Thermal-Hydraulic Challenges in Advanced Nuclear Reactors
A special issue of Energies (ISSN 1996-1073). This special issue belongs to the section "B4: Nuclear Energy".
Deadline for manuscript submissions: closed (18 June 2024) | Viewed by 10052
Special Issue Editor
Interests: nuclear thermal hydraulic; thermal management; heat and mass transfer; two-phase flow
Special Issues, Collections and Topics in MDPI journals
Special Issue Information
Dear Colleagues,
Nuclear engineering and technology play a vital role in achieving low carbon emission goals worldwide, while providing reliable, baseload power to the world economy. Nuclear energy today provides over a third of the world’s low-carbon electricity. For nuclear energy to continue to play its role in a sustainable global energy supply, both technical and institutional innovations are needed. This includes a new generation of reactors, such as advanced light water reactors, small modular reactors, including molten salt reactors and fast reactors, and even the pursuit of fusion energy.
Nuclear reactor thermal hydraulics involves the study of fluid flow, heat and mass transfer applied to nuclear technologies. It is of fundamental importance in both the design and safety operation of nuclear reactors. We are pleased to invite you to submit papers to the journal Energies for a Special Issue titled “Thermal–Hydraulic Challenges in Advanced Nuclear Reactors”. The purpose of the issue is to advance our understanding of flow and heat transfer phenomena in nuclear reactor systems to support new-generation reactor design as well as the safety of existing reactors. Experiments, system code analyses, and CFD simulations are all welcome.
The core topics include but are not limited to:
- Single- and two-phase phenomena (convective heat transfer, boiling, onset of flow instability, flow regimes, single- and two-phase pressure drop);
- Enhancement of boiling heat transfer;
- Interphase transfer processes in two-phase flow;
- Transport of radioactive trace species and aerosols in bubbles;
- Condensation in two-phase flow systems with noncondensables;
- Hydrodynamics of countercurrent two-phase flow;
- Hydrodynamics of three-phase flow systems.
Prof. Dr. Naihua Wang
Guest Editor
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Keywords
- boiling
- CFD
- condensation
- countercurrent flow
- experiment
- flow instability
- heat transfer
- interphase transfer
- mixing
- nuclear reactor
- safety
- stratification
- subchannel
- two-phase flow
- verification and validation
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