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arxiv_ml 70% Match Research Paper / Benchmark Contribution Nuclear engineers,Thermal-hydraulic engineers,AI/ML researchers in energy systems 19 hours ago

Aggregation of Published Non-Uniform Axial Power Data for Phase II of the OECD/NEA AI/ML Critical Heat Flux Benchmark

generative-ai › diffusion-models
📄 Abstract

Abstract: Critical heat flux (CHF) marks the onset of boiling crisis in light-water reactors, defining safe thermal-hydraulic operating limits. To support Phase II of the OECD/NEA AI/ML CHF benchmark, which introduces spatially varying power profiles, this work compiles and digitizes a broad CHF dataset covering both uniform and non-uniform axial heating conditions. Heating profiles were extracted from technical reports, interpolated onto a consistent axial mesh, validated via energy-balance checks, and encoded in machine-readable formats for benchmark compatibility. Classical CHF correlations exhibit substantial errors under uniform heating and degrade markedly when applied to non-uniform profiles, while modern tabular methods offer improved but still imperfect predictions. A neural network trained solely on uniform data performs well in that regime but fails to generalize to spatially varying scenarios, underscoring the need for models that explicitly incorporate axial power distributions. By providing these curated datasets and baseline modeling results, this study lays the groundwork for advanced transfer-learning strategies, rigorous uncertainty quantification, and design-optimization efforts in the next phase of the CHF benchmark.

Key Contributions

This work compiles and digitizes a broad CHF dataset covering uniform and non-uniform axial heating conditions to support the OECD/NEA AI/ML CHF benchmark. It highlights the limitations of classical correlations and neural networks trained solely on uniform data when applied to spatially varying scenarios, underscoring the need for models that explicitly incorporate axial power distribution.

Business Value

Enhances the safety and operational efficiency of nuclear reactors by improving the accuracy of Critical Heat Flux (CHF) predictions, which are critical for defining safe operating limits.