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本文引用的文献

1
Managing the heat: In-Vessel Components.热管理:堆内构件
Philos Trans A Math Phys Eng Sci. 2024 Oct 9;382(2280):20230408. doi: 10.1098/rsta.2023.0408. Epub 2024 Aug 26.
2
The magnetic cage.磁笼
Philos Trans A Math Phys Eng Sci. 2024 Oct 9;382(2280):20230407. doi: 10.1098/rsta.2023.0407. Epub 2024 Aug 26.
3
Staying positive: producing net power.保持积极:产生净功率。
Philos Trans A Math Phys Eng Sci. 2024 Oct 9;382(2280):20230404. doi: 10.1098/rsta.2023.0404. Epub 2024 Aug 26.
4
Controlling a new plasma regime.控制一种新的等离子体状态。
Philos Trans A Math Phys Eng Sci. 2024 Oct 9;382(2280):20230403. doi: 10.1098/rsta.2023.0403. Epub 2024 Aug 26.
5
Concept design overview: a question of choices and compromise.概念设计概述:选择与折中的问题。
Philos Trans A Math Phys Eng Sci. 2024 Oct 9;382(2280):20230414. doi: 10.1098/rsta.2023.0414. Epub 2024 Aug 26.
6
Fusing together an outline design for sustained fuelling and tritium self-sufficiency.融合持续燃料供应和氚自给自足的轮廓设计。
Philos Trans A Math Phys Eng Sci. 2024 Oct 9;382(2280):20230410. doi: 10.1098/rsta.2023.0410. Epub 2024 Aug 26.
7
Optimizing the cost of the STEP programme.优化STEP项目的成本。
Philos Trans A Math Phys Eng Sci. 2024 Oct 9;382(2280):20230413. doi: 10.1098/rsta.2023.0413. Epub 2024 Aug 26.
8
Demonstration of Safe Termination of Megaampere Relativistic Electron Beams in Tokamaks.托卡马克中兆安相对论电子束安全终止的演示。
Phys Rev Lett. 2021 Apr 30;126(17):175001. doi: 10.1103/PhysRevLett.126.175001.
9
Towards a compact spherical tokamak fusion pilot plant.迈向紧凑型球形托卡马克聚变示范电厂。
Philos Trans A Math Phys Eng Sci. 2019 Mar 25;377(2141):20170439. doi: 10.1098/rsta.2017.0439.
10
Compact steady-state tokamak performance dependence on magnet and core physics limits.紧凑型稳态托卡马克性能对磁体和堆芯物理极限的依赖。
Philos Trans A Math Phys Eng Sci. 2019 Mar 25;377(2141):20170440. doi: 10.1098/rsta.2017.0440.

血浆烧伤——注意差距。

Plasma burn-mind the gap.

作者信息

Meyer Hendrik

机构信息

UKAEA, Culham Campus, Abingdon , Oxon OX14 3DB, UK.

出版信息

Philos Trans A Math Phys Eng Sci. 2024 Oct 9;382(2280):20230406. doi: 10.1098/rsta.2023.0406. Epub 2024 Aug 26.

DOI:10.1098/rsta.2023.0406
PMID:39183655
原文链接:https://pmc.ncbi.nlm.nih.gov/articles/PMC11423683/
Abstract

The programme to design plasma scenarios for the Spherical Tokamak for Energy Production (STEP), a reactor concept aiming at net electricity production, seeks to exploit the inherent advantages of the spherical tokamak (ST) while making conservative assumptions about plasma performance. This approach is motivated by the large gap between present-day STs and future burning plasmas based on this concept. It is concluded that plasma exhaust in such a device is most likely to be manageable in a double null (DN) configuration, and that high core performance is favoured by positive triangularity (PT) plasmas with an elevated central safety factor. Based on a full technical and physics assessment of external heating and current drive (CD) systems, it was decided that the external CD is provided most effectively by microwaves. Operation with active resistive wall mode (RWM) stabilization as well as high elongation is needed for the most compact solution. The gap between existing devices and STEP is most pronounced in the area of core transport, owing to high normalized plasma pressure in the latter which changes qualitatively the nature of the turbulence controlling transport. Plugging this gap will require dedicated experiments, particularly on high-performance STs, and the development of reduced models that faithfully represent turbulent transport at high normalized pressure. Plasma scenarios in STEP will also need to be such that edge localized modes (ELMs) either do not occur or are small enough to be compatible with material lifetime limits. The high current needed for a power plant-relevant plasma leads to the unavoidable generation of high runaway electron beam current during a disruption, where novel mitigation techniques may be needed. This article is part of the theme issue 'Delivering Fusion Energy - The Spherical Tokamak for Energy Production (STEP)'.

摘要

“能源生产球形托卡马克(STEP)”项目旨在实现净电力生产,该反应堆概念在对等离子体性能做出保守假设的同时,寻求利用球形托卡马克(ST)的固有优势。这种方法的动机在于当前的球形托卡马克与基于该概念的未来燃烧等离子体之间存在巨大差距。得出的结论是,在这种装置中,双零(DN)配置最有可能实现可控的等离子体排出,并且具有升高的中心安全因子的正三角形(PT)等离子体有利于实现高核心性能。基于对外部加热和电流驱动(CD)系统的全面技术和物理评估,决定微波最有效地提供外部电流驱动。对于最紧凑的解决方案,需要采用有源电阻壁模(RWM)稳定以及高拉长比运行。由于STEP中归一化等离子体压力较高,这会定性地改变控制输运的湍流性质,因此现有装置与STEP之间的差距在核心输运领域最为明显。弥补这一差距需要进行专门的实验,特别是在高性能球形托卡马克上,并开发能够忠实代表高归一化压力下湍流输运的简化模型。STEP中的等离子体工况还需要确保边缘局域模(ELM)要么不发生,要么小到足以与材料寿命限制相兼容。与发电厂相关的等离子体所需的高电流会导致在破裂期间不可避免地产生高逃逸电子束电流,可能需要新的缓解技术。本文是主题为“实现聚变能源——能源生产球形托卡马克(STEP)”的一部分。

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