energies-logo

Journal Browser

Journal Browser

Latest Advances and Prospects of Thermal-Hydraulics in Nuclear Power System

A special issue of Energies (ISSN 1996-1073). This special issue belongs to the section "B4: Nuclear Energy".

Deadline for manuscript submissions: closed (31 January 2025) | Viewed by 4302

Special Issue Editors


E-Mail Website
Guest Editor
State Key Laboratory of Multiphase Flow in Power Engineering, Xi’an Jiaotong University, Xian-Ning West Road 28#, Xi’an 710049, China
Interests: flow and heat transfer of multiphase flow; flow and heat transfer in porous media; reactor thermal-hydraulics and nuclear power safety; big data and data-driven
Special Issues, Collections and Topics in MDPI journals

E-Mail Website
Guest Editor
School of Nuclear Science and Engineering, Shanghai Jiao Tong University, Shanghai 200240, China
Interests: reactor thermal-hydraulics and nuclear power safety; boiling heat transfer; critical heat flux; flow and boiling induced vibration; intelligent measurement technique

E-Mail
Guest Editor Assistant
CNNC Key Laboratory on Severe Accident in Nuclear Power Safety, China Nuclear Power Engineering Co., Ltd., Beijing 100840, China
Interests: reactor thermal-hydraulics; safety analysis and PRA for light water reactors; currently with a focus on severe accident research including experimental study and code development

Special Issue Information

Dear Colleagues,

Nuclear energy is one of the carbon-free energy sources that are highly efficient. It has been one of the primary sources of energy in the world and represents a promising source for the increasing future demand.

Thermal hydraulics studies in nuclear power systems are essential to the design and safety demands of nuclear reactors, which mainly focused on the issues of how fluids flow, behave, and interact with different structures to transfer heat between the structure and the fluid. Key phenomena include conduction, convection, radiation heat transfer, phase change, and single- and multi-phase flows in nuclear power systems. As technologies move from water-cooled light water reactors to a myriad of options for cooling in new reactor designs, studies in this area cover water, gas, molten salt, and liquid metal coolants for advanced fission and fusion systems, as well as transport and mixing processes that occur inside reactor containment structures and in environmental systems, and both computational and experimental thermal hydraulic characterizations are at the forefront of maintaining reactor safety.

The Special Issue aims to provide a platform for the latest high-quality progress in the area of Thermal-Hydraulics in Nuclear Power Systems. The scope of the Special Issue includes all aspects of theoretical derivation and analysis, model development and simulation, experimental investigation and engineering application. Submitted articles should contribute to a better understanding of the thermal-hydraulic phenomena and their physics laws. The Special Issue will also consider the publication of state-of-the-art reviews to highlight the possible future direction from the professional insights of world-renowned researchers. Scientific and technical contributions include, but are not limited to:

  • Fundamental thermal-hydraulics;
  • Experimental thermal-hydraulics;
  • Computational thermal-hydraulics;
  • Code development and applications;
  • Thermal hydraulics and safety;
  • Thermal hydraulics of advanced reactors;
  • Thermal hydraulics of nuclear installations;
  • Severe accidents, phenomena, modeling, and experiments.

Dr. Liangxing Li
Dr. Shengjie Gong
Guest Editors

Yidan Yuan
Guest Editor Assistant

Manuscript Submission Information

Manuscripts should be submitted online at www.mdpi.com by registering and logging in to this website. Once you are registered, click here to go to the submission form. Manuscripts can be submitted until the deadline. All submissions that pass pre-check are peer-reviewed. Accepted papers will be published continuously in the journal (as soon as accepted) and will be listed together on the special issue website. Research articles, review articles as well as short communications are invited. For planned papers, a title and short abstract (about 100 words) can be sent to the Editorial Office for announcement on this website.

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. Energies is an international peer-reviewed open access semimonthly 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 2600 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

  • nuclear power
  • nuclear reactor
  • thermal-hydraulics
  • lead-cooled fast reactors
  • sodium-cooled fast reactors
  • high-temperature gas-cooled reactors
  • supercritical water reactors
  • molten salt reactors
  • pressurized water reactors
  • boiling water reactors
  • two-phase flow
  • heat transfer
  • critical heat flux
  • pressure drops
  • flow resistance
  • experiments
  • numerical simulations
  • accident analysis
  • verification and validation
  • numerical models development

Benefits of Publishing in a Special Issue

  • Ease of navigation: Grouping papers by topic helps scholars navigate broad scope journals more efficiently.
  • Greater discoverability: Special Issues support the reach and impact of scientific research. Articles in Special Issues are more discoverable and cited more frequently.
  • Expansion of research network: Special Issues facilitate connections among authors, fostering scientific collaborations.
  • External promotion: Articles in Special Issues are often promoted through the journal's social media, increasing their visibility.
  • e-Book format: Special Issues with more than 10 articles can be published as dedicated e-books, ensuring wide and rapid dissemination.

Further information on MDPI's Special Issue policies can be found here.

Published Papers (5 papers)

Order results
Result details
Select all
Export citation of selected articles as:

Research

Jump to: Review

15 pages, 6244 KiB  
Article
Experimental Studies on the Thermal Hydraulics of a Fuel Column for a Gas-Cooled Micro Reactor (GMR)
by Zheng Huang, Miaoxin Jiao, Jian Jiao, Yanyu Sun, Yanfang Xue, Shuoting Zhang and Dingsheng Wang
Energies 2025, 18(8), 2039; https://doi.org/10.3390/en18082039 - 16 Apr 2025
Viewed by 144
Abstract
A thermal-hydraulic test facility is designed to explore the thermal-hydraulic characteristics inside a fuel assembly under normal operating conditions, thereby providing data for validating computer codes for a novel gas-cooled micro reactor (GMR). The primary loop supplies helium at a prototypic temperature and [...] Read more.
A thermal-hydraulic test facility is designed to explore the thermal-hydraulic characteristics inside a fuel assembly under normal operating conditions, thereby providing data for validating computer codes for a novel gas-cooled micro reactor (GMR). The primary loop supplies helium at a prototypic temperature and pressure to the test section containing a full-size fuel assembly. The experimental procedure and the test conditions were elaborated. Pre-test simulations using the COMSOL Multiphysics 5.0 software yield detailed 3D distributions of the temperature and flow fields inside the test section, which were employed to guide the positioning of thermocouples. The maximum temperature and its locus, the pressure drop of the coolant through the test section, and the helium temperature at the outlet duct were determined. The simulation indicates that the “mixer” component can effectively enhance the mixing of helium in the rear plenum and reduce the outlet helium temperature. The measured data of preliminary tests at the facility agree well with the predicted values, which proves the accuracy and reliability of the thermocouples. An unheated section at the end of the heating rods leads to a relatively large deviation of the results on the last measuring plane. Full article
Show Figures

Figure 1

16 pages, 1898 KiB  
Article
Comparative Analysis on the Characteristics of Liquid Lead and Lead–Bismuth Eutectic as Coolants for Fast Reactors
by Mian Xing, Jihong Fan, Feng Shen, Daogang Lu, Linsen Li, Hui Yu and Jin Fan
Energies 2025, 18(3), 596; https://doi.org/10.3390/en18030596 - 27 Jan 2025
Viewed by 1048
Abstract
With the increasing global demand for sustainable energy, the importance of advanced nuclear technologies, such as fourth-generation reactors, has become increasingly prominent. Fourth-generation reactors often use non-water coolants, among which liquid lead and lead–bismuth eutectics (LBEs) are highly promising, making lead-cooled fast reactors [...] Read more.
With the increasing global demand for sustainable energy, the importance of advanced nuclear technologies, such as fourth-generation reactors, has become increasingly prominent. Fourth-generation reactors often use non-water coolants, among which liquid lead and lead–bismuth eutectics (LBEs) are highly promising, making lead-cooled fast reactors (LFRs) a popular area of research internationally. On the basis of extensive analysis and comparison conducted previously, this article summarizes and analyzes the advantages, problems, and differences in lead and LBE as LFR coolants. Overall, both lead and LBE have excellent neutronic characteristics, good heat transfer performance, and chemical inertness, and make LFRs highly efficient in nuclear fuel utilization, inherently safe, and relatively simplified in design. However, both of them corrode materials severely and produce highly toxic 210Po, which are the problems that need to be considered for further engineering development. Moreover, LBE has a lower melting point, which allows a wider temperature range and lower insulation requirements in its design, making it easier to achieve engineering and miniaturization under the same conditions. Lead has a lower cost, is less corrosive to materials, and produces less 210Po, which makes it a more ideal coolant for future development. Full article
Show Figures

Figure 1

14 pages, 3014 KiB  
Article
Analysis of Heat Transfer Performance Impact for Passive Containment Air-Cooling System Radiation Plates
by Hongliang Wang, Yu Feng, Mingrui Yu, Yong Guo, Wei Li, Qiang Guo and Yidan Yuan
Energies 2025, 18(2), 389; https://doi.org/10.3390/en18020389 - 17 Jan 2025
Viewed by 590
Abstract
In addition to convective heat transfer, radiation heat transfer constitutes a significant component of the thermal performance of Passive Containment Air-Cooling System (PAS). The installation of radiation plates within the PAS flow channel enhances the convective heat transfer area between the wall and [...] Read more.
In addition to convective heat transfer, radiation heat transfer constitutes a significant component of the thermal performance of Passive Containment Air-Cooling System (PAS). The installation of radiation plates within the PAS flow channel enhances the convective heat transfer area between the wall and the air, an effect that should not be overlooked. ANSYS Fluent was employed to investigate how the placement and quantity of radiation plates influence the heat transfer efficiency of PAS. The computational results indicate that radiation plates can substantially enhance the thermal performance of PAS. Specifically, when a radiation plate is positioned 0.9 m from the inner wall of the concrete shell, an improvement in PAS heat transfer power by as much as 34.4% can be achieved. However, it was observed that increasing the number of radiation plates has a minimal impact on overall performance; thus, utilizing multiple plates does not further augment the PAS heat transfer capability. Nonetheless, incorporating several radiation plates may contribute to lowering the temperature of the concrete shell. Based on this research, it can be concluded that strategically arranging radiation plates significantly improves the PAS heat transfer capacity. While multiple radiation plates do not provide additional enhancements to heat transfer efficiency under normal conditions, they remain a viable option for mitigating concrete shell temperatures during accident scenarios. Full article
Show Figures

Figure 1

17 pages, 5534 KiB  
Article
Non-Contact Thermophysical Property Measurements of High-Temperature Corium Through Aerodynamic Levitation
by Yaopeng Gong, Li Zhang, Yidan Yuan and Weimin Ma
Energies 2025, 18(1), 136; https://doi.org/10.3390/en18010136 - 1 Jan 2025
Viewed by 659
Abstract
The thermophysical properties of corium are critical for improving the predictive accuracy of severe accident analysis codes. However, due to the high melting temperature and high volatility of corium, thermophysical property measurements are extremely challenging, resulting in a significant lack of data. This [...] Read more.
The thermophysical properties of corium are critical for improving the predictive accuracy of severe accident analysis codes. However, due to the high melting temperature and high volatility of corium, thermophysical property measurements are extremely challenging, resulting in a significant lack of data. This study presents a non-contact measurement facility based on the aerodynamic levitation technique, enabling the measurement of the density, surface tension, and viscosity of corium components at temperatures exceeding 3000 K. Density is measured based on the axisymmetric ellipsoid assumption of levitated drops, while the surface tension and viscosity are determined using the drop oscillation method. Experimental results for key corium components, including ZrO2 and a UO2-ZrO2 mixture, are presented, addressing data gaps in the thermophysical properties of UO2-containing materials. Full article
Show Figures

Figure 1

Review

Jump to: Research

18 pages, 9714 KiB  
Review
A Review on Ex-Vessel Melt Retention Measures Adopted in Light Water Reactors
by Yidan Yuan, Xiaodong Huo, Wei Li, Qiang Guo, Li Zhang, Yong Guo and Jie Pei
Energies 2024, 17(24), 6220; https://doi.org/10.3390/en17246220 - 10 Dec 2024
Viewed by 862
Abstract
As the cornerstone of severe accident management strategy, either in-vessel or ex-vessel retention of core melt (IVR or EVR) plays a pivotal role in the stabilization and termination of a severe accident and ultimately secures the safety goal of “Practical elimination of large [...] Read more.
As the cornerstone of severe accident management strategy, either in-vessel or ex-vessel retention of core melt (IVR or EVR) plays a pivotal role in the stabilization and termination of a severe accident and ultimately secures the safety goal of “Practical elimination of large radioactive release” for light water reactors. In contrast to the IVR measures that are more or less identical in reactor designs, the EVR measures are quite different from design to design. This study intended to give a critical review on the EVR measures adopted in the reactor designs of VVER-1000, EPR, ESBWR, EU-APR1400 and APWR. The review study began with a general description of the existing EVR measures, including their principles, operational procedures and research efforts. We then focused our discussions on the pros and cons of each EVR measure through the comparisons with the IVR and with the others in terms of simplicity, reliability and economy. We finally tried to identify the remaining issues and uncertainties in the qualification of the EVR measures, based on which potential design improvements and future research needs were recommended. Full article
Show Figures

Figure 1

Back to TopTop