Self-consistent equilibrium and transport simulations for NSTX-U plasmas enhanced via machine learning surrogate models

IF 2 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Brian Leard , Tariq Rafiq , Ian Ward , Franco Galfrascoli , Eugenio Schuster , Alexei Pankin , Marina Gorelenkova
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Abstract

The Control-Oriented Transport SIMulator (COTSIM) is an advanced equilibrium and transport code designed for simulating tokamak discharges at computational speeds suitable for control applications. COTSIM’s modular framework enables users to select models that balance accuracy with speed according to specific needs, allowing the code to operate from fast to faster-than-real-time performance levels. This work presents recent enhancements to COTSIM’s predictive accuracy for NSTX-U scenarios, achieved by integrating neural-network-based surrogate models and self-consistent equilibrium calculations. To improve source deposition predictions, a surrogate model for NUBEAM has been incorporated. Additionally, a surrogate model for the Multi-Mode Module (MMM) now supports predictions of anomalous thermal, momentum, and particle diffusivities—key factors for modeling the evolution of temperature and rotation. Each surrogate model was specifically trained for the NSTX-U operational regime to enhance COTSIM’s accuracy while maintaining computational efficiency. Moreover, COTSIM now couples fixed-boundary equilibrium solvers with its transport solvers, enabling self-consistent predictions of plasma profiles and equilibrium evolution over the discharge. Simulation results demonstrate strong agreement between COTSIM and TRANSP predictions for NSTX-U discharges. These substantial advancements expand COTSIM’s utility in model-based control applications for NSTX-U. Potential applications include simultaneous optimization of equilibrium and transport scenarios, integration into digital twins, real-time profile estimation (e.g., temperature and rotation) from limited or noisy measurements, and advanced feedback-based scenario control.
通过机器学习代理模型增强NSTX-U等离子体的自洽平衡和输运模拟
面向控制的传输模拟器(COTSIM)是一个先进的平衡和传输代码,设计用于模拟托卡马克放电的计算速度适合控制应用。COTSIM的模块化框架使用户能够根据特定需求选择平衡准确性和速度的模型,允许代码从快速到比实时性能水平更快地运行。这项工作展示了最近COTSIM对NSTX-U场景的预测精度的增强,通过集成基于神经网络的代理模型和自洽平衡计算来实现。为了改进源沉积预测,我们采用了NUBEAM的替代模型。此外,多模模块(MMM)的替代模型现在支持异常热、动量和粒子扩散的预测,这些都是模拟温度和旋转演变的关键因素。每个代理模型都针对NSTX-U操作机制进行了专门的训练,以提高COTSIM的准确性,同时保持计算效率。此外,COTSIM现在将固定边界平衡求解器与传输求解器耦合在一起,实现了等离子体轮廓和放电过程中平衡演化的自一致预测。模拟结果表明,COTSIM和TRANSP对NSTX-U排放的预测非常一致。这些实质性的进步扩展了COTSIM在NSTX-U基于模型的控制应用中的实用性。潜在的应用包括平衡和运输场景的同时优化,集成到数字孪生,从有限或有噪声的测量中实时估计轮廓(例如温度和旋转),以及基于反馈的高级场景控制。
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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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