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Nuclear Engineering

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Nuclear Engineering

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Research Frontiers in Neutron Transport in Heterogeneous Media

Development of advanced Monte Carlo and deterministic methods for accurate neutron flux prediction in complex fuel assemblies and reactor geometries.

Anomalous Neutron Streaming Through Void Networks
Spectral Hardening in Multilayered Shielding Geometries
Neutronic Chaos at Material Interfaces
Self-Shielding Effects in Composite Fuel Assemblies
Leakage Prediction Across Fractal-Like Microstructures
Coupled Transport in Thermally Evolving Heterogeneous Systems
Angular Dependence in Anisotropic Scattering Media
Transient Neutron Behavior in Laminated Barriers
Resonance Absorption in Spatially Modulated Matrices
Neutron Flux Shadowing in Complex Three-Dimensional Lattices

All Nuclear Engineering PhD categories