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托卡马克中无有害边缘能量爆发的最高聚变性能。

Highest fusion performance without harmful edge energy bursts in tokamak.

作者信息

Kim S K, Shousha R, Yang S M, Hu Q, Hahn S H, Jalalvand A, Park J-K, Logan N C, Nelson A O, Na Y-S, Nazikian R, Wilcox R, Hong R, Rhodes T, Paz-Soldan C, Jeon Y M, Kim M W, Ko W H, Lee J H, Battey A, Yu G, Bortolon A, Snipes J, Kolemen E

机构信息

Princeton Plasma Physics Laboratory, Princeton, NJ, USA.

Korea Institute of Fusion Energy, Daejeon, South Korea.

出版信息

Nat Commun. 2024 May 11;15(1):3990. doi: 10.1038/s41467-024-48415-w.

DOI:10.1038/s41467-024-48415-w
PMID:38734685
原文链接:https://pmc.ncbi.nlm.nih.gov/articles/PMC11088687/
Abstract

The path of tokamak fusion and International thermonuclear experimental reactor (ITER) is maintaining high-performance plasma to produce sufficient fusion power. This effort is hindered by the transient energy burst arising from the instabilities at the boundary of plasmas. Conventional 3D magnetic perturbations used to suppress these instabilities often degrade fusion performance and increase the risk of other instabilities. This study presents an innovative 3D field optimization approach that leverages machine learning and real-time adaptability to overcome these challenges. Implemented in the DIII-D and KSTAR tokamaks, this method has consistently achieved reactor-relevant core confinement and the highest fusion performance without triggering damaging bursts. This is enabled by advances in the physics understanding of self-organized transport in the plasma edge and machine learning techniques to optimize the 3D field spectrum. The success of automated, real-time adaptive control of such complex systems paves the way for maximizing fusion efficiency in ITER and beyond while minimizing damage to device components.

摘要

托卡马克核聚变及国际热核聚变实验反应堆(ITER)的发展道路在于维持高性能等离子体以产生足够的聚变功率。这一努力受到等离子体边界不稳定性引发的瞬态能量爆发的阻碍。用于抑制这些不稳定性的传统三维磁扰动常常会降低聚变性能,并增加出现其他不稳定性的风险。本研究提出了一种创新的三维场优化方法,该方法利用机器学习和实时适应性来克服这些挑战。在DIII-D和KSTAR托卡马克装置中实施该方法后,始终实现了与反应堆相关的核心约束以及最高的聚变性能,且未引发破坏性爆发。这得益于对等离子体边缘自组织输运的物理理解的进步以及用于优化三维场谱的机器学习技术。这种复杂系统的自动化、实时自适应控制的成功,为在ITER及其他装置中最大化聚变效率、同时最小化对装置部件的损害铺平了道路。

https://cdn.ncbi.nlm.nih.gov/pmc/blobs/a3f9/11088687/f355fe4dbb3d/41467_2024_48415_Fig9_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/a3f9/11088687/bc9e67cdbcf9/41467_2024_48415_Fig1_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/a3f9/11088687/53c0c8c5277e/41467_2024_48415_Fig2_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/a3f9/11088687/d2f6176e622c/41467_2024_48415_Fig3_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/a3f9/11088687/c636028098c3/41467_2024_48415_Fig4_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/a3f9/11088687/e3758f55fe52/41467_2024_48415_Fig5_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/a3f9/11088687/5708841a1a89/41467_2024_48415_Fig6_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/a3f9/11088687/dcaaf6cacc72/41467_2024_48415_Fig7_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/a3f9/11088687/00bd2d37e65e/41467_2024_48415_Fig8_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/a3f9/11088687/f355fe4dbb3d/41467_2024_48415_Fig9_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/a3f9/11088687/bc9e67cdbcf9/41467_2024_48415_Fig1_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/a3f9/11088687/53c0c8c5277e/41467_2024_48415_Fig2_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/a3f9/11088687/d2f6176e622c/41467_2024_48415_Fig3_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/a3f9/11088687/c636028098c3/41467_2024_48415_Fig4_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/a3f9/11088687/e3758f55fe52/41467_2024_48415_Fig5_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/a3f9/11088687/5708841a1a89/41467_2024_48415_Fig6_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/a3f9/11088687/dcaaf6cacc72/41467_2024_48415_Fig7_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/a3f9/11088687/00bd2d37e65e/41467_2024_48415_Fig8_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/a3f9/11088687/f355fe4dbb3d/41467_2024_48415_Fig9_HTML.jpg

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本文引用的文献

1
Avoiding fusion plasma tearing instability with deep reinforcement learning.利用深度强化学习避免聚变等离子体撕裂不稳定性。
Nature. 2024 Feb;626(8000):746-751. doi: 10.1038/s41586-024-07024-9. Epub 2024 Feb 21.
2
Quasicontinuous Exhaust Scenario for a Fusion Reactor: The Renaissance of Small Edge Localized Modes.聚变反应堆的准连续排气方案:小边缘局域模的复兴
Phys Rev Lett. 2022 Oct 14;129(16):165001. doi: 10.1103/PhysRevLett.129.165001.
3
A sustained high-temperature fusion plasma regime facilitated by fast ions.由快离子实现的持续高温聚变等离子体状态。
Nature. 2022 Sep;609(7926):269-275. doi: 10.1038/s41586-022-05008-1. Epub 2022 Sep 7.
4
Magnetic control of tokamak plasmas through deep reinforcement learning.通过深度强化学习控制托卡马克等离子体。
Nature. 2022 Feb;602(7897):414-419. doi: 10.1038/s41586-021-04301-9. Epub 2022 Feb 16.
5
Quasisymmetric Optimization of Nonaxisymmetry in Tokamaks.托卡马克中非轴对称性的准对称优化
Phys Rev Lett. 2021 Mar 26;126(12):125001. doi: 10.1103/PhysRevLett.126.125001.
6
Wide Operational Windows of Edge-Localized Mode Suppression by Resonant Magnetic Perturbations in the DIII-D Tokamak.通过DIII-D托卡马克中的共振磁扰动实现边界局域模抑制的宽操作窗口
Phys Rev Lett. 2020 Jul 24;125(4):045001. doi: 10.1103/PhysRevLett.125.045001.
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Predicting disruptive instabilities in controlled fusion plasmas through deep learning.通过深度学习预测受控聚变等离子体中的不稳定性。
Nature. 2019 Apr;568(7753):526-531. doi: 10.1038/s41586-019-1116-4. Epub 2019 Apr 17.
8
Nonlinear Transition from Mitigation to Suppression of the Edge Localized Mode with Resonant Magnetic Perturbations in the EAST Tokamak.在EAST托卡马克装置中通过共振磁扰动实现从边缘局域模的缓解到抑制的非线性转变
Phys Rev Lett. 2016 Sep 9;117(11):115001. doi: 10.1103/PhysRevLett.117.115001.
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Phys Rev Lett. 2015 Mar 13;114(10):105002. doi: 10.1103/PhysRevLett.114.105002. Epub 2015 Mar 12.
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