等离子燃烧--注意间隙。

IF 4.3 3区 综合性期刊 Q1 MULTIDISCIPLINARY SCIENCES
Hendrik Meyer
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引用次数: 0

摘要

能源生产球形托卡马克(STEP)是一个以净发电为目标的反应堆概念,其等离子体方案设计计划旨在利用球形托卡马克(ST)的固有优势,同时对等离子体性能做出保守假设。之所以采用这种方法,是因为目前的 ST 与基于这一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,这种装置中的等离子体废气最有可能在双空(DN)配置中得到控制,而具有较高中心安全系数的正三角形(PT)等离子体则有利于实现较高的核心性能。根据对外部加热和电流驱动(CD)系统进行的全面技术和物理评估,决定外部 CD 由微波提供最为有效。为了实现最紧凑的解决方案,需要采用主动电阻壁模式(RWM)稳定运行和高伸长率。现有设备与 STEP 之间的差距在堆芯传输领域最为明显,原因是后者的归一化等离子体压力较高,从本质上改变了控制传输的湍流性质。要弥补这一差距,需要进行专门的实验,特别是在高性能 ST 上进行实验,并开发能够忠实反映高归一化压力下湍流输运的简化模型。STEP 中的等离子体方案还需要确保边缘局部模式 (ELM) 不发生或足够小,以符合材料寿命限制。发电厂相关等离子体所需的大电流导致在中断期间不可避免地产生高失控电子束电流,这可能需要新的缓解技术。本文是 "提供聚变能源--用于能源生产的球形托卡马克(STEP)"专题的一部分。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Plasma burn-mind the gap.

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)'.

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来源期刊
CiteScore
9.30
自引率
2.00%
发文量
367
审稿时长
3 months
期刊介绍: Continuing its long history of influential scientific publishing, Philosophical Transactions A publishes high-quality theme issues on topics of current importance and general interest within the physical, mathematical and engineering sciences, guest-edited by leading authorities and comprising new research, reviews and opinions from prominent researchers.
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