Challenges in reactor core thermal-hydraulics: subchannel analysis, CFD modeling and rod bundle CHF

Articles in the same Issue

1. Contents/Inhalt
2. Contents
3. Summaries/Kurzfassungen
4. Summaries
5. Editorial
6. Challenges in reactor core thermal-hydraulics: subchannel analysis, CFD modeling and rod bundle CHF
7. Technical Contributions/Fachbeiträge
8. Subchannel analysis and correlation of the Rod Bundle Heat Transfer (RBHT) steam cooling experimental data
9. CFD analysis on mixing effects of spacer grids with different dimples and sizes for advanced fuel assemblies
10. An experimental investigation on dynamics and heat transfer associated with a single droplet impacting on a hot surface above the Leidenfrost point temperature
11. Study on effects of mixing vane grids on coolant temperature distribution by subchannel analysis
12. Reflood experiments in rod bundles with flow blockages due to clad ballooning
13. The effect of spacer grid critical component on pressure drop under both single and two phase flow conditions
14. Numerical method improvement for a subchannel code
15. Numerical investigation on the characteristics of two-phase flow in fuel assemblies with spacer grid
16. Effects of axial power shapes on CHF locations in a single tube and in rod bundle assemblies
17. CFD evaluation on the thermohydraulic characteristics of tube support plates in steam generator
18. Analysis of heat transfer under high heat flux nucleate boiling conditions
19. Review of the correlation developments and a new concept based on mixing mechanism for heat transfer enhancement of spacer grids
20. A comparison of the CFD simulation results in 5 × 5 sub-channels with mixing grids using different turbulence models
21. Simulation of isothermal multi-phase fuel-coolant interaction using MPS method with GPU acceleration
22. RELAP5 investigation on subchannel flow instability