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Demonstration of reduced neoclassical energy transport in Wendelstein 7-X

Research on magnetic confinement of high-temperature plasmas has the ultimate goal of harnessing nuclear fusion for the production of electricity. Although the tokamak(1) is the leading toroidal magnetic-confinement concept, it is not without shortcomings and the fusion community has therefore also...

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Autores principales: Beidler, C. D., Smith, H. M., Alonso, A., Andreeva, T., Baldzuhn, J., Beurskens, M. N. A., Borchardt, M., Bozhenkov, S. A., Brunner, K. J., Damm, H., Drevlak, M., Ford, O. P., Fuchert, G., Geiger, J., Helander, P., Hergenhahn, U., Hirsch, M., Höfel, U., Kazakov, Ye. O., Kleiber, R., Krychowiak, M., Kwak, S., Langenberg, A., Laqua, H. P., Neuner, U., Pablant, N. A., Pasch, E., Pavone, A., Pedersen, T. S., Rahbarnia, K., Schilling, J., Scott, E. R., Stange, T., Svensson, J., Thomsen, H., Turkin, Y., Warmer, F., Wolf, R. C., Zhang, D.
Formato: Online Artículo Texto
Lenguaje:English
Publicado: Nature Publishing Group UK 2021
Materias:
Acceso en línea:https://www.ncbi.nlm.nih.gov/pmc/articles/PMC8357633/
https://www.ncbi.nlm.nih.gov/pubmed/34381232
http://dx.doi.org/10.1038/s41586-021-03687-w
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author Beidler, C. D.
Smith, H. M.
Alonso, A.
Andreeva, T.
Baldzuhn, J.
Beurskens, M. N. A.
Borchardt, M.
Bozhenkov, S. A.
Brunner, K. J.
Damm, H.
Drevlak, M.
Ford, O. P.
Fuchert, G.
Geiger, J.
Helander, P.
Hergenhahn, U.
Hirsch, M.
Höfel, U.
Kazakov, Ye. O.
Kleiber, R.
Krychowiak, M.
Kwak, S.
Langenberg, A.
Laqua, H. P.
Neuner, U.
Pablant, N. A.
Pasch, E.
Pavone, A.
Pedersen, T. S.
Rahbarnia, K.
Schilling, J.
Scott, E. R.
Stange, T.
Svensson, J.
Thomsen, H.
Turkin, Y.
Warmer, F.
Wolf, R. C.
Zhang, D.
author_facet Beidler, C. D.
Smith, H. M.
Alonso, A.
Andreeva, T.
Baldzuhn, J.
Beurskens, M. N. A.
Borchardt, M.
Bozhenkov, S. A.
Brunner, K. J.
Damm, H.
Drevlak, M.
Ford, O. P.
Fuchert, G.
Geiger, J.
Helander, P.
Hergenhahn, U.
Hirsch, M.
Höfel, U.
Kazakov, Ye. O.
Kleiber, R.
Krychowiak, M.
Kwak, S.
Langenberg, A.
Laqua, H. P.
Neuner, U.
Pablant, N. A.
Pasch, E.
Pavone, A.
Pedersen, T. S.
Rahbarnia, K.
Schilling, J.
Scott, E. R.
Stange, T.
Svensson, J.
Thomsen, H.
Turkin, Y.
Warmer, F.
Wolf, R. C.
Zhang, D.
author_sort Beidler, C. D.
collection PubMed
description Research on magnetic confinement of high-temperature plasmas has the ultimate goal of harnessing nuclear fusion for the production of electricity. Although the tokamak(1) is the leading toroidal magnetic-confinement concept, it is not without shortcomings and the fusion community has therefore also pursued alternative concepts such as the stellarator. Unlike axisymmetric tokamaks, stellarators possess a three-dimensional (3D) magnetic field geometry. The availability of this additional dimension opens up an extensive configuration space for computational optimization of both the field geometry itself and the current-carrying coils that produce it. Such an optimization was undertaken in designing Wendelstein 7-X (W7-X)(2), a large helical-axis advanced stellarator (HELIAS), which began operation in 2015 at Greifswald, Germany. A major drawback of 3D magnetic field geometry, however, is that it introduces a strong temperature dependence into the stellarator’s non-turbulent ‘neoclassical’ energy transport. Indeed, such energy losses will become prohibitive in high-temperature reactor plasmas unless a strong reduction of the geometrical factor associated with this transport can be achieved; such a reduction was therefore a principal goal of the design of W7-X. In spite of the modest heating power currently available, W7-X has already been able to achieve high-temperature plasma conditions during its 2017 and 2018 experimental campaigns, producing record values of the fusion triple product for such stellarator plasmas(3,4). The triple product of plasma density, ion temperature and energy confinement time is used in fusion research as a figure of merit, as it must attain a certain threshold value before net-energy-producing operation of a reactor becomes possible(1,5). Here we demonstrate that such record values provide evidence for reduced neoclassical energy transport in W7-X, as the plasma profiles that produced these results could not have been obtained in stellarators lacking a comparably high level of neoclassical optimization.
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spelling pubmed-83576332021-08-27 Demonstration of reduced neoclassical energy transport in Wendelstein 7-X Beidler, C. D. Smith, H. M. Alonso, A. Andreeva, T. Baldzuhn, J. Beurskens, M. N. A. Borchardt, M. Bozhenkov, S. A. Brunner, K. J. Damm, H. Drevlak, M. Ford, O. P. Fuchert, G. Geiger, J. Helander, P. Hergenhahn, U. Hirsch, M. Höfel, U. Kazakov, Ye. O. Kleiber, R. Krychowiak, M. Kwak, S. Langenberg, A. Laqua, H. P. Neuner, U. Pablant, N. A. Pasch, E. Pavone, A. Pedersen, T. S. Rahbarnia, K. Schilling, J. Scott, E. R. Stange, T. Svensson, J. Thomsen, H. Turkin, Y. Warmer, F. Wolf, R. C. Zhang, D. Nature Article Research on magnetic confinement of high-temperature plasmas has the ultimate goal of harnessing nuclear fusion for the production of electricity. Although the tokamak(1) is the leading toroidal magnetic-confinement concept, it is not without shortcomings and the fusion community has therefore also pursued alternative concepts such as the stellarator. Unlike axisymmetric tokamaks, stellarators possess a three-dimensional (3D) magnetic field geometry. The availability of this additional dimension opens up an extensive configuration space for computational optimization of both the field geometry itself and the current-carrying coils that produce it. Such an optimization was undertaken in designing Wendelstein 7-X (W7-X)(2), a large helical-axis advanced stellarator (HELIAS), which began operation in 2015 at Greifswald, Germany. A major drawback of 3D magnetic field geometry, however, is that it introduces a strong temperature dependence into the stellarator’s non-turbulent ‘neoclassical’ energy transport. Indeed, such energy losses will become prohibitive in high-temperature reactor plasmas unless a strong reduction of the geometrical factor associated with this transport can be achieved; such a reduction was therefore a principal goal of the design of W7-X. In spite of the modest heating power currently available, W7-X has already been able to achieve high-temperature plasma conditions during its 2017 and 2018 experimental campaigns, producing record values of the fusion triple product for such stellarator plasmas(3,4). The triple product of plasma density, ion temperature and energy confinement time is used in fusion research as a figure of merit, as it must attain a certain threshold value before net-energy-producing operation of a reactor becomes possible(1,5). Here we demonstrate that such record values provide evidence for reduced neoclassical energy transport in W7-X, as the plasma profiles that produced these results could not have been obtained in stellarators lacking a comparably high level of neoclassical optimization. Nature Publishing Group UK 2021-08-11 2021 /pmc/articles/PMC8357633/ /pubmed/34381232 http://dx.doi.org/10.1038/s41586-021-03687-w Text en © The Author(s) 2021, corrected publication 2021 https://creativecommons.org/licenses/by/4.0/Open Access This article is licensed under a Creative Commons Attribution 4.0 International License, which permits use, sharing, adaptation, distribution and reproduction in any medium or format, as long as you give appropriate credit to the original author(s) and the source, provide a link to the Creative Commons license, and indicate if changes were made. The images or other third party material in this article are included in the article’s Creative Commons license, unless indicated otherwise in a credit line to the material. If material is not included in the article’s Creative Commons license and your intended use is not permitted by statutory regulation or exceeds the permitted use, you will need to obtain permission directly from the copyright holder. To view a copy of this license, visit http://creativecommons.org/licenses/by/4.0/ (https://creativecommons.org/licenses/by/4.0/) .
spellingShingle Article
Beidler, C. D.
Smith, H. M.
Alonso, A.
Andreeva, T.
Baldzuhn, J.
Beurskens, M. N. A.
Borchardt, M.
Bozhenkov, S. A.
Brunner, K. J.
Damm, H.
Drevlak, M.
Ford, O. P.
Fuchert, G.
Geiger, J.
Helander, P.
Hergenhahn, U.
Hirsch, M.
Höfel, U.
Kazakov, Ye. O.
Kleiber, R.
Krychowiak, M.
Kwak, S.
Langenberg, A.
Laqua, H. P.
Neuner, U.
Pablant, N. A.
Pasch, E.
Pavone, A.
Pedersen, T. S.
Rahbarnia, K.
Schilling, J.
Scott, E. R.
Stange, T.
Svensson, J.
Thomsen, H.
Turkin, Y.
Warmer, F.
Wolf, R. C.
Zhang, D.
Demonstration of reduced neoclassical energy transport in Wendelstein 7-X
title Demonstration of reduced neoclassical energy transport in Wendelstein 7-X
title_full Demonstration of reduced neoclassical energy transport in Wendelstein 7-X
title_fullStr Demonstration of reduced neoclassical energy transport in Wendelstein 7-X
title_full_unstemmed Demonstration of reduced neoclassical energy transport in Wendelstein 7-X
title_short Demonstration of reduced neoclassical energy transport in Wendelstein 7-X
title_sort demonstration of reduced neoclassical energy transport in wendelstein 7-x
topic Article
url https://www.ncbi.nlm.nih.gov/pmc/articles/PMC8357633/
https://www.ncbi.nlm.nih.gov/pubmed/34381232
http://dx.doi.org/10.1038/s41586-021-03687-w
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