OEDGE modeling of outer wall erosion in NSTX and the effect of changes in neutral pressure

J. H. Nichols; M. A. Jaworski; R. Kaita; T. Abrams; C. H. Skinner; D. P. Stotler

doi:10.1016/j.jnucmat.2014.10.094

OEDGE modeling of outer wall erosion in NSTX and the effect of changes in neutral pressure

J. H. Nichols
, M. A. Jaworski
, R. Kaita
, T. Abrams
, C. H. Skinner
, D. P. Stotler

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

2 Scopus citations

Abstract

Abstract Gross erosion from the outer wall is expected to be a major source of impurities for high power fusion devices due to the low redeposition fraction. Scaling studies of sputtering from the all-carbon outer wall of NSTX are reported. It is found that wall erosion decreases with divertor plasma pressure in low/mid temperature regimes, due to increasing divertor neutral opacity. Wall erosion is found to consistently decrease with reduced recycling coefficient, with outer target recycling providing the largest contribution. Upper and lower bounds are calculated for the increase in wall erosion due to a low-field-side gas puff.

Original language	English
Article number	48591
Pages (from-to)	276-279
Number of pages	4
Journal	Journal of Nuclear Materials
Volume	463
DOIs	https://doi.org/10.1016/j.jnucmat.2014.10.094
State	Published - Jul 22 2015
Externally published	Yes

Funding

This work has been supported by US Dept. of Energy contract DE-AC02-09CH11466 . JHN and TA have been supported in part by the US DOE Fusion Energy Sciences Fellowship .

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10.1016/j.jnucmat.2014.10.094

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title = "OEDGE modeling of outer wall erosion in NSTX and the effect of changes in neutral pressure",

abstract = "Abstract Gross erosion from the outer wall is expected to be a major source of impurities for high power fusion devices due to the low redeposition fraction. Scaling studies of sputtering from the all-carbon outer wall of NSTX are reported. It is found that wall erosion decreases with divertor plasma pressure in low/mid temperature regimes, due to increasing divertor neutral opacity. Wall erosion is found to consistently decrease with reduced recycling coefficient, with outer target recycling providing the largest contribution. Upper and lower bounds are calculated for the increase in wall erosion due to a low-field-side gas puff.",

author = "Nichols, \{J. H.\} and Jaworski, \{M. A.\} and R. Kaita and T. Abrams and Skinner, \{C. H.\} and Stotler, \{D. P.\}",

note = "Publisher Copyright: {\textcopyright} 2014 Elsevier B.V.",

year = "2015",

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doi = "10.1016/j.jnucmat.2014.10.094",

language = "English",

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T1 - OEDGE modeling of outer wall erosion in NSTX and the effect of changes in neutral pressure

AU - Nichols, J. H.

AU - Jaworski, M. A.

AU - Kaita, R.

AU - Abrams, T.

AU - Skinner, C. H.

AU - Stotler, D. P.

PY - 2015/7/22

Y1 - 2015/7/22

N2 - Abstract Gross erosion from the outer wall is expected to be a major source of impurities for high power fusion devices due to the low redeposition fraction. Scaling studies of sputtering from the all-carbon outer wall of NSTX are reported. It is found that wall erosion decreases with divertor plasma pressure in low/mid temperature regimes, due to increasing divertor neutral opacity. Wall erosion is found to consistently decrease with reduced recycling coefficient, with outer target recycling providing the largest contribution. Upper and lower bounds are calculated for the increase in wall erosion due to a low-field-side gas puff.

AB - Abstract Gross erosion from the outer wall is expected to be a major source of impurities for high power fusion devices due to the low redeposition fraction. Scaling studies of sputtering from the all-carbon outer wall of NSTX are reported. It is found that wall erosion decreases with divertor plasma pressure in low/mid temperature regimes, due to increasing divertor neutral opacity. Wall erosion is found to consistently decrease with reduced recycling coefficient, with outer target recycling providing the largest contribution. Upper and lower bounds are calculated for the increase in wall erosion due to a low-field-side gas puff.

UR - https://www.scopus.com/pages/publications/84937735130

U2 - 10.1016/j.jnucmat.2014.10.094

DO - 10.1016/j.jnucmat.2014.10.094

M3 - Article

AN - SCOPUS:84937735130

SN - 0022-3115

VL - 463

SP - 276

EP - 279

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

M1 - 48591

ER -

OEDGE modeling of outer wall erosion in NSTX and the effect of changes in neutral pressure

Abstract

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