Mathematical modeling and connectivity-enhanced segmentation of void fraction in two-phase flow CT images

IF 2.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy Pub Date : 2025-07-04 DOI:10.1016/j.anucene.2025.111693

Zirou Jiang , Shuo Xu , Jiahao Chang , Jichen Miao , Yuewen Sun

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引用次数: 0

Abstract

The accurate assessment of two-phase flow in high-temperature gas-cooled reactors (HTGRs) is crucial for nuclear safety and operational efficiency. Void fraction, a key parameter for evaluating two-phase flow and core stability, can be derived from CT images. In static conditions, its measurement reduces to a segmentation task, whereas dynamic conditions require pixel-level corrections due to nonlinear tomographic effects. This study formulates mathematical models addressing these effects and proposes TransUNet-CC, an enhanced segmentation framework incorporating void connectivity priors. Experimental results on CT images reconstructed via FBP, ADMM-TV, and DRP confirm its superior performance, achieving a Dice coefficient of 0.8358 and RVFE of 6.93%. Notably, the DRP algorithm provides high-resolution, low-noise reconstructions, ensuring precise void fraction estimation. This work advances image-based diagnostics for nuclear reactor monitoring, offering a robust solution for complex flow conditions in HTGRs.

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两相流CT图像中空隙率的数学建模与连通性增强分割

高温气冷堆两相流的准确评估对核安全和运行效率至关重要。孔隙率是评价岩心两相流动和稳定性的关键参数，可以从CT图像中得到。在静态条件下，其测量减少到分割任务，而动态条件下，由于非线性层析效应需要像素级校正。本研究制定了解决这些影响的数学模型，并提出了TransUNet-CC，这是一种包含空洞连接先验的增强分割框架。通过FBP、ADMM-TV和DRP重建CT图像的实验结果证实了其优越的性能，Dice系数为0.8358，RVFE为6.93%。值得注意的是，DRP算法提供了高分辨率、低噪声的重建，确保了精确的空隙率估计。这项工作推进了基于图像的核反应堆监测诊断，为高温高温堆中复杂的流动条件提供了一个强大的解决方案。

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

Annals of Nuclear Energy 工程技术-核科学技术

CiteScore

4.30

自引率

21.10%

发文量

632

审稿时长

7.3 months

期刊介绍： Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.