Advances in Thermal–Hydraulic and Multiphase Flow Research in Nuclear Engineering

A special issue of Fluids (ISSN 2311-5521). This special issue belongs to the section "Flow of Multi-Phase Fluids and Granular Materials".

Deadline for manuscript submissions: 13 November 2026 | Viewed by 449

Special Issue Editors


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Guest Editor
Institute for Integrated Radiation and Nuclear Science, Kyoto University, Asashironishi 2-1010, Kumatori, Sennan, Osaka 590-0494, Japan
Interests: thermohydraulics; heat transfer; two-phase flow

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Guest Editor
Sino-French Institute of Nuclear Engineering and Technology, Sun Yat-sen University, Zhuhai 519000, China
Interests: reactor structural mechanics; fluid-structure coupling vibration

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Guest Editor Assistant
Sino-French Institute of Nuclear Engineering and Technology, Sun Yat-sen University, Zhuhai 519000, China
Interests: reduced-order model; flow-induced vibration; reactor thermal-hydraulic

Special Issue Information

Dear Colleagues,

This Special Issue highlights how data-driven methods can improve fluid mechanics research and applications in nuclear engineering. We welcome work that uses machine learning, modern data analytics, and hybrid physics–data approaches to better understand, predict, and control complex thermal–hydraulic and multiphase flows in nuclear systems, with the goal of supporting safer and more efficient design and operation. Topics of interest include (but are not limited to): Data-driven turbulence modeling and closure strategies for nuclear thermal–hydraulics; Surrogate models and fast prediction tools for CFD and system codes; Hybrid physics–ML models for flow, heat transfer, and mass transfer; multiphase flow: boiling, condensation, two-phase instabilities, and critical heat flux (CHF); Flow-induced vibration, thermal mixing, stratification, and flow distribution; Reduced-order modeling, operator learning, and emulation of high-fidelity simulations; Sensor data + ML for flow monitoring, anomaly detection, and state estimation; Data assimilation and uncertainty quantification for thermal–hydraulic predictions; Experimental + simulation data fusion, benchmark datasets and validation practices; Interpretability, robustness, and V&V of data-driven tools for safety-relevant use. Types of submissions we expect:

We invite original research articles, applied case studies (experimental, numerical, or combined), review papers, technical notes, and dataset/benchmark papers. Contributions with clear validation, uncertainty reporting, and reproducible workflows (data/code when possible) are especially encouraged.

Dr. Xiuzhong Shen
Prof. Dr. Naibin Jiang
Guest Editors

Dr. Guangyun Min
Guest Editor Assistant

Manuscript Submission Information

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Submitted manuscripts should not have been published previously, nor be under consideration for publication elsewhere (except conference proceedings papers). All manuscripts are thoroughly refereed through a single-blind peer-review process. A guide for authors and other relevant information for submission of manuscripts is available on the Instructions for Authors page. Fluids is an international peer-reviewed open access monthly journal published by MDPI.

Please visit the Instructions for Authors page before submitting a manuscript. The Article Processing Charge (APC) for publication in this open access journal is 1800 CHF (Swiss Francs). Submitted papers should be well formatted and use good English. Authors may use MDPI's English editing service prior to publication or during author revisions.

Keywords

  • machine learning
  • reduced-order modeling
  • thermal–hydraulics
  • multiphase flow
  • CFD simulation
  • fluid–structure interaction

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Published Papers (1 paper)

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Research

15 pages, 4244 KB  
Article
Numerical Study on the Effect of Structural Parameters on Flow and Heat Transfer Characteristics of Helical Cruciform Fuel
by Yixiang Zou, Yue Ma, Jingwen Yan, Chang’e Wu, Qifeng Lv and Jianqiang Shan
Fluids 2026, 11(6), 141; https://doi.org/10.3390/fluids11060141 - 5 Jun 2026
Viewed by 159
Abstract
As a high-performance innovative fuel rod design, helical cruciform fuel (HCF) exhibits significant advantages over conventional circular fuel rods, such as a larger heat transfer area per unit volume, enhanced fluid flow and heat transfer characteristics due to its helical geometry, and a [...] Read more.
As a high-performance innovative fuel rod design, helical cruciform fuel (HCF) exhibits significant advantages over conventional circular fuel rods, such as a larger heat transfer area per unit volume, enhanced fluid flow and heat transfer characteristics due to its helical geometry, and a periodic self-supporting configuration. These attributes make it a highly promising option for future advanced reactor applications. Using the SST k-ω turbulence model, this study numerically investigates single-phase flow and heat transfer in a triangularly arranged 7-rod compact HCF fuel bundle, focusing on the effects of cross-sectional geometry and helical pitch on its three-dimensional flow and heat transfer behavior. Numerical results indicate that reducing the concave arc radius R increases the heat transfer surface area of the rod bundle, effectively enhancing heat transfer performance and reducing wall temperature; decreasing the helical pitch substantially strengthens fluid mixing. However, when the concave arc radius R becomes excessively small, the cross-flow intensity exhibits a local minimum in the concave region, resulting in a significant degradation of convective heat transfer capability in this area. These findings provide valuable insights for the structural optimization and design selection of HCF. Full article
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