Advances in understanding of high- Z material erosion and re-deposition in low- Z wall environment in DIII-D
Abstract
Dedicated DIII-D experiments coupled with modeling reveal that the net erosion rate of high-Z materials, i.e. Mo and W, is strongly affected by carbon concentration in the plasma and the magnetic pre-sheath properties. We have investigated different methods such as electrical biasing and local gas injection to control high-Z material erosion. The net erosion rate of high-Z materials is significantly reduced due to the high local re-deposition ratio. The ERO modeling shows that the local re-deposition ratio is mainly controlled by the electric field and plasma density within the magnetic pre-sheath. The net erosion can be significantly suppressed by reducing the sheath potential drop. A high carbon impurity concentration in the background plasma is also found to reduce the net erosion rate of high-Z materials. Both DIII-D experiments and modeling show that local 13CH 4 injection can create a carbon coating on the metal surface. The profile of 13C deposition provides quantitative information on radial transport due to E × B drift and the cross-field diffusion. The deuterium gas injection upstream of the W sample can reduce W net erosion rate by plasma perturbation. The inter-ELM W erosion we measured in H-mode plasmas, rates at different radial locations are wellmore »
- Authors:
- more »
- Publication Date:
- Research Org.:
- Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); General Atomics, San Diego, CA (United States); Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Org.:
- USDOE National Nuclear Security Administration (NNSA); USDOE Office of Science (SC), Fusion Energy Sciences (FES) (SC-24)
- OSTI Identifier:
- 1491638
- Alternate Identifier(s):
- OSTI ID: 1357016; OSTI ID: 1374606; OSTI ID: 1374610; OSTI ID: 1503985
- Report Number(s):
- SAND-2017-0016J; LLNL-JRNL-736452
Journal ID: ISSN 0029-5515; 650168
- Grant/Contract Number:
- AC04-94AL85000; GA-DE-SC0008698; AC05-06OR23100; FG02-07ER54917; AC05-00OR22725; FC02-04ER54698; AC52-07NA27344
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Nuclear Fusion
- Additional Journal Information:
- Journal Volume: 57; Journal Issue: 5; Journal ID: ISSN 0029-5515
- Publisher:
- IOP Science
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; erosion; deposition; high-Z materials; impurity
Citation Formats
Ding, R., Rudakov, D. L., Stangeby, P. C., Wampler, W. R., Abrams, T., Brezinsek, S., Briesemeister, A., Bykov, I., Chan, V. S., Chrobak, C. P., Elder, J. D., Guo, H. Y., Guterl, J., Kirschner, A., Lasnier, C. J., Leonard, A. W., Makowski, M. A., McLean, A. G., Snyder, P. B., Thomas, D. M., Tskhakaya, D., Unterberg, E. A., Wang, H. Q., and Watkins, J. G. Advances in understanding of high- Z material erosion and re-deposition in low- Z wall environment in DIII-D. United States: N. p., 2017.
Web. doi:10.1088/1741-4326/aa6451.
Ding, R., Rudakov, D. L., Stangeby, P. C., Wampler, W. R., Abrams, T., Brezinsek, S., Briesemeister, A., Bykov, I., Chan, V. S., Chrobak, C. P., Elder, J. D., Guo, H. Y., Guterl, J., Kirschner, A., Lasnier, C. J., Leonard, A. W., Makowski, M. A., McLean, A. G., Snyder, P. B., Thomas, D. M., Tskhakaya, D., Unterberg, E. A., Wang, H. Q., & Watkins, J. G. Advances in understanding of high- Z material erosion and re-deposition in low- Z wall environment in DIII-D. United States. doi:10.1088/1741-4326/aa6451.
Ding, R., Rudakov, D. L., Stangeby, P. C., Wampler, W. R., Abrams, T., Brezinsek, S., Briesemeister, A., Bykov, I., Chan, V. S., Chrobak, C. P., Elder, J. D., Guo, H. Y., Guterl, J., Kirschner, A., Lasnier, C. J., Leonard, A. W., Makowski, M. A., McLean, A. G., Snyder, P. B., Thomas, D. M., Tskhakaya, D., Unterberg, E. A., Wang, H. Q., and Watkins, J. G. Fri .
"Advances in understanding of high- Z material erosion and re-deposition in low- Z wall environment in DIII-D". United States. doi:10.1088/1741-4326/aa6451. https://www.osti.gov/servlets/purl/1491638.
@article{osti_1491638,
title = {Advances in understanding of high- Z material erosion and re-deposition in low- Z wall environment in DIII-D},
author = {Ding, R. and Rudakov, D. L. and Stangeby, P. C. and Wampler, W. R. and Abrams, T. and Brezinsek, S. and Briesemeister, A. and Bykov, I. and Chan, V. S. and Chrobak, C. P. and Elder, J. D. and Guo, H. Y. and Guterl, J. and Kirschner, A. and Lasnier, C. J. and Leonard, A. W. and Makowski, M. A. and McLean, A. G. and Snyder, P. B. and Thomas, D. M. and Tskhakaya, D. and Unterberg, E. A. and Wang, H. Q. and Watkins, J. G.},
abstractNote = {Dedicated DIII-D experiments coupled with modeling reveal that the net erosion rate of high-Z materials, i.e. Mo and W, is strongly affected by carbon concentration in the plasma and the magnetic pre-sheath properties. We have investigated different methods such as electrical biasing and local gas injection to control high-Z material erosion. The net erosion rate of high-Z materials is significantly reduced due to the high local re-deposition ratio. The ERO modeling shows that the local re-deposition ratio is mainly controlled by the electric field and plasma density within the magnetic pre-sheath. The net erosion can be significantly suppressed by reducing the sheath potential drop. A high carbon impurity concentration in the background plasma is also found to reduce the net erosion rate of high-Z materials. Both DIII-D experiments and modeling show that local 13CH4 injection can create a carbon coating on the metal surface. The profile of 13C deposition provides quantitative information on radial transport due to E × B drift and the cross-field diffusion. The deuterium gas injection upstream of the W sample can reduce W net erosion rate by plasma perturbation. The inter-ELM W erosion we measured in H-mode plasmas, rates at different radial locations are well reproduced by ERO modeling taking into account charge-state-resolved carbon ion flux in the background plasma calculated using the OEDGE code.},
doi = {10.1088/1741-4326/aa6451},
journal = {Nuclear Fusion},
number = 5,
volume = 57,
place = {United States},
year = {2017},
month = {3}
}
Web of Science
Figures / Tables:

Figures / Tables found in this record: