ORIGINAL RESEARCH
Published on 07 Jan 2025
Prediction of critical heat flux in a rod bundle channel with spacer grids based on the Eulerian two-fluid model
doi 10.3389/fenrg.2024.1366902
- 109 views
- Frontiers in Energy Research
- Nuclear Energy
- Research Topics
- Experimental and Simulation Research on Nuclear Reactor Thermal-Hydraulics, Volume II
Experimental and Simulation Research on Nuclear Reactor Thermal-Hydraulics, Volume II
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Frontiers in Energy Research
- Nuclear Energy
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