Enabling High-Degree-of-Freedom Thermal Engineering Calculations via Lightweight Machine Learning

Author:

Tian Yajing12ORCID,Wang Yuyang12,Yin Shasha12,Lu Jia12,Hu Yu12

Affiliation:

1. State Key Laboratory of Advanced Nuclear Energy Technology, Chengdu 610213, China

2. Nuclear Power Institute of China, Chengdu 610213, China

Abstract

U-tube steam generators (UTSGs) are crucial in nuclear power plants, serving as the interface between the primary and secondary coolant loops. UTSGs ensure efficient heat exchange, operational stability, and safety, directly impacting the plant’s efficiency and reliability. Existing UTSG models have fixed structures, which can only be used when certain parameters are given as model input. Such constraints hinder their ability to accommodate the diverse operating conditions, where input and output parameters can vary significantly. To address this challenge, we propose a machine learning-based method for developing a high-degree-of-freedom UTSG thermal model. The most notable feature of this approach is its capacity to flexibly interchange input and output parameters. By adopting comprehensive parameter sensitivity analysis, the most efficient method for training dataset generation is determined. Leveraging a lightweight machine learning method, the prediction accuracy for all UTSG parameters is improved to within 2.1%. The flexibility of the proposed machine learning approach ensures that the UTSG model can accommodate any type of parameter input without extensive reconfiguration of the model structure, thereby enhancing its applicability and robustness in real-world applications.

Publisher

MDPI AG

Reference19 articles.

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3. Breeze, P. (2017). Chapter 4—Water-Cooled Reactors. Nuclear Power, Academic Press.

4. Ali, M.R.A. (1976). Lumped Parametar, State Variable Dynamic Models for U-Tube Recirculation Type Nuclear Steam Generators, The University of Tennessee.

5. Development of a seven-region lumped parameter nonlinear dynamic model for U-tube recirculation nuclear steam generator;Zhong;Ann. Nucl. Energy,2022

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