DiMES contributions to PMI understanding

C. P C Wong, D. G. Whyte, R. Bastasz, W. Wampler, J. N. Brooks, T. E. Evans, W. P. West, J. Whaley, R. Doerner, J. Watkins, J. P. Allain, A. Hassanein, D. Rudakov

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Abstract

The Divertor Materials Evaluation System (DiMES) program at General Atomics has been using a sample changer mechanism to expose different plasma-facing materials to the lower divertor of DIII-D to study integrated plasma materials interaction effects in a tokamak and to benchmark modeling codes. We found that for carbon divertor plates, a detached plasma eliminates net erosion in DIII-D. A spectroscopic study of chemical sputtering Indicated the potential improvement of erosion arising from the aging of the first wall material. We also found the importance of the carbon source from the first wall of DIII-D. When lithium was exposed at the divertor we found significant and complicated MHD interactions between the scrape-off layer current in a tokamak and the conducting liquid. This paper is a report on what we have learned and what we plan to do in response to the needs for the plasma facing components (PFC) design for advanced tokamak machines like ITER. Our plan for the study of liquid surface interaction with the plasma will also be presented.

Original languageEnglish (US)
Title of host publication20th IEEE/NPSS Symposium on Fusion Engineering, SOFE 03
Pages236-241
Number of pages6
StatePublished - 2003
Externally publishedYes
Event20th IEEE/NPSS Symposium on Fusion Engineering, SOFE 03 - San Diego, CA, United States

Other

Other20th IEEE/NPSS Symposium on Fusion Engineering, SOFE 03
CountryUnited States
CitySan Diego, CA
Period10/14/0310/17/03

Fingerprint

Plasmas
Beam plasma interactions
Erosion
Carbon
Liquids
erosion
evaluation
carbon
interactions
Facings
Magnetohydrodynamics
Sputtering
Lithium
liquid surfaces
surface reactions
lithium
sputtering
conduction
liquids

ASJC Scopus subject areas

  • Nuclear and High Energy Physics
  • Nuclear Energy and Engineering

Cite this

Wong, C. P. C., Whyte, D. G., Bastasz, R., Wampler, W., Brooks, J. N., Evans, T. E., ... Rudakov, D. (2003). DiMES contributions to PMI understanding. In 20th IEEE/NPSS Symposium on Fusion Engineering, SOFE 03 (pp. 236-241)

DiMES contributions to PMI understanding. / Wong, C. P C; Whyte, D. G.; Bastasz, R.; Wampler, W.; Brooks, J. N.; Evans, T. E.; West, W. P.; Whaley, J.; Doerner, R.; Watkins, J.; Allain, J. P.; Hassanein, A.; Rudakov, D.

20th IEEE/NPSS Symposium on Fusion Engineering, SOFE 03. 2003. p. 236-241.

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Wong, CPC, Whyte, DG, Bastasz, R, Wampler, W, Brooks, JN, Evans, TE, West, WP, Whaley, J, Doerner, R, Watkins, J, Allain, JP, Hassanein, A & Rudakov, D 2003, DiMES contributions to PMI understanding. in 20th IEEE/NPSS Symposium on Fusion Engineering, SOFE 03. pp. 236-241, 20th IEEE/NPSS Symposium on Fusion Engineering, SOFE 03, San Diego, CA, United States, 14-17 October.
Wong CPC, Whyte DG, Bastasz R, Wampler W, Brooks JN, Evans TE et al. DiMES contributions to PMI understanding. In 20th IEEE/NPSS Symposium on Fusion Engineering, SOFE 03. 2003. p. 236-241.

Wong, C. P C; Whyte, D. G.; Bastasz, R.; Wampler, W.; Brooks, J. N.; Evans, T. E.; West, W. P.; Whaley, J.; Doerner, R.; Watkins, J.; Allain, J. P.; Hassanein, A.; Rudakov, D. / DiMES contributions to PMI understanding.

20th IEEE/NPSS Symposium on Fusion Engineering, SOFE 03. 2003. p. 236-241.

Research output: Chapter in Book/Report/Conference proceedingConference contribution

@inbook{2276760c2c5840619b1bd11731810c0b,
title = "DiMES contributions to PMI understanding",
abstract = "The Divertor Materials Evaluation System (DiMES) program at General Atomics has been using a sample changer mechanism to expose different plasma-facing materials to the lower divertor of DIII-D to study integrated plasma materials interaction effects in a tokamak and to benchmark modeling codes. We found that for carbon divertor plates, a detached plasma eliminates net erosion in DIII-D. A spectroscopic study of chemical sputtering Indicated the potential improvement of erosion arising from the aging of the first wall material. We also found the importance of the carbon source from the first wall of DIII-D. When lithium was exposed at the divertor we found significant and complicated MHD interactions between the scrape-off layer current in a tokamak and the conducting liquid. This paper is a report on what we have learned and what we plan to do in response to the needs for the plasma facing components (PFC) design for advanced tokamak machines like ITER. Our plan for the study of liquid surface interaction with the plasma will also be presented.",
author = "Wong, {C. P C} and Whyte, {D. G.} and R. Bastasz and W. Wampler and Brooks, {J. N.} and Evans, {T. E.} and West, {W. P.} and J. Whaley and R. Doerner and J. Watkins and Allain, {J. P.} and A. Hassanein and D. Rudakov",
year = "2003",
pages = "236--241",
booktitle = "20th IEEE/NPSS Symposium on Fusion Engineering, SOFE 03",

}

TY - CHAP

T1 - DiMES contributions to PMI understanding

AU - Wong,C. P C

AU - Whyte,D. G.

AU - Bastasz,R.

AU - Wampler,W.

AU - Brooks,J. N.

AU - Evans,T. E.

AU - West,W. P.

AU - Whaley,J.

AU - Doerner,R.

AU - Watkins,J.

AU - Allain,J. P.

AU - Hassanein,A.

AU - Rudakov,D.

PY - 2003

Y1 - 2003

N2 - The Divertor Materials Evaluation System (DiMES) program at General Atomics has been using a sample changer mechanism to expose different plasma-facing materials to the lower divertor of DIII-D to study integrated plasma materials interaction effects in a tokamak and to benchmark modeling codes. We found that for carbon divertor plates, a detached plasma eliminates net erosion in DIII-D. A spectroscopic study of chemical sputtering Indicated the potential improvement of erosion arising from the aging of the first wall material. We also found the importance of the carbon source from the first wall of DIII-D. When lithium was exposed at the divertor we found significant and complicated MHD interactions between the scrape-off layer current in a tokamak and the conducting liquid. This paper is a report on what we have learned and what we plan to do in response to the needs for the plasma facing components (PFC) design for advanced tokamak machines like ITER. Our plan for the study of liquid surface interaction with the plasma will also be presented.

AB - The Divertor Materials Evaluation System (DiMES) program at General Atomics has been using a sample changer mechanism to expose different plasma-facing materials to the lower divertor of DIII-D to study integrated plasma materials interaction effects in a tokamak and to benchmark modeling codes. We found that for carbon divertor plates, a detached plasma eliminates net erosion in DIII-D. A spectroscopic study of chemical sputtering Indicated the potential improvement of erosion arising from the aging of the first wall material. We also found the importance of the carbon source from the first wall of DIII-D. When lithium was exposed at the divertor we found significant and complicated MHD interactions between the scrape-off layer current in a tokamak and the conducting liquid. This paper is a report on what we have learned and what we plan to do in response to the needs for the plasma facing components (PFC) design for advanced tokamak machines like ITER. Our plan for the study of liquid surface interaction with the plasma will also be presented.

UR - http://www.scopus.com/inward/record.url?scp=27644485072&partnerID=8YFLogxK

UR - http://www.scopus.com/inward/citedby.url?scp=27644485072&partnerID=8YFLogxK

M3 - Conference contribution

SP - 236

EP - 241

BT - 20th IEEE/NPSS Symposium on Fusion Engineering, SOFE 03

ER -