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arXiv 2603.12972physics.plasm-ph
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关于托卡马克等离子体受控终止时间尺度的研究

On the timescales of controlled termination of tokamak plasmas

École Polytechnique Fédérale de Lausanne (EPFL)(洛桑联邦理工学院)

Simon Van Mulders, Olivier Sauter

AI总结:

研究通过RAPTOR代码分析不同托卡马克装置中受控终止时间尺度的演变,发现内部电感与电阻比τ_LR可作为跨设备比较的关键时间尺度,为快速终止方案提供理论依据。

摘要:

RAPTOR代码用于研究受控终止欧姆等离子体的时间尺度如何从现有托卡马克如TCV和JET扩展到反应堆级托卡马克如ITER和DEMO。研究显示,将等离子体电流I_p从平坦顶值下降至20%并持续Δt_ramp-down=τ_LR=L_i/R,可产生自相似的电流密度峰值,表明τ_LR是跨设备比较的相关时间尺度,其值分别为TCV 0.033s,JET 2.87s,ITER 63.2s,DEMO 166.9s。τ_LR易于评估,可在系统代码或实时控制系统中计算。模拟的Δt_ramp-down=τ_LR情况下,末端归一化内部电感ℓ_i3限制在2以下。比τ_LR更快的I_p下降会导致边界回路电压反转,形成反向电流层,伴随ℓ_i3>2,中心区域磁剪低且压力剖面尖峰。ITER和DEMO预期的等离子体体积和 elongation 减小可抵消电流密度反转和ℓ_i3增加,同时改善垂直稳定性控制,可能实现更快的I_p下降场景。需通过实验和理论研究验证此类快速终止方案的可行性,尤其需关注垂直位置控制、形状控制和(电阻性)beta限制。提出一个简单的分析模型,基于0D工程参数估算不同托卡马克和操作点的τ_LR。

英文摘要:

The RAPTOR code is used to model how the time required for controlled termination of Ohmic plasmas scales from present tokamaks like TCV and JET, to reactor-grade tokamaks like ITER and DEMO. We show that ramping the plasma current $I_p$ down to 20% of the flat-top value over a time $Δt_{ramp-down}=τ_{LR}=L_i/R$, with internal inductance $L_i$ and resistance $R$ evaluated at flat-top conditions, results in an approximately self-similar peaking of the current density for these four tokamaks, indicating the adequacy of $τ_{LR}$ as a relevant timescale for cross-machine comparison, yielding $τ_{LR} =$ 0.033s (TCV), 2.87s (JET), 63.2s (ITER) and 166.9s (DEMO). Note that $τ_{LR}$ is easy to evaluate, both in systems codes and on a real-time control system. For the simulated ramp-downs with $Δt_{ramp-down}=τ_{LR}$, the end-of-ramp-down normalized internal inductance $\ell_{i3}$ is limited below 2. An $I_p$ ramp-down faster than $τ_{LR}=L_i/R$ requires a reversal of the boundary loop voltage and leads to the formation of a broad plasma layer carrying current in the direction opposite to the total plasma current, concomitant with $\ell_{i3}>2$, a central region with low magnetic shear and strongly peaked pressure profiles. Significant reduction of plasma volume and elongation, as foreseen for ITER and DEMO, is shown to counteract the reversal of current density and the $\ell_{i3}$ increase, while easing vertical stability control, potentially enabling faster $I_p$ ramp-down scenarios. Experimental and theoretical studies should be performed to test the feasibility of such fast termination scenarios, notably with respect to vertical position control, shape control and (resistive) beta limits. A simple analytical model is proposed and applied to estimate $τ_{LR}$ based on 0D engineering parameters for different tokamaks and for different operating points.

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