Results 1 to 10 of about 1,452 (264)

Divertor geometry effects on detachment in TCV [PDF]

Journal of Nuclear Materials, 2001
Experimental observations and some preliminary results from B2-Eirene code modelling of divertor detachment in the TCV tokamak are reported, with emphasis on the aspects of this detachment related to divertor geometry. The contribution is restricted to deuterium fuelled ohmic plasmas for which the CB drift is directed away from the X-point of lower ...
Pitts, R., Duval, B., Loarte, A., Moret, J., Boedo, J., Coster, D., Furno, I., Horacek, J., Kukushkin, A., Reiterand, D., Rommers, J.   +10 more
openaire   +4 more sources

The role of drifts on the isotope effect on divertor plasma detachment in JET Ohmic discharges

Nuclear Materials and Energy, 2020
Experiments in JET-ILW Ohmic confinement mode plasmas show that the line-averaged detachment onset density in deuterium discharges is approx. 10% lower than in hydrogen discharges.
V. Solokha, M. Groth, S. Brezinsek, M. Brix, G. Corrigan, C. Guillemaut, D. Harting, S. Jachmich, U. Kruezi, S. Marsen, S. Wiesen   +10 more
doaj   +2 more sources

Evaluation of ITER divertor shunts as a synthetic diagnostic for detachment control [PDF]

Nuclear Fusion, 2023
Reliable diagnostics that measure the detached state of the ITER divertor plasma will be necessary to control heat flux to the divertor targets during steady state, burning plasma operation. This paper conducts an initial exploration into the feasibility
C.A. Orrico, T. Ravensbergen, R.A. Pitts, X. Bonnin, E. Kaveeva, J.S. Park, V. Rozhansky, I. Senichenkov, C. Watts, M. de Baar   +9 more
doaj   +2 more sources

Energy and particle balance during plasma detachment in a long-leg divertor configuration

Nuclear Fusion, 2023
Comprehensive studies of energy and particle balances in the transition to plasma detachment in an alternative divertor configuration with long outer legs are shown.
R. Masline, S.I. Krasheninnikov
doaj   +2 more sources

Measurements of heat flux components due to charged and non-charged particles in DIII-D divertor near and under detachment

Nuclear Materials and Energy, 2023
Surfacing Eroding Thermocouples (SETC) have been used to provide high spatial and temporal resolution heat flux measurement in DIII-D. SETCs were first tested in the lower divertor of DIII-D using the Divertor Material Evaluation System (DiMES), then an ...
J. Ren, D.C. Donovan, J.G. Watkins, H.Q. Wang, X.X. Ma, R. Maurizio, M.W. Shafer, D. Rudakov, P.C. Stangeby, D. Thomas, S. Hong   +10 more
doaj   +1 more source

Control of tungsten impurity source and edge transport using different gas injection with full tungsten divertor on EAST

Nuclear Materials and Energy, 2022
Tungsten (W) erosion and edge transport are investigated for EAST L-mode discharges with different gas injection. It is found that W erosion can be suppressed or mitigated by Ne or D2 seeding when divertor detachment is achieved.
R. Ding, G.L. Xu, H. Wang, F. Ding, L. Zhang, Q. Zhang, K.D. Li, J.B. Liu, S. Brezinsek, A. Kirschner, S.X. Wang, B.F. Gao, L.Y. Meng, L. Wang, H. Xie, H. Si, R. Yan, D.H. Zhu, J.L. Chen   +18 more
doaj   +1 more source

Optimizing detachment control using the magnetic configuration of divertors [PDF]

Nuclear Fusion, 2022
Abstract As tokamak research moves to reactor conditions, the control of a stable, optimally-detached divertor plasma has become increasingly relevant. Simple predictions of such detachment control have been performed previously using the detachment location sensitivity (DLS) model (Lipschultz et al 2016 Nucl.
C. Cowley, B. Lipschultz, D. Moulton, B. Dudson   +3 more
openaire   +2 more sources

Modeling of argon seeding in ASDEX Upgrade H-mode plasma with SOLPS5.0

Nuclear Materials and Energy, 2017
SOLPS modeling of Ar seeding in ASDEX Upgrade H-mode plasma shows that the divertor compression of Ar increases with the seeding rate when the inner divertor is detached and the outer divertor is attached.
L.Y. Xiang, M. Wischmeier, D. Coster, M. Bernert, H.Y. Guo, G.N. Luo, ASDEX Upgrade team   +6 more
doaj   +1 more source

A new scaling for divertor detachment

Plasma Physics and Controlled Fusion, 2017
The ITER design, and future reactor designs, depend on divertor 'detachment,' whether partial, pronounced or complete, to limit heat flux to plasma-facing components and to limit surface erosion due to sputtering. It would be valuable to have a measure of the difficulty of achieving detachment as a function of machine parameters, such as input power ...
R J Goldston, M L Reinke, J A Schwartz
openaire   +2 more sources

Sustained radiative divertor in high-performance grassy-ELM regime with metal wall towards long-pulse operation in EAST

Nuclear Materials and Energy, 2021
Simultaneous control of transient heat load induced by large-amplitude edge-localized modes (ELMs) and steady-state heat load on divertor targets under metal wall environment is crucial for steady-state operation of future tokamak fusion reactors, such ...
K.D. Li, G.S. Xu, Q.P. Yuan, L. Wang, Z.S. Yang, J.B. Liu, Q.Q. Yang, K. Wu, Y.M. Duan, J.C. Xu, L.Y. Meng, H.Q. Wang, H.Y. Guo, F. Ding, M.W. Chen, L. Zhang, N. Yan, Y.Q. Tao, E.Z. Li, L. Zeng, B. Zhang, X.Z. Gong, B.J. Xiao, G.N. Luo, B.N. Wan   +24 more
doaj   +1 more source