利用机器学习代用模型优化控制 DIII-D 中的电子温度曲线

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Shira Morosohk , Zibo Wang , Sai Tej Paruchuri , Tariq Rafiq , Eugenio Schuster
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引用次数: 0

摘要

托卡马克作为潜在核聚变反应堆的可行性取决于能否使等离子体保持稳定状态,同时达到尽可能高的温度、密度和约束时间。托卡马克方案开发试图找到能满足所有这些条件的等离子体状态,并能在特定的硬件限制条件下使用。这就要求能够控制等离子体特性,如归一化贝塔、内部电感、安全系数、旋转等。与其他一些属性相比,电子温度()曲线这一属性受到的关注较少,但对于实现高性能却同样重要。在这项工作中,线性二次积分(LQI)控制用于开发 DIII-D 中电子温度曲线的控制器。该控制器基于一个线性化模型,该模型来自描述电子温度演变的传输方程,并包括神经网络代理模型 NubeamNet 和 MMMnet 的贡献。利用 COTSIM 对控制器进行了模拟测试,证明它能够跟踪目标轮廓。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Optimal control of the electron temperature profile in DIII-D using machine learning surrogate models

The viability of the tokamak as a potential fusion reactor depends on the ability to keep the plasma in a stable regime while achieving temperatures, densities, and confinement times that are as high as possible. Tokamak scenario development attempts to find plasma regimes that achieve all of these conditions and are accessible with a given set of hardware constraints. This requires the ability to control plasma properties such as the normalized beta, the internal inductance, safety factor, rotation, etc. One property that has received less attention than some of the others, but is no less critical to achieving high performance, is the electron temperature (Te) profile. In this work, Linear Quadratic Integral (LQI) control is used to develop a controller for the electron temperature profile in DIII-D. The controller is based on a linearized model derived from the transport equation that describes the evolution of the electron temperature, and includes contributions from the neural network surrogate models NubeamNet and MMMnet. The controller is tested in simulation using COTSIM, and is proven capable of tracking a target Te profile.

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来源期刊
Fusion Engineering and Design
Fusion Engineering and Design 工程技术-核科学技术
CiteScore
3.50
自引率
23.50%
发文量
275
审稿时长
3.8 months
期刊介绍: The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.
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