Taming the plasma-material interface with the 'snowflake' divertor in NSTX

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

doi:10.1088/0029-5515/51/1/012001

Taming the plasma-material interface with the 'snowflake' divertor in NSTX

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

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

80 Scopus citations

Abstract

Steady-state handling of divertor heat flux is a critical issue for ITER and future conventional and spherical tokamaks with compact high-power density divertors. A novel 'snowflake' divertor (SFD) configuration was theoretically predicted to have significant magnetic geometry benefits for divertor heat flux mitigation, such as an increased plasma-wetted area and a higher divertor volume available for volumetric power and momentum loss processes, as compared with the standard divertor. Both a significant divertor peak heat flux reduction and impurity screening have been achieved simultaneously with core H-mode confinement in discharges with the SFD using only a minimal set of poloidal field coils.

Original language	English (US)
Article number	012001
Journal	Nuclear Fusion
Volume	51
Issue number	1
DOIs	https://doi.org/10.1088/0029-5515/51/1/012001
State	Published - Jan 2011

All Science Journal Classification (ASJC) codes

Nuclear and High Energy Physics
Condensed Matter Physics

Access to Document

10.1088/0029-5515/51/1/012001

Cite this

Soukhanovskii, V. A., Ahn, J. W., Bell, R. E., Gates, D. A., Gerhardt, S., Kaita, R., Kolemen, E., LeBlanc, B. P., Maingi, R., Makowski, M., Maqueda, R., McLean, A. G., Menard, J. E., Mueller, D., Paul, S. F., Raman, R., Roquemore, A. L., Ryutov, D. D., Sabbagh, S. A., & Scott, H. A. (2011). Taming the plasma-material interface with the 'snowflake' divertor in NSTX. Nuclear Fusion, 51(1), Article 012001. https://doi.org/10.1088/0029-5515/51/1/012001

@article{71f559d8948341f0ba539b0284c1a428,

title = "Taming the plasma-material interface with the 'snowflake' divertor in NSTX",

abstract = "Steady-state handling of divertor heat flux is a critical issue for ITER and future conventional and spherical tokamaks with compact high-power density divertors. A novel 'snowflake' divertor (SFD) configuration was theoretically predicted to have significant magnetic geometry benefits for divertor heat flux mitigation, such as an increased plasma-wetted area and a higher divertor volume available for volumetric power and momentum loss processes, as compared with the standard divertor. Both a significant divertor peak heat flux reduction and impurity screening have been achieved simultaneously with core H-mode confinement in discharges with the SFD using only a minimal set of poloidal field coils.",

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 LeBlanc, {B. P.} and R. Maingi and M. Makowski and R. Maqueda and McLean, {A. G.} and Menard, {J. E.} and D. Mueller and Paul, {S. F.} and R. Raman and Roquemore, {A. L.} and Ryutov, {D. D.} and Sabbagh, {S. A.} and Scott, {H. A.}",

year = "2011",

month = jan,

doi = "10.1088/0029-5515/51/1/012001",

language = "English (US)",

volume = "51",

journal = "Nuclear Fusion",

issn = "0029-5515",

publisher = "IOP Publishing Ltd.",

number = "1",

}

Soukhanovskii, VA, Ahn, JW, Bell, RE, Gates, DA, Gerhardt, S, Kaita, R, Kolemen, E, LeBlanc, BP, Maingi, R, Makowski, M, Maqueda, R, McLean, AG, Menard, JE, Mueller, D, Paul, SF, Raman, R, Roquemore, AL, Ryutov, DD, Sabbagh, SA & Scott, HA 2011, 'Taming the plasma-material interface with the 'snowflake' divertor in NSTX', Nuclear Fusion, vol. 51, no. 1, 012001. https://doi.org/10.1088/0029-5515/51/1/012001

TY - JOUR

T1 - Taming the plasma-material interface with the 'snowflake' divertor 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 - LeBlanc, B. P.

AU - Maingi, R.

AU - Makowski, M.

AU - Maqueda, R.

AU - McLean, A. G.

AU - Menard, J. E.

AU - Mueller, D.

AU - Paul, S. F.

AU - Raman, R.

AU - Roquemore, A. L.

AU - Ryutov, D. D.

AU - Sabbagh, S. A.

AU - Scott, H. A.

PY - 2011/1

Y1 - 2011/1

N2 - Steady-state handling of divertor heat flux is a critical issue for ITER and future conventional and spherical tokamaks with compact high-power density divertors. A novel 'snowflake' divertor (SFD) configuration was theoretically predicted to have significant magnetic geometry benefits for divertor heat flux mitigation, such as an increased plasma-wetted area and a higher divertor volume available for volumetric power and momentum loss processes, as compared with the standard divertor. Both a significant divertor peak heat flux reduction and impurity screening have been achieved simultaneously with core H-mode confinement in discharges with the SFD using only a minimal set of poloidal field coils.

AB - Steady-state handling of divertor heat flux is a critical issue for ITER and future conventional and spherical tokamaks with compact high-power density divertors. A novel 'snowflake' divertor (SFD) configuration was theoretically predicted to have significant magnetic geometry benefits for divertor heat flux mitigation, such as an increased plasma-wetted area and a higher divertor volume available for volumetric power and momentum loss processes, as compared with the standard divertor. Both a significant divertor peak heat flux reduction and impurity screening have been achieved simultaneously with core H-mode confinement in discharges with the SFD using only a minimal set of poloidal field coils.

UR - http://www.scopus.com/inward/record.url?scp=79551503362&partnerID=8YFLogxK

UR - http://www.scopus.com/inward/citedby.url?scp=79551503362&partnerID=8YFLogxK

U2 - 10.1088/0029-5515/51/1/012001

DO - 10.1088/0029-5515/51/1/012001

M3 - Article

AN - SCOPUS:79551503362

SN - 0029-5515

VL - 51

JO - Nuclear Fusion

JF - Nuclear Fusion

IS - 1

M1 - 012001

ER -

Taming the plasma-material interface with the 'snowflake' divertor in NSTX

Abstract

All Science Journal Classification (ASJC) codes

Access to Document

Other files and links

Fingerprint

Cite this