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.; Lau, C.; Lerche, E.; Lombard, G.; Manas, P.; Martin, E. 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:10.7910/DVN/AAAYFM

Title: Developing high performance RF heating scenarios on the WEST tokamak

Dataset
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Abstract

High power experiments, up to 9.2 MW with LHCD and ICRH, have been carried out in the full tungsten tokamak WEST. Quasi non inductive discharges have been achieved allowing to extend the plasma duration to 53s with stationary conditions in particular with respect to tungsten contamination. Transitions in H mode are obtained lasting up to 4s with weak energy increment at the power crossing the separatrix is close to the threshold. Hot L mode plasmas (Te(0)>3keV) with a confinement time following the ITER L96 scaling 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 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. Apart few pulses post-boronization, the plasma radiation is rather high (Prad/Ptot~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 inmore » tungsten is given.« less

Authors:

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. more »

OSTI

Publication Date:: Sun Feb 27 23:00:00 EST 2022

DOE Contract Number:: SC0014264

Research Org.:: Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States). Plasma Science and Fusion Center

Sponsoring Org.:: USDOE Office of Science (SC), Fusion Energy Sciences (FES)

Collaborations:: West Team

Subject:: 70 PLASMA PHYSICS AND FUSION TECHNOLOGY

OSTI Identifier:: 1887781

DOI:: https://doi.org/10.7910/DVN/AAAYFM

Citation Formats


                    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., Lau, C., Lerche, E., Lombard, G., Manas, P., Martin, E. 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., and Wallace, G. M. Developing high performance RF heating scenarios on the WEST tokamak.  United States: N. p., 2022. 
        Web.  doi:10.7910/DVN/AAAYFM.

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                    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., Lau, C., Lerche, E., Lombard, G., Manas, P., Martin, E. 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. Developing high performance RF heating scenarios on the WEST tokamak.  United States.  doi:https://doi.org/10.7910/DVN/AAAYFM

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                    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., Lau, C., Lerche, E., Lombard, G., Manas, P., Martin, E. 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., and Wallace, G. M. 2022.  
"Developing high performance RF heating scenarios on the WEST tokamak".  United States.  doi:https://doi.org/10.7910/DVN/AAAYFM.  https://www.osti.gov/servlets/purl/1887781. Pub date:Sun Feb 27 23:00:00 EST 2022

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@article{osti_1887781,

  title        = {Developing high performance RF heating scenarios on the WEST tokamak},

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

  abstractNote = {High power experiments, up to 9.2 MW with LHCD and ICRH, have been carried out in the full tungsten tokamak WEST. Quasi non inductive discharges have been achieved allowing to extend the plasma duration to 53s with stationary conditions in particular with respect to tungsten contamination. Transitions in H mode are obtained lasting up to 4s with weak energy increment at the power crossing the separatrix is close to the threshold. Hot L mode plasmas (Te(0)>3keV) with a confinement time following the ITER L96 scaling 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 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. Apart few pulses post-boronization, the plasma radiation is rather high (Prad/Ptot~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.},

  doi          = {10.7910/DVN/AAAYFM},

  journal      = {},

  number       = ,

  volume       = ,

  place        = {United States},

  year         = {Sun Feb 27 23:00:00 EST 2022},

  month        = {Sun Feb 27 23:00:00 EST 2022}

}

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