Advanced scenarios for ITER operation

Advanced scenarios for ITER operation
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DOI:
10.1088/0741-3335/47/5a/003
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发表时间:
2004-10
影响因子:
2.2
通讯作者:
A. Sips
A. Sips
中科院分区:
物理与天体物理2区
文献类型:
--
作者:
A. Sips

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在使用磁约束的热核聚变研究中,托卡马克是实现反应堆所需条件的主要候选者。一个国际实验,ITER,被提议作为证明聚变能的科学和技术可行性的下一个必要和关键步骤。ITER是制造和研究以自热为主的等离子体。这将为在反应堆相关条件下探索α-粒子加热、等离子体湍流和湍流输运、等离子体压力的稳定性限制以及功率和粒子的排气提供独特的机会。在实验、理论和建模方面获得的重要新结果,使人们能够更好地理解托卡马克等离子体中发生的物理过程,并增强人们对ITER将实现其目标的信心。特别是在提高托卡马克性能的研究方面取得了进展,旨在将放电脉冲长度延长到稳态运行(高级场景)。标准托卡马克放电的电流密度向等离子体中心单调增加。另一方面,高级场景使用改进的电流密度剖面。不同的高级方案包括(i)等离子体维持一个具有平坦电流密度分布(零磁剪切)的中心区域,能够在高等离子体压力下稳定运行;(ii)放电具有电流密度分布的离轴最大值(核心的反向磁剪切),能够形成内部传输屏障,以增加等离子体的限制。介绍了先进托卡马克放电的物理原理,并概述了不同托卡马克实验的最新结果。实验之间的国际合作旨在更好地理解、控制和优化这些等离子体。在ITER中探索先进场景的能力是非常可取的,以便验证今天在实验中获得的结果,并展示显着增加托卡马克经济吸引力的潜力。
In thermonuclear fusion research using magnetic confinement, the tokamak is the leading candidate for achieving the conditions required for a reactor. An international experiment, ITER, is proposed as the next essential and critical step on the path to demonstrating the scientific and technological feasibility of fusion energy. ITER is to produce and study plasmas dominated by self-heating. This would give unique opportunities to explore, in reactor relevant conditions, the physics of α-particle heating, plasma turbulence and turbulent transport, stability limits to the plasma pressure and exhaust of power and particles. Important new results obtained in experiments, theory and modelling, enable an improved understanding of the physical processes occurring in tokamak plasmas and give enhanced confidence that ITER will achieve its goals. In particular, progress has been made in research to raise the performance of tokamaks, aimed to extend the discharge pulse length towards steady-state operation (advanced scenarios). Standard tokamak discharges have a current density increasing monotonically towards the centre of the plasma. Advanced scenarios, on the other hand, use a modified current density profile. Different advanced scenarios range from (i) plasmas that sustain a central region with a flat current density profile (zero magnetic shear), capable of operating stationary at high plasma pressure, to (ii) discharges with an off-axis maximum of the current density profile (reversed magnetic shear in the core), able to form internal transport barriers, to increase the confinement of the plasma. The physics of advanced tokamak discharges is described, together with an overview of recent results from different tokamak experiments. International collaboration between experiments aims to provide a better understanding, control and optimization of these plasmas. The ability to explore advanced scenarios in ITER is very desirable, in order to verify the results obtained in experiments today and to demonstrate the potential to significantly increase the economic attractiveness of the tokamak.