Parameter Identification for a Reduced Transport Model in Fusion Plasma

IF 2.9 3区 工程技术 Q1 ENGINEERING, MULTIDISCIPLINARY
Louis Lamérand, Didier Auroux, Francesca Rapetti
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引用次数: 0

Abstract

Two-dimensional transport codes for the simulation of tokamak plasmas are simplified versions of full 3D fluid models, where plasma turbulence is averaged out. One of the main challenges in such reduced models is to accurately reconstruct transverse transport fluxes that arise from the averaging of stresses due to fluctuations. These transverse fluxes are typically approximated by ad-hoc diffusion coefficients (turbulent eddy viscosity), manually adjusted to align numerical solutions with experimental observations. They can vary significantly depending on the type of tokamak, the experimental conditions, and even the location within the device, severely limiting the predictive capability of these codes for new configurations. To address this issue, we recently proposed an innovative approach to fusion plasma simulations by introducing two additional transport equations for turbulence-related variables (specifically, the turbulent kinetic energy κ $$ \kappa $$ and its dissipation rate ε $$ \varepsilon $$ ) into the mean-flow system to estimate the turbulent eddy viscosity. This approach also introduces new free parameters, but they are primarily governed by the underlying transport physics and thus exhibit considerably less variation across devices and plasma regions. In this article, we continue an ongoing study of data assimilation techniques to determine the free parameters of the κ ε $$ \kappa -\varepsilon $$ model for transverse turbulent plasma transport. Based on digital twin experiments within the framework of equations averaged over the magnetic surfaces of the tokamak, we provide an in-depth study of optimization strategies to improve the performance of the calibration algorithm in a complex configuration with considerable scale variation of the parameters.

聚变等离子体中简化输运模型的参数辨识
用于模拟托卡马克等离子体的二维传输码是全三维流体模型的简化版本,其中等离子体湍流是平均的。这种简化模型的主要挑战之一是准确地重建由于波动引起的应力平均而产生的横向输运通量。这些横向通量通常由特设扩散系数(湍流涡流粘度)近似,手动调整以使数值解与实验观测结果一致。它们可以根据托卡马克的类型、实验条件甚至设备内的位置而发生显著变化,严重限制了这些代码对新配置的预测能力。为了解决这个问题,我们最近提出了一种创新的方法来模拟聚变等离子体,通过引入两个额外的湍流相关变量的输运方程(具体来说,将紊流动能κ $$ \kappa $$及其耗散率ε $$ \varepsilon $$)引入平均流系统,估算紊流涡动粘度。这种方法也引入了新的自由参数,但它们主要由潜在的输运物理控制,因此在设备和等离子体区域之间表现出相当小的变化。在本文中,我们继续进行数据同化技术的研究,以确定κ−ε $$ \kappa -\varepsilon $$横向湍流等离子体输运模型的自由参数。基于在托卡马克磁面平均方程框架内的数字孪生实验,我们深入研究了优化策略,以提高在参数有较大尺度变化的复杂配置下校准算法的性能。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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来源期刊
CiteScore
5.70
自引率
6.90%
发文量
276
审稿时长
5.3 months
期刊介绍: The International Journal for Numerical Methods in Engineering publishes original papers describing significant, novel developments in numerical methods that are applicable to engineering problems. The Journal is known for welcoming contributions in a wide range of areas in computational engineering, including computational issues in model reduction, uncertainty quantification, verification and validation, inverse analysis and stochastic methods, optimisation, element technology, solution techniques and parallel computing, damage and fracture, mechanics at micro and nano-scales, low-speed fluid dynamics, fluid-structure interaction, electromagnetics, coupled diffusion phenomena, and error estimation and mesh generation. It is emphasized that this is by no means an exhaustive list, and particularly papers on multi-scale, multi-physics or multi-disciplinary problems, and on new, emerging topics are welcome.
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