Developing high performance RF heating scenarios on the WEST tokamak

Goniche, M.; Ostuni, V.; Bourdelle, C.; Maget, P.; Artaud, J. F.; Bernard, J. M.; Bobkov, V.; Bucalossi, J.; Clairet, F.; Colas, L.; Desgranges, C.; Delpech, L.; Devynck, P.; Dumont, R.; Ekedahl, A.; Fedorczak, N.; Garcia, J.; Gaspar, J.; Gil, C.; Guillemaut, C.; Gunn, J.; Hillairet, J.; Klepper, C. Christopher; Lau, Cornwall; Lerche, E.; Lombard, G.; Manas, P.; Martin, Elijah H.; Mazon, D.; Meyer, O.; Morales, J.; Moreau, Ph.; Nardon, E.; Nouailletas, R.; Pegourié, B.; Peret, M.; Peysson, Y.; Regal-Mezin, X.; Sabot, R.; Shiraiwa, S.; Urbanczyk, G.; Vermare, L.; Vezinet, D.; Wallace, G. M.

doi:10.1088/1741-4326/ac9691

Developing high performance RF heating scenarios on the WEST tokamak

Journal Article · Sun Nov 20 23:00:00 EST 2022 · Nuclear Fusion

DOI:https://doi.org/10.1088/1741-4326/ac9691· OSTI ID:1909154

^[1]; Ostuni, V. ^[1]; ^[1]; ^[1]; Artaud, J. F. ^[1]; Bernard, J. M. ^[1]; Bobkov, V. ^[2]; Bucalossi, J. ^[1]; Clairet, F. ^[1]; ^[1]; Desgranges, C. ^[1]; Delpech, L. ^[1]; ^[1]; ^[1]; Ekedahl, A. ^[1]; Fedorczak, N. ^[1]; ^[1]; Gaspar, J. ^[3]; Gil, C. ^[1]; Guillemaut, C. ^[1] more »

CEA, IRFM, Saint Paul Lez Durance (France)
Max-Planck Institut für Plasmaphysik, Garching (Germany)
Aix-Marseille Univ., Marseille (France); Centre National de la Recherche Scientifique (CNRS) (France); IUSTI Laboratory, Marseille (France)
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Royal Military Academy, Bruxelles (Belgium)
Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
Ecole Polytechnique, Palaiseau (France); Centre National de la Recherche Scientifique-Mixed Organizations (CNRS-UMR), Paris (France)
Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States). Plasma Science and Fusion Center

High power experiments, up to 9.2 MW with LHCD and ICRH, have been carried out in the full tungsten tokamak WEST. Here, quasi non inductive discharges have been achieved allowing to extend the plasma duration to 53 s with stationary conditions in particular with respect to tungsten contamination. Transitions to H mode are observed, and H-modes lasting up to 4 s have been obtained. The increase in stored energy is weak since the power crossing the separatrix is close to the L–H threshold. Hot L mode plasmas (central temperature exceeding 3 keV) with a confinement time following the ITER L96 scaling law are routinely obtained. The weak aspect ratio dependence of this scaling law is confirmed. Tungsten accumulation is generally not an operational issue on WEST. Difficulty of burning through tungsten can prevent the discharge from accessing to a hot core plasma in the ramp-up phase, or can lead to rapid collapse of the central temperature when radiation is enhanced by a slight decrease of the temperature. Except a few pulses post-boronization, the plasma radiation is rather high (P_rad/P_tot ~ 50%) and is dominated by tungsten. This fraction does not vary as the RF power is ramped up and is quite similar in ICRH and/or LHCD heated plasmas. An estimate of the contribution of the RF antennas to the plasma contamination in tungsten is given.

View Accepted Manuscript (DOE)

Research Organization:: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Sponsoring Organization:: USDOE; Euratom

Contributing Organization:: The WEST Team

Grant/Contract Number:: AC05-00OR22725

OSTI ID:: 1909154

Journal Information:: Nuclear Fusion, Journal Name: Nuclear Fusion Journal Issue: 12 Vol. 62; ISSN 0029-5515

Publisher:: IOP ScienceCopyright Statement

Country of Publication:: United States

Language:: English

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