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Impact of drifts on divertor power exhaust in DIII-D
- Source :
- 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 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, Nuclear Materials and Energy, Vol 19, Iss, Pp 230-238 (2019)
- Publication Year :
- 2019
- Publisher :
- Elsevier BV, 2019.
-
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].
- Subjects :
- Nuclear and High Energy Physics
Field (physics)
DIII-D
Detachment
Materials Science (miscellaneous)
Flux
Drifts
01 natural sciences
010305 fluids & plasmas
Divertor
Physics::Plasma Physics
UEDGE
0103 physical sciences
Radiative transfer
010302 applied physics
Physics
ta114
Power exhaust
Plasma
lcsh:TK9001-9401
High-confinement mode
Nuclear Energy and Engineering
Heat flux
lcsh:Nuclear engineering. Atomic power
Atomic physics
Subjects
Details
- ISSN :
- 23521791
- Volume :
- 19
- Database :
- OpenAIRE
- Journal :
- Nuclear Materials and Energy
- Accession number :
- edsair.doi.dedup.....a1af14d965ae570c88e064f525101f7f