thesis aims to investigate the neutronic and thermal-hydraulic performance of a chloride-based molten salt fast reactor (MSFR) and to evaluate the effect of introducing sodium fluoride (NaF) as a fuel salt additive.

1. Introduction 2. Literature Review 2.1. Overview of Molten Salt Fast Reactors 2.2. Neutronic and Thermal-Hydraulic Performance 2.3. Chloride-Based MSFR Studies 3. Theoretical Background 3.1. Neutron Physics in MSFR 3.2. Thermal-Hydraulic Principles 3.3. Salt Chemistry and Interaction 4. Methodology 4.1. Reactor Design Parameters 4.2. Simulation Tools and Models 4.3. Data Collection and Analysis 5. Neutronic Performance Analysis 5.1. Neutron Flux Distribution 5.2. Reactivity and Control Systems 5.3. Safety Margins and Limitations 6. Thermal-Hydraulic Performance Evaluation 6.1. Heat Transfer Mechanisms 6.2. Temperature Profiles and Dynamics 6.3. Coolant Flow and Stability 7. Evaluation of Sodium Fluoride Additive 7.1. Chemical Properties of NaF 7.2. Impact on Neutronic Performance 7.3. Influence on Thermal-Hydraulics 8. Discussion and Implications 8.1. Comparing Performance with and without NaF 8.2. Implications for Reactor Safety 8.3. Future Research Directions 9. Conclusion

1. How does the introduction of sodium fluoride (NaF) as a fuel salt additive affect the neutronic performance and safety margins in chloride-based molten salt fast reactors? 2. What impact does sodium fluoride (NaF) have on the thermal-hydraulic performance, including temperature profiles and coolant flow stability, in chloride-based molten salt fast reactors?