"Snowflake" divertor configuration in NSTX

V. A. Soukhanovskii; J. W. Ahn; R. E. Bell; D. A. Gates; S. Gerhardt; R. Kaita; E. Kolemen; H. W. Kugel; B. P. Leblanc; R. Maingi; R. Maqueda; A. McLean; J. E. Menard; D. M. Mueller; S. F. Paul; R. Raman; A. L. Roquemore; D. D. Ryutov; H. A. Scott

doi:10.1016/j.jnucmat.2010.07.047

"Snowflake" divertor configuration in NSTX

V. A. Soukhanovskii
, J. W. Ahn
, R. E. Bell
, D. A. Gates
, S. Gerhardt
, R. Kaita
, E. Kolemen
, H. W. Kugel
, B. P. Leblanc
, R. Maingi
, R. Maqueda
, A. McLean
, J. E. Menard
, D. M. Mueller
, S. F. Paul
, R. Raman
, A. L. Roquemore
, D. D. Ryutov
, H. A. Scott

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

30 Scopus citations

Abstract

Steady-state handling of divertor heat flux is a critical issue for present and future conventional and spherical tokamaks with compact high power density divertors. A novel "snowflake" divertor (SFD) configuration that takes advantage of magnetic properties of a second-order poloidal null has been predicted to have a larger plasma-wetted area and a larger divertor volume, in comparison with a standard first-order poloidal X-point divertor configuration. The SFD was obtained in 0.8 MA, 4-6 MW NBI-heated H-mode discharges in NSTX using two divertor magnetic coils. The SFD led to a partial detachment of the outer strike point even in low-collisionality scrape-off layer plasma obtained with lithium coatings in NSTX. Significant divertor peak heat flux reduction and impurity screening have been achieved simultaneously with good core confinement and MHD properties.

Original language	English (US)
Pages (from-to)	S365-S368
Journal	Journal of Nuclear Materials
Volume	415
Issue number	1 SUPPL
DOIs	https://doi.org/10.1016/j.jnucmat.2010.07.047
State	Published - Aug 1 2011

All Science Journal Classification (ASJC) codes

Nuclear and High Energy Physics
General Materials Science
Nuclear Energy and Engineering

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10.1016/j.jnucmat.2010.07.047

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Soukhanovskii, V. A., Ahn, J. W., Bell, R. E., Gates, D. A., Gerhardt, S., Kaita, R., Kolemen, E., Kugel, H. W., Leblanc, B. P., Maingi, R., Maqueda, R., McLean, A., Menard, J. E., Mueller, D. M., Paul, S. F., Raman, R., Roquemore, A. L., Ryutov, D. D., & Scott, H. A. (2011). "Snowflake" divertor configuration in NSTX. Journal of Nuclear Materials, 415(1 SUPPL), S365-S368. https://doi.org/10.1016/j.jnucmat.2010.07.047

@article{89a993bf07ef459792235d033766fc5c,

title = "{"}Snowflake{"} divertor configuration in NSTX",

abstract = "Steady-state handling of divertor heat flux is a critical issue for present and future conventional and spherical tokamaks with compact high power density divertors. A novel {"}snowflake{"} divertor (SFD) configuration that takes advantage of magnetic properties of a second-order poloidal null has been predicted to have a larger plasma-wetted area and a larger divertor volume, in comparison with a standard first-order poloidal X-point divertor configuration. The SFD was obtained in 0.8 MA, 4-6 MW NBI-heated H-mode discharges in NSTX using two divertor magnetic coils. The SFD led to a partial detachment of the outer strike point even in low-collisionality scrape-off layer plasma obtained with lithium coatings in NSTX. Significant divertor peak heat flux reduction and impurity screening have been achieved simultaneously with good core confinement and MHD properties.",

author = "Soukhanovskii, \{V. A.\} and Ahn, \{J. W.\} and Bell, \{R. E.\} and Gates, \{D. A.\} and S. Gerhardt and R. Kaita and E. Kolemen and Kugel, \{H. W.\} and Leblanc, \{B. P.\} and R. Maingi and R. Maqueda and A. McLean and Menard, \{J. E.\} and Mueller, \{D. M.\} and Paul, \{S. F.\} and R. Raman and Roquemore, \{A. L.\} and Ryutov, \{D. D.\} and Scott, \{H. A.\}",

note = "Funding Information: We thank the entire NSTX Team for technical, engineering and computer support and plasma, NBI and diagnostic operations. This work was performed under the auspices of the US Department of Energy under Contracts DE-AC52-07NA27344, DE-AC02-09CH11466, DE-AC05-00OR22725, W-7405-ENG-36, and DE-FG02-04ER54758. ",

year = "2011",

month = aug,

day = "1",

doi = "10.1016/j.jnucmat.2010.07.047",

language = "English (US)",

volume = "415",

pages = "S365--S368",

journal = "Journal of Nuclear Materials",

issn = "0022-3115",

publisher = "Elsevier B.V.",

number = "1 SUPPL",

}

Soukhanovskii, VA, Ahn, JW, Bell, RE, Gates, DA, Gerhardt, S, Kaita, R, Kolemen, E, Kugel, HW, Leblanc, BP , Maingi, R, Maqueda, R, McLean, A, Menard, JE, Mueller, DM, Paul, SF, Raman, R, Roquemore, AL, Ryutov, DD & Scott, HA 2011, '"Snowflake" divertor configuration in NSTX', Journal of Nuclear Materials, vol. 415, no. 1 SUPPL, pp. S365-S368. https://doi.org/10.1016/j.jnucmat.2010.07.047

TY - JOUR

T1 - "Snowflake" divertor configuration in NSTX

AU - Soukhanovskii, V. A.

AU - Ahn, J. W.

AU - Bell, R. E.

AU - Gates, D. A.

AU - Gerhardt, S.

AU - Kaita, R.

AU - Kolemen, E.

AU - Kugel, H. W.

AU - Leblanc, B. P.

AU - Maingi, R.

AU - Maqueda, R.

AU - McLean, A.

AU - Menard, J. E.

AU - Mueller, D. M.

AU - Paul, S. F.

AU - Raman, R.

AU - Roquemore, A. L.

AU - Ryutov, D. D.

AU - Scott, H. A.

N1 - Funding Information: We thank the entire NSTX Team for technical, engineering and computer support and plasma, NBI and diagnostic operations. This work was performed under the auspices of the US Department of Energy under Contracts DE-AC52-07NA27344, DE-AC02-09CH11466, DE-AC05-00OR22725, W-7405-ENG-36, and DE-FG02-04ER54758.

PY - 2011/8/1

Y1 - 2011/8/1

N2 - Steady-state handling of divertor heat flux is a critical issue for present and future conventional and spherical tokamaks with compact high power density divertors. A novel "snowflake" divertor (SFD) configuration that takes advantage of magnetic properties of a second-order poloidal null has been predicted to have a larger plasma-wetted area and a larger divertor volume, in comparison with a standard first-order poloidal X-point divertor configuration. The SFD was obtained in 0.8 MA, 4-6 MW NBI-heated H-mode discharges in NSTX using two divertor magnetic coils. The SFD led to a partial detachment of the outer strike point even in low-collisionality scrape-off layer plasma obtained with lithium coatings in NSTX. Significant divertor peak heat flux reduction and impurity screening have been achieved simultaneously with good core confinement and MHD properties.

AB - Steady-state handling of divertor heat flux is a critical issue for present and future conventional and spherical tokamaks with compact high power density divertors. A novel "snowflake" divertor (SFD) configuration that takes advantage of magnetic properties of a second-order poloidal null has been predicted to have a larger plasma-wetted area and a larger divertor volume, in comparison with a standard first-order poloidal X-point divertor configuration. The SFD was obtained in 0.8 MA, 4-6 MW NBI-heated H-mode discharges in NSTX using two divertor magnetic coils. The SFD led to a partial detachment of the outer strike point even in low-collisionality scrape-off layer plasma obtained with lithium coatings in NSTX. Significant divertor peak heat flux reduction and impurity screening have been achieved simultaneously with good core confinement and MHD properties.

UR - https://www.scopus.com/pages/publications/80054834023

UR - https://www.scopus.com/pages/publications/80054834023#tab=citedBy

U2 - 10.1016/j.jnucmat.2010.07.047

DO - 10.1016/j.jnucmat.2010.07.047

M3 - Article

AN - SCOPUS:80054834023

SN - 0022-3115

VL - 415

SP - S365-S368

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

IS - 1 SUPPL

ER -

"Snowflake" divertor configuration in NSTX

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