Evaluation of COBRA-TF prediction performance enhanced by machine learning-based CHF models

IF 3.2 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Congshan Mao, Yue Jin
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引用次数: 0

Abstract

This study investigates the integration of machine learning (ML) techniques into the thermal-hydraulic code COBRA-TF as a foundational advancement for predictive modeling in complex multiphase energy systems. Accurate prediction of critical heat flux (CHF) is essential not only for nuclear reactor safety and performance, but also for a wide range of high-efficiency energy systems that rely on advanced heat transfer, including concentrated solar power, supercritical CO2 cycles, fission and fusion energy systems, and next-generation thermal desalination and storage technologies. Four ML models were developed and assessed, including two pure data-driven artificial neural networks (ANN) with 3- and 4-layer architectures, as well as two physics-informed machine learning (PIML) variants that embed physical constraints derived from the classical Zuber correlation. The models were trained and validated using the NRC CHF dataset and subsequently integrated into the COBRA-TF at the source-code level, enabling efficient and real-time hybrid modeling. Testing across diverse operating conditions demonstrated that all ML-enhanced COBRA-TF models substantially outperformed the legacy tool in both accuracy and stability. The PIML-enhanced models, particularly the PIML-4L model, achieve the lowest mean absolute error (MAE) and mean absolute percentage error (MAPE) among all tested models. While PIML-3L yields the lowest RMSE, PIML-4L performs best in normalized metrics such as rRMSE, indicating better control of extreme deviations. Error-based analysis further reveals that at least 80 % of predictions from all models fall within a ±15 % relative error range. PIML-3L achieves the highest accuracy under strict error tolerances (≤5 %), while PIML-4L performs best in the moderate error range (5–15 %), demonstrating superior robustness. Overall, it was concluded that integrating ML—especially PIML—into COBRA-TF significantly improves its CHF prediction capabilities, with PIML-4L offering the most comprehensive performance gain.
基于机器学习的CHF模型增强COBRA-TF预测性能的评价
本研究探讨了将机器学习(ML)技术集成到热工代码COBRA-TF中,作为复杂多相能源系统预测建模的基础进展。准确预测临界热流密度(CHF)不仅对核反应堆的安全和性能至关重要,而且对依赖先进传热的各种高效能源系统也至关重要,包括聚光太阳能发电、超临界二氧化碳循环、裂变和聚变能源系统以及下一代热脱盐和储存技术。开发并评估了四种机器学习模型,包括两种纯数据驱动的人工神经网络(ANN),具有3层和4层架构,以及两种物理信息机器学习(PIML)变体,该变体嵌入了源自经典Zuber相关性的物理约束。这些模型使用NRC CHF数据集进行训练和验证,随后在源代码级别集成到COBRA-TF中,实现了高效和实时的混合建模。在不同操作条件下的测试表明,所有ml增强的COBRA-TF模型在准确性和稳定性方面都大大优于传统工具。PIML-4L模型的平均绝对误差(MAE)和平均绝对百分比误差(MAPE)在所有测试模型中最低。虽然PIML-3L产生最低的RMSE,但PIML-4L在标准化指标(如rRMSE)中表现最好,表明可以更好地控制极端偏差。基于误差的分析进一步表明,所有模型的预测中至少有80%落在±15%的相对误差范围内。PIML-3L在严格的误差容限(≤5%)下具有最高的精度,而PIML-4L在中等误差范围(5 - 15%)下具有最佳的精度,具有较好的鲁棒性。总的来说,我们得出的结论是,将ml(尤其是piml)集成到COBRA-TF中可以显著提高其CHF预测能力,其中PIML-4L提供了最全面的性能增益。
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
Progress in Nuclear Energy
Progress in Nuclear Energy 工程技术-核科学技术
CiteScore
5.30
自引率
14.80%
发文量
331
审稿时长
3.5 months
期刊介绍: Progress in Nuclear Energy is an international review journal covering all aspects of nuclear science and engineering. In keeping with the maturity of nuclear power, articles on safety, siting and environmental problems are encouraged, as are those associated with economics and fuel management. However, basic physics and engineering will remain an important aspect of the editorial policy. Articles published are either of a review nature or present new material in more depth. They are aimed at researchers and technically-oriented managers working in the nuclear energy field. Please note the following: 1) PNE seeks high quality research papers which are medium to long in length. Short research papers should be submitted to the journal Annals in Nuclear Energy. 2) PNE reserves the right to reject papers which are based solely on routine application of computer codes used to produce reactor designs or explain existing reactor phenomena. Such papers, although worthy, are best left as laboratory reports whereas Progress in Nuclear Energy seeks papers of originality, which are archival in nature, in the fields of mathematical and experimental nuclear technology, including fission, fusion (blanket physics, radiation damage), safety, materials aspects, economics, etc. 3) Review papers, which may occasionally be invited, are particularly sought by the journal in these fields.
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