Advances in the Thermal Hydraulics of Reactor Engineering and Reactor Safety Analyses
A special issue of Energies (ISSN 1996-1073). This special issue belongs to the section "B4: Nuclear Energy".
Deadline for manuscript submissions: closed (18 July 2024) | Viewed by 2554
Special Issue Editors
Interests: thermal hydraulics of reactor engineering; theoretical modeling and simulation; high-temperature two-phase flow and heat transfer; pebble flow gas-cooled reactor core; reactor safety analysis; particle flow
Interests: two-phase flow; loss of coolant accident; density instability in ocean condition; thermal hydraulics of reactor engineering; tokamak plasma
Special Issue Information
Dear Colleagues,
The Guest Editor is inviting submissions to a Special Issue of Energies on the subject area of “Advance in Thermal Hydraulics of Reactor Engineering and Reactor Safety Analysis”. The most crucial factor for fission nuclear energy is reactor safety. Thermal hydraulics continues to be an important area of exploration when it comes to comprehending the safety operation and design of nuclear systems. Specifically，the thermal-hydraulic analysis of thermodynamics, fluid mechanics, and heat transfer can be used to determine critical reactor design parameters. In addition, the technology for reactor accident (flow boiling crisis, flow instability, and loss of coolant accidents) mitigation and prevention is necessary for the system’s optimization and safety assessments of nuclear power plants. The reliability of thermal-hydraulic computer codes in predicting consequences of severe accidents and the specification of appropriate accident management strategies are main challenges in mitigating potential severe accidents in nuclear safety analyses.
This Special Issue invites all researchers from nuclear reactor academia and industry to share their latest important results to advance the fields of thermal hydraulics and reactor safety. Submissions of high-quality research papers on the above topics are welcome, particularly those demonstrating a high level of academic discussion and communication. Topics of interest for publication include but are not limited to the following:
- Nuclear thermal hydraulics;
- Nuclear safety analysis;
- Thermodynamics;
- Fluid mechanics;
- Heat transfer;
- Flow boiling crisis;
- Flow instability;
- Loss of coolant accident;
- Computational fluid dynamics;
- Severe accident analysis.
Dr. Nan Gui
Dr. Xiaoxi Zhang
Guest Editors
Manuscript Submission Information
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