Impact of drifts on divertor power exhaust in DIII-D

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Impact of drifts on divertor power exhaust in DIII-D. / Jaervinen, A. E.; Allen, S. L.; Eldon, D.; Fenstermacher, M. E.; Groth, M.; Hill, D. N.; Lasnier, C. J.; Leonard, A. W.; McLean, A. G.; Porter, G. D.; Rognlien, T. D.; Samuell, C. M.; Wang, H. Q.; Watkins, J. G.

In: Nuclear Materials and Energy, Vol. 19, 01.05.2019, p. 230-238.

Research output: Contribution to journalArticleScientificpeer-review

Harvard

Jaervinen, AE, Allen, SL, Eldon, D, Fenstermacher, ME, Groth, M, Hill, DN, Lasnier, CJ, Leonard, AW, McLean, AG, Porter, GD, Rognlien, TD, Samuell, CM, Wang, HQ & Watkins, JG 2019, 'Impact of drifts on divertor power exhaust in DIII-D' Nuclear Materials and Energy, vol. 19, pp. 230-238. https://doi.org/10.1016/j.nme.2019.02.023

APA

Jaervinen, A. E., Allen, S. L., Eldon, D., Fenstermacher, M. E., Groth, M., Hill, D. N., ... Watkins, J. G. (2019). Impact of drifts on divertor power exhaust in DIII-D. Nuclear Materials and Energy, 19, 230-238. https://doi.org/10.1016/j.nme.2019.02.023

Vancouver

Jaervinen AE, Allen SL, Eldon D, Fenstermacher ME, Groth M, Hill DN et al. Impact of drifts on divertor power exhaust in DIII-D. Nuclear Materials and Energy. 2019 May 1;19:230-238. https://doi.org/10.1016/j.nme.2019.02.023

Author

Jaervinen, A. E. ; Allen, S. L. ; Eldon, D. ; Fenstermacher, M. E. ; Groth, M. ; Hill, D. N. ; Lasnier, C. J. ; Leonard, A. W. ; McLean, A. G. ; Porter, G. D. ; Rognlien, T. D. ; Samuell, C. M. ; Wang, H. Q. ; Watkins, J. G. / Impact of drifts on divertor power exhaust in DIII-D. In: Nuclear Materials and Energy. 2019 ; Vol. 19. pp. 230-238.

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@article{53fe893452ba436296a669d57e16e1ba,
title = "Impact of drifts on divertor power exhaust in DIII-D",
abstract = "Radiative divertor experiments and 2D fluid simulations show strong impact of cross-field drifts on the low field side (LFS) divertor target heat flux and volumetric radiation profiles when evolving to detached conditions in DIII-D high confinement mode (H-mode) plasmas with forward and reversed toroidal field configurations. In both field configurations, the peak heat flux is reduced by about a factor of 2 in detachment by D 2 -injection and by factor of 3 – 4 in detachment by N 2 -injection. Operating with the B × ∇B-drift towards the X-point (fwd. BT), the LFS divertor radiation front is observed to shift step-like from the target to near to the X-point at the onset of detachment. In contrast, operating with the B × ∇B-drift away from the X-point (rev. BT), the radiation front is observed to remain closer to the target plate and to be radially shifted towards the far SOL. These phenomena occur with detachment induced both with N 2 - and D 2 -injection. The step-like detachment onset is consistent with recently published theory of the role of poloidal E × B-drift in the private flux region in driving highly non-linear detachment onset in fwd. BT [22].",
keywords = "Detachment, Divertor, Drifts, Power exhaust, UEDGE",
author = "Jaervinen, {A. E.} and Allen, {S. L.} and D. Eldon and Fenstermacher, {M. E.} and M. Groth and Hill, {D. N.} and Lasnier, {C. J.} and Leonard, {A. W.} and McLean, {A. G.} and Porter, {G. D.} and Rognlien, {T. D.} and Samuell, {C. M.} and Wang, {H. Q.} and Watkins, {J. G.}",
year = "2019",
month = "5",
day = "1",
doi = "10.1016/j.nme.2019.02.023",
language = "English",
volume = "19",
pages = "230--238",
journal = "Nuclear Materials and Energy",
issn = "2352-1791",
publisher = "Elsevier Science Publishers BV",

}

RIS - Download

TY - JOUR

T1 - Impact of drifts on divertor power exhaust in DIII-D

AU - Jaervinen, A. E.

AU - Allen, S. L.

AU - Eldon, D.

AU - Fenstermacher, M. E.

AU - Groth, M.

AU - Hill, D. N.

AU - Lasnier, C. J.

AU - Leonard, A. W.

AU - McLean, A. G.

AU - Porter, G. D.

AU - Rognlien, T. D.

AU - Samuell, C. M.

AU - Wang, H. Q.

AU - Watkins, J. G.

PY - 2019/5/1

Y1 - 2019/5/1

N2 - Radiative divertor experiments and 2D fluid simulations show strong impact of cross-field drifts on the low field side (LFS) divertor target heat flux and volumetric radiation profiles when evolving to detached conditions in DIII-D high confinement mode (H-mode) plasmas with forward and reversed toroidal field configurations. In both field configurations, the peak heat flux is reduced by about a factor of 2 in detachment by D 2 -injection and by factor of 3 – 4 in detachment by N 2 -injection. Operating with the B × ∇B-drift towards the X-point (fwd. BT), the LFS divertor radiation front is observed to shift step-like from the target to near to the X-point at the onset of detachment. In contrast, operating with the B × ∇B-drift away from the X-point (rev. BT), the radiation front is observed to remain closer to the target plate and to be radially shifted towards the far SOL. These phenomena occur with detachment induced both with N 2 - and D 2 -injection. The step-like detachment onset is consistent with recently published theory of the role of poloidal E × B-drift in the private flux region in driving highly non-linear detachment onset in fwd. BT [22].

AB - Radiative divertor experiments and 2D fluid simulations show strong impact of cross-field drifts on the low field side (LFS) divertor target heat flux and volumetric radiation profiles when evolving to detached conditions in DIII-D high confinement mode (H-mode) plasmas with forward and reversed toroidal field configurations. In both field configurations, the peak heat flux is reduced by about a factor of 2 in detachment by D 2 -injection and by factor of 3 – 4 in detachment by N 2 -injection. Operating with the B × ∇B-drift towards the X-point (fwd. BT), the LFS divertor radiation front is observed to shift step-like from the target to near to the X-point at the onset of detachment. In contrast, operating with the B × ∇B-drift away from the X-point (rev. BT), the radiation front is observed to remain closer to the target plate and to be radially shifted towards the far SOL. These phenomena occur with detachment induced both with N 2 - and D 2 -injection. The step-like detachment onset is consistent with recently published theory of the role of poloidal E × B-drift in the private flux region in driving highly non-linear detachment onset in fwd. BT [22].

KW - Detachment

KW - Divertor

KW - Drifts

KW - Power exhaust

KW - UEDGE

UR - http://www.scopus.com/inward/record.url?scp=85062422868&partnerID=8YFLogxK

U2 - 10.1016/j.nme.2019.02.023

DO - 10.1016/j.nme.2019.02.023

M3 - Article

VL - 19

SP - 230

EP - 238

JO - Nuclear Materials and Energy

JF - Nuclear Materials and Energy

SN - 2352-1791

ER -

ID: 35318625