Numerical Investigation and Analytical Modeling of MHD Pressure Drop in Lead–Lithium Flows Within Rectangular Ducts Under Variable Magnetic Field for Nuclear Fusion Reactors

Key findings from this study

This research indicates that:

• Analytical predictions of MHD pressure drop align with CFD simulations for Lead-Lithium flows in rectangular ducts under external magnetic fields.
• Magnetic field intensity directly modulates total pressure drop in conducting fluid channels.
• The analytical framework provides sufficiently accurate estimations for preliminary breeding blanket design purposes.

Overview

This work investigates magnetohydrodynamic (MHD) pressure drop in Lead-Lithium eutectic alloy flows through rectangular ducts under variable external magnetic fields. The Dual-Cooled Lead-Lithium breeding blanket concept integrates liquid metal for heat transfer and tritium breeding with helium gas cooling. MHD effects—including eddy current induction and resulting Lorentz forces—generate additional pressure losses and reduce thermal efficiency in tokamak environments.

Methods and approach

An analytical model estimated total MHD-induced pressure losses along the channel for varying magnetic field intensities. Computational fluid dynamics simulations using COMSOL Multiphysics provided validation data. Comparisons between analytical predictions and CFD results clarified the influence of applied magnetic field intensity on overall pressure drop.

Results

The analytical model successfully predicted MHD pressure losses across different magnetic field intensities when benchmarked against CFD simulations. The validation process confirmed the analytical approach's accuracy for estimating pressure drop behavior in rectangular conduits containing electrically conducting fluids. Results demonstrate that magnetic field intensity exerts a quantifiable influence on total pressure drop magnitude, with the analytical framework capturing this relationship sufficiently for design-stage applications.

Implications

The validated analytical model provides preliminary design tools for fusion reactor breeding blankets without requiring full computational simulation. Accurate MHD pressure loss estimation enables optimization of coolant circulation systems and thermal management strategies in future tokamak designs. The methodology may facilitate rapid evaluation of alternative magnet configurations and fluid compositions during conceptual engineering phases.

Scope and limitations

This summary is based on the study abstract and available metadata. It does not include a full analysis of the complete paper, supplementary materials, or underlying datasets unless explicitly stated. Findings should be interpreted in the context of the original publication.