磁约束燃烧等离子体物理的现状与展望

孙有文; 仇志勇; 万宝年

doi:10.7498/aps.73.20240831

摘要

本文从设计和运行托卡马克聚变堆需求的角度, 简要概述了托卡马克高约束运行方案和高能量粒子约束涉及的关键物理的发展现状和挑战. 过去几十年中, 托卡马克高约束模式物理研究取得了重要进展, 明确了聚变堆运行区的主要稳定性和约束的限制条件及其性能优化的主要调控手段, 发展了感应、混合和稳态等若干可能适用于未来托卡马克聚变堆的运行方案. 在反应堆阿尔法粒子加热主导的条件下, 潜在主导阿尔法粒子输运损失的阿尔芬不稳定性的线性谱特征和激发机制得到了充分的理解; 在阿尔芬不稳定性的非线性饱和、阿尔法粒子约束, 及通过加热沉积和微观湍流对等离子体约束的影响等方面开展了大量的实验和理论探索. 当前, 磁约束聚变物理已进入临近点火燃烧等离子体研究的新阶段, 面临着全新的挑战, 如: 聚变堆条件下如何实现高能量阿尔法粒子对等离子体有效自加热; 在阿尔法粒子自加热为主条件下, 如何通过调控等离子体关键参数分布维持等离子体稳定性和高约束性能, 实现聚变堆高效安全运行; 能否建立全尺度模型, 实现聚变堆复杂等离子体的长时间动力学过程的准确预测等. 这些关键问题的解决, 可为未来聚变堆的设计和运行奠定坚实的物理基础, 同时推动等离子体学科的发展.

关键词:

Abstract

Current status and challenges of key physics related to high-confinement operational scenarios and energetic particle confinement are briefly reviewed from the perspective of design and operation of tokamak-based fusion reactors. In the past few decades, significant progress has been made in the research on high-confinement mode physics, i.e. the main stability and confinement constraints on operational window of a fusion reactor have been identified, and some control methods for adjusting plasma kinetic profiles to optimize performance have been developed. Several operational scenarios, including inductive, hybrid and steady-state etc, which are potentially applicable for future reactors, have been developed. In the conditions that fusion alpha particle self-heating is predominant and shear Alfvén wave (SAW) instabilities potentially dominate fusion alpha particle transport, the SAW linear stability properties and excitation mechanisms are understood in depth, and the SAW instabilities nonlinear saturation, alpha particle confinement, and the influence of the heating deposition and the micro-turbulence regulation on fusion profile are under extensive investigation. The magnetically confined fusion research has entered a new stage of ignition and burning plasma physics, and new challenges that are faced are addressed, including whether efficient self-heating of plasmas by fusion alpha particles can be achieved, how the plasma stability and high-confinement can be maintained through the active control of key plasma profiles under the condition of dominant alpha particle heating, and whether it is possible to establish accurate models to predict long time scale complex dynamical evolution of fusion plasmas etc. Solving these key problems will lay a solid scientific foundation for designing and operating future fusion reactors as well as promote the development of plasma science.

Keywords:

作者及机构信息

中国科学院合肥物质科学院研究院, 等离子体物理研究所, 合肥　230031

通信作者: 万宝年, bnwan@ipp.ac.cn

基金项目: 安徽省自然科学基金(批准号: 2208085J39)和国家自然科学基金(批准号: 12275236)资助的课题.

Authors and contacts

Institute of Plasma Physics, Hefei Institute of Physical Science, Chinese Academy of Sciences, Hefei 230031, China

Corresponding author: Wan Bao-Nian, bnwan@ipp.ac.cn

Funds: Project supported by the Natural Science Foundation of Anhui Province, China (Grant No. 2208085J39) and the National Natural Science Foundation of China (Grant No. 12275236).

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施引文献

图 A1 托卡马克装置磁位型

Fig. A1. Magnetic field configuration of a tokamak.

下载: 全尺寸图片幻灯片

图 1 托卡马克聚变堆运行的归一化参数区($q_{95}^{-1},\beta_{\rm N} $)示意图, 其中不同曲线代表一个理想的聚变堆需要满足的不同等离子体物理限制条件的示意分布, 如最低聚变功率需求(蓝色曲线), 稳定性极限限制(红色曲线), 最低聚变增益因子需求限制(绿色曲线)和高能量粒子约束限制(紫色曲线), 以及其他一些限制条件(灰色虚线)等

Fig. 1. A schematic plot of operational window of a tokamak fusion reactor in terms of normalized parameters ($q_{95}^{-1},\beta_{\rm N}$). Different constraints from plasma physics for a fusion reactor, e.g. threshold fusion power (blue curve), stability limit (red curve), threshold fusion gain (green curve), limits from a particle confinement (purple curve), and some other constraints (gray dashed curves) etc.

下载: 全尺寸图片幻灯片

图 2 感应(红色)、混合(绿色)和稳态(蓝色)运行方案的q分布(实线)和压力分布(虚线)示意图

Fig. 2. A schematic plot of q (solid lines) and pressure (dashed lines) profiles for inductive (red), hybrid (green) and steady state (blue) scenarios.

下载: 全尺寸图片幻灯片

图 3 ITER混合运行模式下阿尔芬连续谱和不稳定性示意图, 其中, 横坐标是归一化的径向位置, 纵坐标是频率, 虚线为安全因子分布, EPM表示高能量粒子模, TAE表示环阿尔芬本征模, EAE表示椭圆形变诱发阿尔芬本征模, NAE表示三角形变诱发阿尔芬本征模, 此处取环向模数n = 10

Fig. 3. A schematic plot of shear Alfvén wave continuous spectrum and associated instabilities of ITER hybrid scenario is presented. Here, the horizontal axis represents the normalized minor radius, and the vertical axis is the normalized frequency. The dashed curve corresponds to the q-profile, and a representative toroidal mode number n = 10 is adopted. The frequencies and mode localizations of energetic particle mode (EPM), toroidal Alfvén eigenmode (TAE), ellipticity induced Alfvén eigenmode (EAE) and non-circularity induced Alfvén eigenmode (NAE) are also given.

下载: 全尺寸图片幻灯片

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