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Deep Learning Models for ADITYA-U MHD Equilibrium

Published 6 Jul 2026 in physics.plasm-ph | (2607.04865v1)

Abstract: This work presents deep learning models to predict magnetohydrodynamic equilibrium parameters and profiles for the ADITYA-U tokamak. A synthetic free-boundary equilibrium dataset consisting of 100,760 cases was generated using the pyIPREQ Grad-Shafranov solver, with inputs derived from 766 ADITYA-U plasma discharges and constrained to experimentally relevant circular limiter plasmas near the flat-top phase. Several deep learning approaches were investigated for predicting scalar equilibrium quantities, one-dimensional safety factor profiles and two-dimensional poloidal flux profiles. These approaches included Dense neural networks, principal component analysis based reduced-order models, one-dimensional and two-dimensional convolutional neural networks, and physics-informed neural networks incorporating Grad-Shafranov residual constraints. In addition, an inverse model was developed to estimate poloidal field coil currents from desired plasma equilibrium conditions. The results demonstrate that key equilibrium parameters and profiles can be accurately estimated within the operational domain represented by the dataset. The developed models provide a computationally efficient alternative to conventional equilibrium estimation and can be useful for real-time plasma control, rapid equilibrium analysis, and experimental planning in ADITYA-U operations.

Summary

  • The paper introduces surrogate deep learning models leveraging a synthetic equilibrium dataset to accurately predict MHD parameters in the ADITYA-U tokamak.
  • It integrates PCA, CNN architectures, and PINN constraints to achieve median errors below key thresholds and enable swift, real-time control.
  • Physical insights are validated by comparing model predictions with experimental distributions, highlighting potential for broader fusion device applications.

Deep Learning Models for ADITYA-U MHD Equilibrium: Technical Analysis

Synthetic Dataset Construction and Physical Operational Domain

Accurate modeling of MHD equilibrium in ADITYA-U tokamak is addressed through the development of surrogate models trained on an expansive synthetic equilibrium dataset. The dataset comprises 100,760 instances, generated using the pyIPREQ Grad-Shafranov free-boundary solver with inputs from 766 ADITYA-U discharges. Physical realism is ensured via physics-informed filtering criteria, targeting flat-top phase, circular limiter configurations, and exclusion of nonphysical or numerically unstable cases. Key current profile parameters (α\alpha, β\beta, γ\gamma) are determined through data-driven procedures, including Bayesian optimization and empirically constructed probabilistic models for poloidal beta (βp\beta_p). The operational domain spans Ip∈[1.01×105,1.95×105]I_p \in [1.01\times 10^5, 1.95\times 10^5] A, q0∈[0.9,1.5]q_0 \in [0.9, 1.5], q1>2.0q_1 > 2.0, and βp∈[0.05,0.4]\beta_p \in [0.05, 0.4], accurately capturing ADITYA-U's experimental regime.

The dataset's statistical distributions of equilibrium quantities are shown to be consistent with experimental measurements; e.g., the sampled plasma current centroid matches the observed distribution (Figure 1). Figure 1

Figure 1: Distribution of plasma current centroid positions sampled during equilibrium generation, showing consistency with experimentally observed flat-top data.

Comprehensive visualization of equilibrium distributions in (βp,ℓi)(\beta_p,\ell_i) space, qq-profile ensembles, and LCFS positions confirm broad but physically plausible coverage within the prescribed operational ranges.

Forward Models for Equilibrium Scalars and Inverse Coil Currents

Dense neural network architectures are constructed for scalar equilibrium parameters (β\beta0) and coil currents (β\beta1, β\beta2, β\beta3), optimized via Hyperband search. Scalar prediction models achieve high accuracy, with median absolute errors well within physically relevant thresholds (e.g., β\beta4 for β\beta5 and β\beta6 for β\beta7), despite operational variability. The inverse model for coil currents is shown to infer actuator settings with median errors of β\beta8 A/turn for β\beta9 and γ\gamma0 A/turn for γ\gamma1, supporting real-time experiment planning and actuator trend analysis.

Reduced-Order and Convolutional Surrogate Models for Profile Prediction

Safety Factor (γ\gamma2) Profile Models

Principal Component Analysis is leveraged for dimensionality reduction, revealing that γ\gamma3-profiles are nearly four-dimensional (99.99% explained variance). Dense regressors for PCA-coefficients yield median absolute errors γ\gamma4 for γ\gamma5 and γ\gamma6 for γ\gamma7 (Figure 2). Figure 2

Figure 2: Mean absolute errors for reconstructed γ\gamma8-profiles demonstrate highly efficient low-rank representations and accurate predictions for both core and edge safety factors.

Alternatively, 1d-CNNs predicting γ\gamma9 enable physics-constrained monotonicity and outperform PCA models on local edge accuracy, with core errors βp\beta_p0 and edge errors βp\beta_p1 (Figure 3). Figure 3

Figure 3: Distribution of CNN-predicted βp\beta_p2-profiles visualized for median, 99th percentile, and worst-case errors, highlighting robustness and physical consistency.

Poloidal Flux (βp\beta_p3) Profile Models and Physics-Informed Constraints

For βp\beta_p4 profiles, PCA models achieve 99.99% explained variance in five modes, but optimal accuracy requires up to 13 modes, as shown by improved mean absolute errors and reduced Grad-Shafranov residuals. Both PCA and CNN models are formulated as PINNs, directly incorporating Grad-Shafranov operator residual as a penalizing loss term. CNN models, via upsampling, achieve finer local accuracy but introduce spatially confined distortions; PCA models distribute errors globally and preserve dominant equilibrium structures (Figure 4). Figure 4

Figure 4: Median and 99th percentile CNN reconstructions of βp\beta_p5 profiles display agreement in major features with some localized error, confirming suitability for real-time equilibrium inference.

Strong numerical claims are substantiated: PCA and CNN PINNs reconstruct full 2D profiles with median errors βp\beta_p6 across the operational domain, residuals approaching solver accuracy, and inference times βp\beta_p7 ms per equilibrium on CPU, suggesting applicability for real-time control systems.

Comparative Analysis and Physical Insights

The study establishes the operational domain as admitting efficient low-rank representations, with most variability encapsulated in a small number of latent dimensions, consistent with global equilibrium physics. PCA-based models excel at smooth global reconstructions, while CNNs capture local spatial variability more effectively. PINN formulations regularize out-of-domain predictions, ensuring physical compatibility.

Difficulties in predicting certain parameters (e.g., βp\beta_p8, βp\beta_p9, Ip∈[1.01×105,1.95×105]I_p \in [1.01\times 10^5, 1.95\times 10^5]0) indicate information bottlenecks in available diagnostics, motivating future inclusion of richer profile measurements and advanced regression strategies. Model limitations arise from dataset restriction to circular limiters; expansion to shaped plasmas and broader current-profile parameterization is feasible given the framework.

Practical and Theoretical Implications

Practically, these models allow rapid equilibrium prediction and actuator planning via direct mapping from measured signals to key equilibrium descriptors. Computational efficiency facilitates integration with plasma control systems, and PINN-based regularization enhances trustworthiness of real-time surrogates. Theoretically, the methodology demonstrates that well-designed synthetic datasets and low-rank surrogates can replace slow iterative solvers for operational parameter regimes. Extrapolation to other devices (e.g., KSTAR, EAST, JET) is supported by analogous studies using similar approaches [2020Joung, 2026Rutigliano, 2025Zheng].

Anticipated future developments include incorporation of advanced diagnostic signals, uncertainty-aware ensembles, transformer-based architectures, and extension to shaped plasma regimes. Inclusion of formal stability analysis and broader data-driven modeling will address current limitations and increase applicability for fusion device control.

Conclusion

This technical evaluation demonstrates that deep learning models, particularly PINNs and reduced-rank representations, are highly effective for fast MHD equilibrium prediction in ADITYA-U tokamak within experimentally relevant operational domains. The study provides authoritative evidence for model accuracy (Ip∈[1.01×105,1.95×105]I_p \in [1.01\times 10^5, 1.95\times 10^5]1 ms inference, absolute errors Ip∈[1.01×105,1.95×105]I_p \in [1.01\times 10^5, 1.95\times 10^5]2 in key quantities), scalability, and robustness. Physical regularization via PDE constraints is essential for maintaining predictive fidelity. The framework is immediately applicable to real-time control, experiment planning, and rapid data interpretation; future work will broaden operational scope and diagnostic integration. The systematic construction and evaluation of surrogate models on comprehensive synthetic datasets set a paradigm for data-driven equilibrium modeling across tokamak devices (2607.04865).

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