas, C.P. Chrobak, D.L. Rudakov, A.G. McLean, E.A. Unterberg, A.R. Briesemeister, P.C. Stangeby, J.D. Elder, W.R. Wampler and J.G. Watkins, “The inter-ELM tungsten erosion profile in DIII-D H-mode discharges and benchmarking with ERO+OEDGE modeling,” Nuclear Fusion 57 056034 (2017).
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; Plasma Surface Interaction

Citation Formats

Snyder, Philip, and Ding, Rui. Plasma Surface Interactions: Bridging from the Surface to the Micron Frontier through Leadership Class Computing (Final Technical Report). United States: N. p., 2020. Web.
Snyder, Philip, & Ding, Rui. Plasma Surface Interactions: Bridging from the Surface to the Micron Frontier through Leadership Class Computing (Final Technical Report). United States.
Snyder, Philip, and Ding, Rui. 2020. "Plasma Surface Interactions: Bridging from the Surface to the Micron Frontier through Leadership Class Computing (Final Technical Report)". United States.
@article{osti_1577347,
title = {Plasma Surface Interactions: Bridging from the Surface to the Micron Frontier through Leadership Class Computing (Final Technical Report)},
author = {Snyder, Philip and Ding, Rui},
abstractNote = {The development of magnetic fusion energy requires compatibility between plasmas heated to temperatures much hotter than the sun, and material surfaces which surround the plasma and must survive long term without undue erosion. The goal of the Plasma Surface Interactions (PSI) SciDAC project was to develop robust, high-fidelity simulation tools capable of predicting the plasma facing component (PFC) operating lifetime and the PFC impact on plasma contamination, recycling of hydrogenic species, and tritium retention in future magnetic fusion devices, with a focus on tungsten based material systems. An important aspect of this robust validation of simulation results against observations, including those on the DIII-D and EAST tokamaks. The General Atomics PSI SciDAC project has assembled and extended a database of tokamak plasms material interface (PMI) data, assisted in planning and carrying out experiments appropriate for validation of PSI SciDAC codes, and performed validation using state-of-the-art PMI modeling codes, such as the ERO code. A major activity has been using ERO simulations to understand and control high-Z material erosion in the DIII-D divertor. These simulations have found good agreement with multiple observations of net and gross erosion, and identified the importance of the sheath electric field in erosion/redeposition. They have also enabled development of techniques to minimize net material erosion. For example, dedicated experiments on DIII-D, guided by ERO simulation results, have been undertaken to further study the role of carbon impurity concentration and sheath potential, yielding important new insights, including methods for substantially reducing high-Z material erosion.},
doi = {},
url = {https://www.osti.gov/biblio/1577347}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue Jan 07 00:00:00 EST 2020},
month = {Tue Jan 07 00:00:00 EST 2020}
}

Technical Report:
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